Notice of Availability of Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding Relocation of Departure From Nucleate Boiling Parameters to the Core Operating Limits Report for Combustion Engineering Pressurized Water Reactors Using the Consolidated Line Item Improvement Process, 31108-31112 [E7-10786]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 72, Number 107 (Tuesday, June 5, 2007)]
[Notices]
[Pages 31108-31112]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-10786]


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NUCLEAR REGULATORY COMMISSION


Notice of Availability of Model Safety Evaluation and Model 
License Amendment Request on Technical Specification Improvement 
Regarding Relocation of Departure From Nucleate Boiling Parameters to 
the Core Operating Limits Report for Combustion Engineering Pressurized 
Water Reactors Using the Consolidated Line Item Improvement Process

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of availability.

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SUMMARY: Notice is hereby given that the staff of the U.S. Nuclear 
Regulatory Commission (NRC) has prepared a model license amendment 
request (LAR), model safety evaluation (SE), and model proposed no 
significant hazards consideration (NSHC) determination related to 
changes to Standard Technical Specifications (STSs) for Combustion 
Engineering Pressurized Water Reactors (PWRs), NUREG-1432, Revision 
3.1. This change allows the numerical limits located in technical 
specification (TS) 3.4.1, ``RCS Pressure, Temperature, and Flow 
[Departure from Nucleate Boiling (DNB)] Limits'' to be replaced with 
references to the Core Operating Limits Report (COLR). Associated 
changes are also included for the TS 3.4.1 Bases, and TS 5.6.3 ``Core 
Operating Limits Report (COLR).'' The Technical Specifications Task 
Force (TSTF) proposed these changes to the TS in TSTF-487 Revision 0, 
``Relocate DNB Parameters to the COLR.'' This request was slightly 
modified in TSTF-487 Revision 1 on May 4, 2007.
    The purpose of the model SE, LAR, and NSHC is to permit the NRC to 
efficiently process amendments to incorporate these changes into plant-
specific TSs for Combustion Engineering PWRs. Licensees of nuclear 
power reactors to which the models apply can request amendments 
conforming to the models. In such a request, a licensee should confirm 
the applicability of the model LAR, model SE and NSHC determination to 
its plant.

DATES: The NRC staff issued a Federal Register Notice (72 FR 12223, 
March 15, 2007) which provided a model LAR, model SE, and model NSHC 
for comment related to replacing the DNB parameters in TS 3.4.1 with 
references to the COLR. The revised model LAR, revised model SE, and 
unchanged NSHC associated with this change are provided in this notice. 
The NRC can most efficiently consider applications based upon the model 
LAR, which references the model SE, if the application is submitted 
within one year of this Federal Register Notice.

FOR FURTHER INFORMATION CONTACT: William Cartwright, Mail Stop: O-12H2, 
Division of Inspection and Regional Support, Office of Nuclear Reactor 
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone (301) 415-8345.

SUPPLEMENTARY INFORMATION:

Background

    This change was made using the Consolidated Line Item Improvement 
Process [CLIIP] for STS Changes for Power Reactors, issued on March 20, 
2000 as Regulatory Information Summary 2000-006. This document can be 
viewed on the NRC's public Web page at https://www.nrc.gov/reading-rm/
doc-collections/gen-comm/reg-issues/2000/ri00006.html. The CLIIP is 
intended to improve the efficiency and transparency of NRC licensing 
processes by processing proposed changes to the STS in a manner that 
supports subsequent license amendment applications. Those licensees 
opting to apply for the subject change to TSs are responsible for 
reviewing the NRC staff's evaluation, referencing the applicable 
technical justifications, and providing any necessary plant-specific 
information. This notice finalizes the model LAR and model SE. Each 
amendment application made in response to the notice of availability 
will be processed and noticed in accordance with applicable NRC rules 
and procedures.
    The purpose of this change is to allow Combustion Engineering PWR 
licensees to recalculate cycle specific departure from nucleate boiling 
(DNB) parameter limits in the COLR using NRC-approved

