Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption, 13482-13483 [E9-6845]

Download as PDF mstockstill on PROD1PC66 with NOTICES 13482 Federal Register / Vol. 74, No. 58 / Friday, March 27, 2009 / Notices hours for reporting and 17,726 hours for recordkeeping)]. 7. Abstract: 10 CFR part 40 establishes requirements for licenses for the receipt, possession, use and transfer of radioactive source and byproduct material. NRC Form 484 is used to report certain groundwater monitoring data required by 10 CFR part 40 for uranium recovery licensees. The application, reporting and recordkeeping requirements are necessary to permit the NRC to make a determination on whether the possession, use, and transfer of source and byproduct material is in conformance with the Commission’s regulations for protection of public health and safety. Submit, by May 26, 2009, comments that address the following questions: 1. Is the proposed collection of information necessary for the NRC to properly perform its functions? Does the information have practical utility? 2. Is the burden estimate accurate? 3. Is there a way to enhance the quality, utility, and clarity of the information to be collected? 4. How can the burden of the information collection be minimized, including the use of automated collection techniques or other forms of information technology? A copy of the draft supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O–1 F21, Rockville, Maryland 20852. OMB clearance requests are available at the NRC worldwide Web site: https:// www.nrc.gov/public-involve/doccomment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments submitted in writing or in electronic form will be made available for public inspection. Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed. Comments submitted should reference Docket No. NRC–2009–0133. You may submit your comments by any of the following methods. Electronic comments: Go to https:// www.regulations.gov and search for Docket No. NRC–2009–0133. Mail comments to NRC Clearance Officer, Gregory Trussell (T–5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. Questions about the information collection requirements may be directed to the NRC Clearance Officer, Gregory Trussell VerDate Nov<24>2008 17:13 Mar 26, 2009 Jkt 217001 (T–5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, by telephone at 301–415–6445, or by e-mail to INFOCOLLECTS.Resource@NRC.GOV. Dated at Rockville, Maryland, this 20th day of March, 2009. For the Nuclear Regulatory Commission. Gregory Trussell, NRC Clearance Officer, Office of Information Services. [FR Doc. E9–6847 Filed 3–26–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–271; NRC–2009–0121] Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Exemption 1.0 Background Entergy Nuclear Operations, Inc. (Entergy or the licensee) is the holder of Facility Operating License No. DPR–28, which authorizes operation of the Vermont Yankee Nuclear Power Station (VY). The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the Nuclear Regulatory Commission (NRC or the Commission) now or hereafter in effect. The facility consists of a boiling-water reactor located in Windham County, Vermont. 2.0 Request/Action Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.48, requires that nuclear power plants that were licensed before January 1, 1979, of which VY is one, must satisfy the requirements of 10 CFR Part 50, Appendix R, Section III.G.2, which requires to have a minimum of 20 feet separation between redundant cable trays. In an NRC letter dated December 1, 1986, the NRC granted the licensee the exemption from the provisions of 10 CFR Part 50, Appendix R, Section III.G.2, which in part permitted a reduction in minimum separation distance between cable trays in the northwest corner of Fire Zone RB–3 of the reactor building to 18 feet. VY has identified that the actual minimum physical separation distance between the cable trays is actually 17 feet–7.5 inches. In summary, the letter dated July 11, 2008, Agencywide Documents Access and Management System (ADAMS) accession number ML082030154, as supplemented on November 20, 2008, PO 00000 Frm 00088 Fmt 4703 Sfmt 4703 ADAMS accession number ML083370180, Entergy on behalf of VY, requested a revision to the exemption from the provisions of 10 CFR Part 50, Appendix R, Section III.G.2, dated December 1, 1986 (ML011620492), which in part permitted a reduction in minimum separation distance between cable trays in the northwest corner of Fire Zone RB–3 of the Reactor Building to 18 feet. VY has requested a revision of the existing exemption to permit the actual minimum separation distance of 17 feet–7.5 inches. 