[[Page 31109]]

methodologies. With this alternative, reload license amendments for the 
sole purpose of updating the cycle specific DNB parameter limits will 
be unnecessary. By letter dated June 20, 2005, the TSTF proposed these 
changes for incorporation into the STSs as TSTF-487 Revision 0 (ADAMS 
Accession No. ML051860302), followed by TSTF-487 Revision 1 on May 4, 
2007 (ADAMS Accession No. ML071240259) . These changes are based on the 
NRC Generic Letter 88-16 ``Removal of Cycle-Specific Parameter Limits 
from Technical Specifications'' (ADAMS Accession No. ML041830597).
    ADAMS documents are accessible electronically from the Agency-wide 
Documents Access and Management System's (ADAMS) Public Electronic 
Reading Room on the Internet at the NRC Web site https://www.nrc.gov/
reading-rm/adams.html. Persons who do not have access to ADAMS or who 
encounter problems in accessing the documents located in ADAMS should 
contact the NRC Public Document Room Reference staff by telephone at 1-
800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.

Applicability

    These proposed changes will revise the limiting condition for 
operation (LCO) 3.4.1, surveillance requirement (SR) 3.4.1, and TS 
5.6.3 for Combustion Engineering PWRs. Licensees adopting this change 
may also have to change the bases associated with TS 3.4.1 under their 
bases control program. To efficiently process incoming license 
amendment applications, the NRC staff requests that each licensee using 
the CLIIP to adopt the changes addressed by TSTF-487 Revision 1, submit 
a LAR that adheres to the following model. Any variations from the 
model LAR should be explained in the licensee's submittal. Variations 
from the approach recommended in this notice may require additional 
time and resources by the NRC staff for review. Significant variations 
from the approach, or inclusion of additional changes to the license, 
will result in NRC staff rejection of the submittal. Instead, licensees 
desiring significant variations and/or additional changes should submit 
a LAR that does not request to adopt TSTF-487.

Public Notices

    The staff issued a Federal Register Notice (72 FR 12223, March 15, 
2007) that requested public comment on the NRC's pending action to 
allow relocation of DNB parameters to the COLR for Combustion 
Engineering PWRs using the CLIIP. One response was received from the 
TSTF (ADAMS Accession No. ML071030076). The comments are summarized and 
discussed below:
    1. Comment: A statement did not need to be added to TS section 
5.6.3 regarding the requirement to perform the COLR calculations at 
rated thermal power (RTP). The justification for this was that it was a 
restatement of existing regulatory requirements. In addition, the 
wording proposed by the NRC staff was unclear to licensees. It was 
proposed in the comment that licensees make a commitment as part of 
their amendment request instead of making changes to the TS 
administrative controls section 5.6.3.
    Response: The NRC staff discussed this issue at a public meeting 
held on March 22, 2007. In response to that meeting, the TSTF provided 
modified wording that was acceptable to the NRC staff for TS section 
5.6.3 in TSTF-487 Revision 1, on May 4, 2007 (ADAMS Accession No. 
ML071240259). The modified wording has been incorporated into the model 
SE.
    2. Comment: References to the TS bases should be removed from the 
model application as the bases are under the licensee's control, not 
required to be approved by the NRC, and not required as part of TS 
amendments.
    Response: The Code of Federal Regulations (10 CFR 50.36 (a)) states 
``A summary of the basis or reasons for such specifications, other than 
those covering administrative controls, shall also be included in the 
application, but shall not become part of the technical 
specifications.'' The regulations supporting inclusion of the bases 
into TS amendments are described in 10 CFR 50.90, which states that 
applications for amendments should be made ``fully describing the 
changes desired, and following as far as applicable, the form 
prescribed for original applications.'' Providing the bases changes 
with the amendment assists in assuring a common understanding of the 
changed TS requirements between the licensee and the NRC staff. As the 
licensee is required to maintain and update the TS bases, providing the 
updated changes to the NRC as part of an amendment request does not 
constitute an additional burden. This comment was not incorporated.
    3. Comment: The oath or affirmation statement in the model 
application was not consistent with RIS 2001-18, ``Requirements for 
Oath or Affirmation.''
    Response: The model application was revised to be consistent with 
RIS 2001-18.
    4. Comment: The last portion of the applicability section discussed 
the consequences of a licensee submitting variations from the approach 
described in the model application. The last sentence published in the 
notice for comment reads ``Instead, licensees desiring significant 
variations and/or additional changes should submit a LAR that does not 
claim to adopt TSTF-487.'' The comment requested to revise that 
sentence to ``Instead, licensees desiring significant variations and/or 
additional changes should submit a LAR that does not claim to adopt 
TSTF-487 under the CLIIP.'' The purpose of this change would be to 
allow licensees to adopt model applications to facilitate NRC staff 
review as part other amendment processes (for example, a license 
amendment to adopt standard technical specifications).
    Response: The CLIIP allows licensees to submit amendment requests 
that closely adopt model applications developed under a streamlined 
process. Amendments proposing to adopt TSTFs that substantially deviate 
from model applications are not appropriate for a streamlined review 
process. For amendments that substantially deviate from a model 
application, licensees can reference or follow approved TSTF model 
applications to support their amendment requests. These requests will 
receive the normal NRC staff review process. This comment was not 
incorporated.
    The NRC staff has proceeded with announcing the availability of the 
change in this notice with some minor changes to the model LAR and 
model SE as a result of public comments. Licensees wishing to adopt the 
change will submit an application in accordance with applicable rules 
and other regulatory requirements. The NRC staff will, in turn, issue 
for each application a notice of consideration of issuance of amendment 
to facility operating license(s), a proposed NSHC determination, and an 
opportunity for a hearing. A notice of issuance of an amendment to 
operating license(s) will also be issued to announce the revised 
requirements for each plant that applies for and receives the requested 
change.