3.0 Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. One of these special circumstances, described in 10 CFR 50.12(a)(2)(ii), is that the application of the regulation is not necessary to achieve the underlying purpose of the rule. The underlying purpose of Subsection III.G.2 of 10 CFR Part 50, Appendix R, is to ensure that one of the redundant trains necessary to achieve and maintain hot shutdown conditions remains free of fire damage in the event of a fire. The NRC staff reviewed the licensee’s evaluation in support of the subject exemption request and concludes that the further reduction in minimum separation distance is sufficient to maintain an adequate level of safety to meet the requirements of 10 CFR 50.12(a)(2)(ii) in that the application of the regulation is not necessary to achieve the underlying purpose of the rule. Authorized by Law This exemption would permit a reduced minimum separation distance of 17 feet–7.5 inches, instead of ‘‘more than 20 feet’’ between cable trays in Fire Zone RB–3, elevation 252 feet, provided all other passive and active forms of protection (e.g., lack of combustible fuel loading or fire hazards, fire detectors and automatic fire suppression system) are provided and maintained in accordance with III.G.2. As stated above, 10 CFR 50.12 allows the NRC to grant exemptions from the requirements of 10 CFR Part 50. The NRC staff has determined that granting of the licensee’s proposed exemption will not result in a violation of the Atomic Energy Act of 1954, as amended, or the E:\FR\FM\27MRN1.SGM 27MRN1 Federal Register / Vol. 74, No. 58 / Friday, March 27, 2009 / Notices mstockstill on PROD1PC66 with NOTICES Commission’s regulations. Therefore, the exemption is authorized by law. No Undue Risk to Public Health and Safety One of the underlying purposes of 10 CFR Part 50, Appendix R Section III.G is to protect safe shutdown capability. This is done by ensuring that one train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station(s) is free of fire damage. III.G.2 provides the following means to ensure that a redundant train of safe shutdown equipment is free of fire damage, where redundant trains are located in the same fire area: a. Separation of cables and equipment by a fire barrier having a 3-hour rating, b. Separation of cables and equipment by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards and with fire detectors and an automatic fire suppression system in the fire area, or c. Enclosure of cables and equipment in a fire barrier having a 1-hour rating and with fire detectors and an automatic fire suppression system in the fire area. Entergy has indicated that the cable trays will be separated by a minimum distance of 17 feet–7.5 inches for a horizontal distance of approximately 10 feet and that the remaining length of cable trays will be separated by more than 17 feet–7.5 inches. Entergy has also indicated that transient combustibles and hot work controls have been enhanced since the exemption was originally granted. This was accomplished by designating Fire Zone RB–3 as a ‘‘Level 2’’ combustible control area, which limits combustibles to moderate quantities and hot work requires prior review and approval of a fire protection engineer. Additionally, Entergy has stated that a pre-action automatic sprinkler system is provided beneath the lowest level of cable trays and above the top level of cable trays in Fire Zone RB–3 and that manual suppression equipment is provided throughout Fire Zone RB–3 in the form of accessible fire hose stations and portable fire extinguishers. A fire detection system is provided in the form of Ionization-type smoke detectors. According to Entergy, the fire protection systems are functionally unchanged from what was previously included in the December 1, 1986, evaluation. The licensee has indicated that 1-hour 3M Interam fire barriers were installed to