    Dated at Rockville, Maryland, this 29th day of May, 2007.

    For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and 
Regional Support, Office of Nuclear Reactor Regulation.

    For inclusion on the technical specification Web page the following 
example of an application was prepared by the NRC staff to facilitate 
the adoption of Technical Specifications Task Force (TSTF) Traveler 
TSTF-487,

[[Page 31110]]

Revision 1 ``relocate DNB parameters to the COLR.'' The model provides 
the expected level of detail and content for an application to adopt 
TSTF-487, Revision 1. Licensees remain responsible for ensuring that 
their actual application fulfills their administrative requirements as 
well as NRC regulations.

U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, 
DC 20555.
SUBJECT: Plant name, Docket No. 50-[xxx,] Re: Application for technical 
specification improvement to adopt TSTF-487, Revision 1, ``relocate DNB 
parameters to the COLR''

    Dear Sir or Madam: In accordance with the provisions of Section 
50.90 of Title 10 of the Code of Federal Regulations (10 CFR), 
[LICENSEE] is submitting a request for an amendment to the technical 
specifications (TS) for [PLANT NAME, UNIT NOS.]. The proposed changes 
would allow [PLANT NAME] to replace the DNB numeric limits in TS with 
references to the core operating limits report (COLR).
    The changes are consistent with NRC-approved Industry Technical 
Specification Task Force (TSTF) Standard Technical Specification Change 
Traveler, TSTF-487 Revision 1. The availability of this TS improvement 
was announced in the Federal Register on [DATE] [ ] FR [ ]) as part of 
the consolidated line item improvement process (CLIIP).
    Enclosure 1 provides a description and assessment of the proposed 
changes, as well as confirmation of applicability. Enclosure 2 provides 
the existing TS pages and TS Bases marked-up to show the proposed 
changes. Enclosure 3 provides final TS pages and TS Bases pages. 
[LICENSEE] requests approval of the proposed license amendment by 
[DATE], with the amendment being implemented [BY DATE OR WITHIN X 
DAYS]. In accordance with 10 CFR 50.91, a copy of this application, 
with enclosures, is being provided to the designated [STATE] Official.
    I declare [or certify, verify, state] under penalty of perjury that 
the foregoing is true and correct. Executed on [date] [Signature].

[Note that request may be notarized in lieu of using this oath or 
affirmation statement].
If you should have any questions regarding this submittal, please 
contact [ ].

     Sincerely,

Name, Title

Enclosures:

    1. Description and Assessment of Proposed Changes.
    2. Proposed Technical Specification Changes and Technical 
Specification Bases Changes.
    3. Final Technical Specification and Bases pages.

cc: NRR Project Manager, Regional Office, Resident Inspector, State 
Contact, ITSB Branch Chief.

1.0 Description

    This letter is a request to amend Operating License(s) [LICENSE 
NUMBER(S)] for [PLANT/UNIT NAME(S)]. The proposed changes would revise 
Technical Specification (TS) 3.4.1, ``RCS Pressure, Temperature, and 
Flow [Departure from Nucleate Boiling (DNB)] Limits,'' the bases for TS 
3.4.1, and TS 5.6.3 ``Core Operating Limits Report (COLR),'' to allow 
[PLANT NAME] to place the DNB numeric limits with references to the 
COLR.
    Technical Specification Task Force (TSTF) change traveler TSTF-487, 
Revision 1 ``Relocate DNB Parameters to the COLR'' was announced for 
availability in the Federal Register on [DATE] as part of the 
consolidated line item improvement process (CLIIP).

2.0 Proposed Changes

    Consistent with NRC-approved TSTF-487 Revision 1, the following 
changes are proposed:
     Revise the limiting conditions for operation and 
surveillance requirements in TS 3.4.1 to replace the DNB numeric limits 
for reactor coolant pressure, temperature, and flow with references to 
limits for those parameters calculated in the COLR.
     Revise the bases associated with TS 3.4.1 to reflect that 
the DNB numeric limits are contained in the COLR.
     Revise TS 5.6.3 to add the methodology requirements for 
calculating the DNB numeric limits in the COLR.

3.0 Background

    The background for this application is as stated in the model SE in 
NRC's Notice of Availability published on [DATE ] ([ ] FR [ ]), and 
TSTF-487, Revision 1.

4.0 Technical Analysis

    [LICENSEE] has reviewed Generic Letter 88-16, and the model SE 
published on [DATE] ([ ] FR [ ]) as part of the CLIIP Notice for 
Comment. [LICENSEE] has applied the methodology in Generic Letter 88-16 
to develop the proposed TS changes. [LICENSEE] has also concluded that 
the justifications presented in TSTF-487, Revision 1 and the model SE 
prepared by the NRC staff are applicable to [PLANT, UNIT NOS.], and 
justify this amendment for the incorporation of the changes to the 
[PLANT] TS.

5.0 Regulatory Analysis

    A description of this proposed change and its relationship to 
applicable regulatory requirements and guidance was provided in the NRC 
Notice of Availability published on [DATE] ([ ] FR [ ]), the NRC Notice 
for Comment published on [DATE] ([ ] FR [ ]), and TSTF-487, Revision 1.

6.0 No Significant Hazards Consideration

    [LICENSEE] has reviewed the proposed no significant hazards 
consideration determination published in the Federal Register on [DATE] 
([ ] FR [ ]) as part of the CLIIP. [LICENSEE] has concluded that the 
proposed determination presented in the notice is applicable to [PLANT] 
and the determination is hereby incorporated by reference to satisfy 
the requirements of 10 CFR 50.91(a).

7.0 Environmental Evaluation

    [LICENSEE] has reviewed the environmental consideration included in 
the model SE published in the Federal Register on [DATE] ([ ] FR [ ]) 
as part of the CLIIP. [LICENSEE] has concluded that the staff's 
findings presented therein are applicable to [PLANT] and the 
determination is hereby incorporated by reference for this application.

Proposed Safety Evaluation,
U.S Nuclear Regulatory Commission,
Office of Nuclear Reactor Regulation.

Consolidated Line Item Improvement Technical Specification Task Force 
(TSTF)
Change TSTF-487, Revision 1, RELOCATE DNB PARAMETERS TO THE COLR

1.0 Introduction

    By application dated [Date], (Ref. 7.1), the [Name of Licensee] 
(the licensee) requested changes to the Technical Specifications (TS) 
for the [Name of Facility].
    The proposed changes would revise TS 3.4.1, the associated bases of 
TS 3.4.1, and TS 5.6.3 to replace the departure from nucleate boiling 
(DNB) parameters limits in Technical Specifications (TSs) with 
references to the Core Operating Limits Report (COLR). These changes 
would allow the licensee to recalculate the DNB parameter limits using 
NRC-approved methodologies without the need for a license amendment 
request (LAR).