protect certain raceways in the northwest corner of elevation 252 feet however; no credit for the barriers has been requested as part of this exemption. VerDate Nov<24>2008 17:13 Mar 26, 2009 Jkt 217001 Based on the above, the exemption to allow the reduced minimum separation distance of 17 feet–7.5 inches in lieu of the 20 feet dimension specified in III.G.2 a, b, and c, does not increase the probability of postulated accidents or undue risk. Based on the combination of a lack of combustible fuel loading and ignition sources, room configuration and the separation distance of 17 feet– 7.5 inches, the overall level of protection and defense in depth has been shown to meet or exceed the intent of the requirements included in III.G.2 and equivalent with regard to safe shutdown capability following a fire. Therefore, there is no additional risk to public health and safety. Consistent With Common Defense and Security The proposed exemption would permit a reduced minimum separation distance between cable trays in a select area in lieu of meeting the separation requirements specified in III.G.2. This change has no relation to security issues. Therefore, the common defense and security is not impacted by this exemption. Special Circumstances Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances is not necessary to achieve the underlying purpose of the rule. Part of the underlying purpose of 10 CFR Part 50, Appendix R Section III.G is to assure safe shutdown capability. Entergy states that the active and passive fire protection features that were included in the original exemption remain functionally unchanged. This review determined that the reduction in minimum separation distance does not adversely affect the level of safety at the plant given the physical configuration of the cable trays, existing suppression and detection systems and the lack of combustible fuel loading in the area. The combination of these safeguards is sufficient to maintain safe shutdown capability in the event of a fire even at the reduced separation distance of 17 feet–7.5 inches. Since the underlying purpose of 10 CFR Part 50, Appendix R Section III.G to protect safe shutdown capability is achieved, the special circumstances required by 10 CFR 50.12(a)(2)(ii) for the granting of an exemption from 10 CFR Part 50, Appendix R Section III.G.2 exist. 4.0 Conclusion Accordingly, the Commission has determined that special circumstances are present and that, pursuant to 10 CFR PO 00000 Frm 00089 Fmt 4703 Sfmt 4703 13483 50.12(a), the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security levels intended by the rule for Nuclear Power Plants. Therefore, the Commission hereby grants Entergy an exemption from the requirements of III.G.2 b of 10 CFR Part 50, Appendix R, which is required by 10 CFR 50.48(b) for plants licensed to operate before January 1, 1979, to VY. Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment (74 FR 11612). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 19th day of March 2009. For the Nuclear Regulatory Commission. Robert A. Nelson, Acting Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E9–6845 Filed 3–26–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0138] Proposed Generic Communication; Pre-Licensing Construction Activities at Proposed Uranium Recovery Facilities AGENCY: Nuclear Regulatory Commission. ACTION: Notice of opportunity for public comment. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is proposing to issue a regulatory issue summary (RIS) to present its interpretation of the regulations governing the commencement of construction found in 10 CFR 40.32(e). This Federal Register notice is available through the NRC’s Agencywide Documents Access and Management System (ADAMS) under accession number ML083470668. DATES: Comment period expires April 27, 2009. Comments submitted after this date will be considered if it is practical to do so, but assurance of consideration cannot be given except for comments received on or before this date. ADDRESSES: Submit written comments to the Chief, Uranium Recovery Licensing Branch, Division of Waste Management and Environmental Protection, Office of Federal and State Materials and Environmental Management Programs, U.S. Nuclear E:\FR\FM\27MRN1.SGM 27MRN1