[[Page 31111]]

    The proposed changes include the following:
     Change TS 3.4.1, ``RCS Pressure, Temperature, and Flow 
[Departure from Nucleate Boiling (DNB)] Limits,'' Limiting Conditions 
for Operation (LCO) 3.4.1 and the associated Surveillance Requirements 
(SRs) to replace the specific limit values of RCS pressurizer pressure, 
cold leg temperature, and RCS total flow rate with ``the limits 
specified in the COLR.''
     Change the bases for LCO 3.4.1 to reflect that the DNB 
limits are specified in the COLR.
     Change Section 5.6.3 of TS, ``Core Operating Limits Report 
(COLR)'' to include the NRC approved methodologies and requirements 
used to calculate the DNB limits.
    Generic Letter (GL) 88-16 titled ``Removal of Cycle-Specific 
Parameter Limits from Technical Specifications'' (Ref. 7.2) is the 
regulatory guidance for this change.

2.0 Regulatory Evaluation

    The Commission's regulatory requirements related to the content of 
Technical Specifications are specified in Title 10 CFR (Code of Federal 
Regulations), Section 50.36, ``Technical Specifications.'' 10 CFR 
50.36(c)(2)(i) defines that limiting conditions for operation are the 
lowest functional capability or performance levels of equipment 
required for safe operation of the facility. For the DNB parameters, 10 
CFR 50.36(c)(2)(ii)(B) Criterion 2 applies, which requires that TS LCOs 
be established for each process variable, design feature, or operating 
restriction that is an initial condition of a design basis accident or 
transient analysis that either assumes the failure of or presents a 
challenge to the integrity of a fission product barrier.
    LARs are required for each fuel cycle design that results in 
changes to parameter limits specified in TS. To meet 10 CFR 
50.36(c)(2)(ii) requirements and alleviate the need for LARs to update 
parameter limits every fuel cycle, the NRC issued GL 88-16 with 
specific guidance for replacing the limit values for cycle-specific 
parameters in the TSs with references to an owner-controlled document, 
namely, the COLR. The guidance in GL 88-16 includes the following three 
actions:
    1. The addition of the definition of a named formal report (i.e., 
Core Operating Limits Report) in TS that includes the values of cycle-
specific parameter limits that have been established using an NRC-
approved methodology and consistent with all applicable limits of the 
safety analyses.
    2. The addition of an administrative reporting requirement (in TS 
5.6.3) to submit the formal report on cycle-specific parameter limits 
to the Commission for information.
    3. The modification of individual TS to note that the specific 
parameters shall be maintained within the limits provided in the 
defined formal report (COLR).
    The proposed change has been evaluated against GL 88-16 and found 
to be consistent with that regulatory guidance.