Agencies

[Federal Register Volume 74, Number 58 (Friday, March 27, 2009)]
[Notices]
[Pages 13482-13483]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-6845]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket No. 50-271; NRC-2009-0121]


Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power 
Station; Exemption

1.0 Background

    Entergy Nuclear Operations, Inc. (Entergy or the licensee) is the 
holder of Facility Operating License No. DPR-28, which authorizes 
operation of the Vermont Yankee Nuclear Power Station (VY). The license 
provides, among other things, that the facility is subject to all 
rules, regulations, and orders of the Nuclear Regulatory Commission 
(NRC or the Commission) now or hereafter in effect.
    The facility consists of a boiling-water reactor located in Windham 
County, Vermont.

2.0 Request/Action

    Title 10 of the Code of Federal Regulations (10 CFR), Part 50, 
Section 50.48, requires that nuclear power plants that were licensed 
before January 1, 1979, of which VY is one, must satisfy the 
requirements of 10 CFR Part 50, Appendix R, Section III.G.2, which 
requires to have a minimum of 20 feet separation between redundant 
cable trays.
    In an NRC letter dated December 1, 1986, the NRC granted the 
licensee the exemption from the provisions of 10 CFR Part 50, Appendix 
R, Section III.G.2, which in part permitted a reduction in minimum 
separation distance between cable trays in the northwest corner of Fire 
Zone RB-3 of the reactor building to 18 feet. VY has identified that 
the actual minimum physical separation distance between the cable trays 
is actually 17 feet-7.5 inches.
    In summary, the letter dated July 11, 2008, Agencywide Documents 
Access and Management System (ADAMS) accession number ML082030154, as 
supplemented on November 20, 2008, ADAMS accession number ML083370180, 
Entergy on behalf of VY, requested a revision to the exemption from the 
provisions of 10 CFR Part 50, Appendix R, Section III.G.2, dated 
December 1, 1986 (ML011620492), which in part permitted a reduction in 
minimum separation distance between cable trays in the northwest corner 
of Fire Zone RB-3 of the Reactor Building to 18 feet. VY has requested 
a revision of the existing exemption to permit the actual minimum 
separation distance of 17 feet-7.5 inches.

3.0 Discussion

    Pursuant to 10 CFR 50.12, the Commission may, upon application by 
any interested person or upon its own initiative, grant exemptions from 
the requirements of 10 CFR Part 50 when (1) the exemptions are 
authorized by law, will not present an undue risk to public health or 
safety, and are consistent with the common defense and security; and 
(2) when special circumstances are present. One of these special 
circumstances, described in 10 CFR 50.12(a)(2)(ii), is that the 
application of the regulation is not necessary to achieve the 
underlying purpose of the rule.
    The underlying purpose of Subsection III.G.2 of 10 CFR Part 50, 
Appendix R, is to ensure that one of the redundant trains necessary to 
achieve and maintain hot shutdown conditions remains free of fire 
damage in the event of a fire.
    The NRC staff reviewed the licensee's evaluation in support of the 
subject exemption request and concludes that the further reduction in 
minimum separation distance is sufficient to maintain an adequate level 
of safety to meet the requirements of 10 CFR 50.12(a)(2)(ii) in that 
the application of the regulation is not necessary to achieve the 
underlying purpose of the rule.

Authorized by Law

    This exemption would permit a reduced minimum separation distance 
of 17 feet-7.5 inches, instead of ``more than 20 feet'' between cable 
trays in Fire Zone RB-3, elevation 252 feet, provided all other passive 
and active forms of protection (e.g., lack of combustible fuel loading 
or fire hazards, fire detectors and automatic fire suppression system) 
are provided and maintained in accordance with III.G.2. As stated 
above, 10 CFR 50.12 allows the NRC to grant exemptions from the 
requirements of 10 CFR Part 50. The NRC staff has determined that 
granting of the licensee's proposed exemption will not result in a 
violation of the Atomic Energy Act of 1954, as amended, or the

[[Page 13483]]

Commission's regulations. Therefore, the exemption is authorized by 
law.