3.0 Technical Evaluation

    TS LCO 3.4.1 specifies the limit values of the DNB parameters to 
assure that the pressurizer pressure, the RCS cold leg temperature, and 
RCS flow rate during operation at rated thermal power (RTP) will be 
maintained within the limits assumed in the safety analyses in the 
final safety analysis report (FSAR). The safety analyses of anticipated 
operational occurrences (AOOs) and accidents assume initial conditions 
within the envelope of normal steady state operation at the RTP to 
demonstrate that the applicable acceptance criteria, including the 
specified acceptable fuel design limits (such as DNB ratio) and RCS 
pressure boundary design conditions, are met for each event analyzed. 
The TS limits placed on the DNB-related parameters ensure that these 
parameters, when appropriate measurement uncertainties are applied, 
will be bounded by those assumed in the safety analyses, and thereby 
provide assurance that the applicable acceptance criteria will not be 
violated should a transient or accident occur while operating at the 
RTP.
    It is essential to safety that the plant is operated within the DNB 
parameter limits. This change retains the requirement to maintain the 
plant within the DNB parameter limits in LCO 3.4.1 along with the SR 
verification for each of the DNB parameters. As these parameter limits 
are calculated using NRC-approved methodologies and are consistent with 
all applicable limits of the plant safety analyses, this change does 
not affect nuclear safety.
    TS 5.6.3, ``Core Operating Limits Report (COLR),'' specifies that 
the core operating limits shall be determined such that all applicable 
limits of the safety analyses are met, and that the analytical methods 
used to determine the core operating limits shall be those previously 
reviewed and approved by the NRC. This change modifies the list of NRC 
approved methodologies in TS 5.6.3 to include those used to calculate 
the DNB limits on pressurizer pressure, RCS cold leg temperature, and 
RCS total flow rate. The limit values of these parameters in the COLR 
will comply with existing operating fuel cycle analysis requirements, 
and are initial conditions assumed in safety analyses. Replacing of the 
DNB parameter values with references to the COLR does not lessen the 
requirement for compliance with all applicable limits.
    Any revisions to the safety analyses that require prior NRC 
approval will be identified by the 10 CFR 50.59 review process. TS 
5.6.3 also specifies that the COLR, including any midcycle revisions or 
supplements, shall be provided upon issuance for each reload cycle to 
the NRC. This will allow NRC staff to continue trending the information 
even though prior NRC approval of the changes to these limits will not 
be required.
    10 CFR 50.36 requires LCOs to contain the lowest functional 
capability or performance levels of equipment for safe operation of the 
facility. The NRC staff finds that the proposed change to LCO 3.4.1 
referencing the specific values of the DNB parameter limits in TS in 
the COLR continues to meet the regulatory requirement of 10 CFR 
50.36(c)(2)(ii)(B) (Criterion 2), and follows the guidance described in 
GL 88-16. The NRC staff, therefore, concludes that this change is 
acceptable.
    For safety analyses of transients or accidents, various sections of 
Chapter 15 of the Standard Review Plan (Ref. 7.3) specify that the 
reactor is initially at the RTP plus uncertainty, and the RCS flow is 
at nominal design flow including the measurement uncertainty. If one or 
more DNB parameter limits change, and these changes do not support the 
RTP, a license amendment would be required to either reduce the RTP or 
limit the plant operation at a level below the RTP. 10 CFR 50 Appendix 
K requires that the loss of coolant accident analysis be performed at 
102% of the RTP. Other plant-specific analyses can contain an initial 
condition to be performed at RTP. To insure a clear understanding of 
this requirement TS 5.6.3.c. has been reworded to add the underlined 
text: ``The core operating limits shall be determined assuming 
operation at RATED THERMAL POWER such that all applicable limits * * 
*.''

4.0 State Consultation

    In accordance with the Commission's regulations, the [------] State 
official was notified of the proposed issuance of the amendment. The 
State official had [(1) no comments or (2) the following comments--with 
subsequent disposition by the staff].

[[Page 31112]]

5.0 Environmental Consideration

    The amendment[s] change[s] a requirement with respect to the 
installation or use of a facility component located within the 
restricted area as defined in 10 CFR part 20 or surveillance 
requirements. The NRC staff has determined that the amendment involves 
no significant increase in the amounts, and no significant change in 
the types, of any effluents that may be released offsite, and that 
there is no significant increase in individual or cumulative 
occupational radiation exposure. The Commission has previously issued a 
proposed finding that the amendment involves no significant hazards 
consideration and there has been no public comment on such finding 
published [DATE] ([ ] FR [ ]). Accordingly, the amendment meets the 
eligibility criteria for categorical exclusion set forth in 10 CFR 
51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact 
statement or environmental assessment need be prepared in connection 
with the issuance of the amendment.

6.0 Conclusion

    The NRC staff has reviewed this proposed change to replace the 
values of the DNB parameters in TS with references to the COLR. This 
change will allow the licensee the flexibility to manage operating and 
core design margins associated with the DNB parameters without the need 
for cycle-specific LARs. Any future revisions to safety analyses that 
require prior NRC approval will be identified by the 10 CFR 50.59 
review process. Based on this evaluation the NRC staff concludes that 
this change meets the regulatory requirements of 10 CFR 50.36, follows 
the guidance described in GL 88-16, and is acceptable.

7.0 References

    7.1 License Amendment Request dated [MMM, DD, YYYY], [Title of 
Amendment Request], ADAMS Accession No. [MLXXXXXXXXX]
    7.2 Generic Letter 88-16 dated October 4, 1988, ``Removal of Cycle-
Specific Parameter Limits from Technical Specifications,'' ADAMS 
Accession No. ML041830597
    7.3 NUREG-0800, ``Standard Review Plan.''

Proposed No Significant Hazards Consideration Determination

    Description of Amendment Request: [Plant name] requests adoption of 
an approved change to the standard technical specifications (STS) for 
Combustion Engineering Pressurized Water Reactor (PWR) Plants (NUREG-
1432) and plant-specific technical specifications (TS), to allow 
replacing the departure from nucleate boiling (DNB) parameter limits 
with references to the core operating limits report (COLR) in 
accordance with Generic Letter 88-16, ``Removal of Cycle Specific 
Parameter Limits from Technical Specifications,'' dated October 4, 
1988. The changes are consistent with NRC approved Industry/Technical 
Specification Task Force (TSTF) Standard Technical Specification Change 
Traveler, TSTF-487, Revision 1.
    Basis for proposed no-significant-hazards-consideration 
determination: As required by 10 CFR 50.91(a), an analysis of the issue 
of no-significant-hazards-consideration is presented below:
    Criterion 1: Does the Proposed Change Involve a Significant 
Increase in the Probability or Consequences of an Accident Previously 
Evaluated?
    Response: No.
    The proposed amendment replaces the limit values of the reactor 
coolant system (RCS) DNB parameters (i.e., pressurizer pressure, RCS 
cold leg temperature, and RCS flow rate) in TS with references to the 
COLR, in accordance with the guidance of Generic Letter 88-16, to allow 
these parameter limit values to be recalculated without a license 
amendment. The proposed amendment does not involve operation of any 
required structures, systems, or components (SSCs) in a manner or 
configuration different from those previously recognized or evaluated. 
The cycle-specific values in the COLR must be calculated using the NRC-
approved methodologies listed in TS 5.6.3, ``Core Operating Limits 
Report (COLR).'' Replacing the RCS DNB parameter limits in TS with 
references to the COLR will maintain existing operating fuel cycle 
analysis requirements. Because these parameter limits are determined 
using the NRC-approved methodologies, the acceptance criteria 
established for the safety analyses of various transients and accidents 
will continue to be met. Therefore, neither the probability nor 
consequences of any accident previously evaluated will be increased by 
the proposed change.
    Therefore, operation of the facility in accordance with the 
proposed amendment does not involve a significant increase in the 
probability or consequences of an accident previously evaluated.
    Criterion 2: Does the Proposed Change Create the Possibility of a 
New or Different Kind of Accident from any Previously Evaluated?
    Response: No.
    The proposed amendment to replace the RCS DNB parameter limits in 
TS with references to the COLR does not involve a physical alteration 
of the plant, nor a change or addition of a system function. The 
proposed amendment does not involve operation of any required SSCs in a 
manner or configuration different from those previously recognized or 
evaluated. No new failure mechanisms will be introduced by the proposed 
change.
    Therefore, the proposed amendment does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    Criterion 3: Does the Proposed Change Involve a Significant 
Reduction in the Margin of Safety?
    Response: No.
    The proposed amendment to replace the RCS DNB parameter limits in 
TS with references to the COLR will continue to maintain the margin of 
safety. The DNB parameter limits specified in the COLR will be 
determined based on the safety analyses of transients and accidents, 
performed using the NRC-approved methodologies that show that, with 
appropriate measurement uncertainties of these parameters accounted 
for, the acceptance criteria for each of the analyzed transients are 
met. This provides the same margin of safety as the limit values 
currently specified in the TS. Any future revisions to the safety 
analyses that require prior NRC approval are identified per the 10 CFR 
50.59 review process.
    Therefore, the proposed amendment would not involve a significant 
reduction in a margin of safety.
    Based on the staff's review of the licensee's analysis, the staff 
concludes that the proposed amendment presents no significant hazards 
consideration under the standards set forth in 10 CFR 50.92(c) and, 
accordingly, a finding of ``no significant hazards consideration'' is 
justified.
    Dated at Rockville, Maryland, this ---- day of --------, 2007.

    For the Nuclear Regulatory Commission.

Project Manager, Plant Licensing Branch [ ], Division of Operating 
Reactor Licensing, Office of Nuclear Reactor Regulation.

[FR Doc. E7-10786 Filed 6-4-07; 8:45 am]
BILLING CODE 7590-01-P