No Undue Risk to Public Health and Safety

    One of the underlying purposes of 10 CFR Part 50, Appendix R 
Section III.G is to protect safe shutdown capability. This is done by 
ensuring that one train of systems necessary to achieve and maintain 
hot shutdown conditions from either the control room or emergency 
control station(s) is free of fire damage. III.G.2 provides the 
following means to ensure that a redundant train of safe shutdown 
equipment is free of fire damage, where redundant trains are located in 
the same fire area:
    a. Separation of cables and equipment by a fire barrier having a 3-
hour rating,
    b. Separation of cables and equipment by a horizontal distance of 
more than 20 feet with no intervening combustibles or fire hazards and 
with fire detectors and an automatic fire suppression system in the 
fire area, or
    c. Enclosure of cables and equipment in a fire barrier having a 1-
hour rating and with fire detectors and an automatic fire suppression 
system in the fire area.
    Entergy has indicated that the cable trays will be separated by a 
minimum distance of 17 feet-7.5 inches for a horizontal distance of 
approximately 10 feet and that the remaining length of cable trays will 
be separated by more than 17 feet-7.5 inches. Entergy has also 
indicated that transient combustibles and hot work controls have been 
enhanced since the exemption was originally granted. This was 
accomplished by designating Fire Zone RB-3 as a ``Level 2'' combustible 
control area, which limits combustibles to moderate quantities and hot 
work requires prior review and approval of a fire protection engineer.
    Additionally, Entergy has stated that a pre-action automatic 
sprinkler system is provided beneath the lowest level of cable trays 
and above the top level of cable trays in Fire Zone RB-3 and that 
manual suppression equipment is provided throughout Fire Zone RB-3 in 
the form of accessible fire hose stations and portable fire 
extinguishers. A fire detection system is provided in the form of 
Ionization-type smoke detectors.
    According to Entergy, the fire protection systems are functionally 
unchanged from what was previously included in the December 1, 1986, 
evaluation. The licensee has indicated that 1-hour 3M Interam fire 
barriers were installed to protect certain raceways in the northwest 
corner of elevation 252 feet however; no credit for the barriers has 
been requested as part of this exemption.
    Based on the above, the exemption to allow the reduced minimum 
separation distance of 17 feet-7.5 inches in lieu of the 20 feet 
dimension specified in III.G.2 a, b, and c, does not increase the 
probability of postulated accidents or undue risk. Based on the 
combination of a lack of combustible fuel loading and ignition sources, 
room configuration and the separation distance of 17 feet-7.5 inches, 
the overall level of protection and defense in depth has been shown to 
meet or exceed the intent of the requirements included in III.G.2 and 
equivalent with regard to safe shutdown capability following a fire. 
Therefore, there is no additional risk to public health and safety.

Consistent With Common Defense and Security

    The proposed exemption would permit a reduced minimum separation 
distance between cable trays in a select area in lieu of meeting the 
separation requirements specified in III.G.2. This change has no 
relation to security issues. Therefore, the common defense and security 
is not impacted by this exemption.

Special Circumstances

    Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), 
are present whenever application of the regulation in the particular 
circumstances is not necessary to achieve the underlying purpose of the 
rule. Part of the underlying purpose of 10 CFR Part 50, Appendix R 
Section III.G is to assure safe shutdown capability. Entergy states 
that the active and passive fire protection features that were included 
in the original exemption remain functionally unchanged. This review 
determined that the reduction in minimum separation distance does not 
adversely affect the level of safety at the plant given the physical 
configuration of the cable trays, existing suppression and detection 
systems and the lack of combustible fuel loading in the area. The 
combination of these safeguards is sufficient to maintain safe shutdown 
capability in the event of a fire even at the reduced separation 
distance of 17 feet-7.5 inches. Since the underlying purpose of 10 CFR 
Part 50, Appendix R Section III.G to protect safe shutdown capability 
is achieved, the special circumstances required by 10 CFR 
50.12(a)(2)(ii) for the granting of an exemption from 10 CFR Part 50, 
Appendix R Section III.G.2 exist.

4.0 Conclusion

    Accordingly, the Commission has determined that special 
circumstances are present and that, pursuant to 10 CFR 50.12(a), the 
exemption is authorized by law, will not present an undue risk to the 
public health and safety, and is consistent with the common defense and 
security levels intended by the rule for Nuclear Power Plants. 
Therefore, the Commission hereby grants Entergy an exemption from the 
requirements of III.G.2 b of 10 CFR Part 50, Appendix R, which is 
required by 10 CFR 50.48(b) for plants licensed to operate before 
January 1, 1979, to VY.
    Pursuant to 10 CFR 51.32, the Commission has determined that the 
granting of this exemption will not have a significant effect on the 
quality of the human environment (74 FR 11612).
    This exemption is effective upon issuance.

    Dated at Rockville, Maryland, this 19th day of March 2009.

    For the Nuclear Regulatory Commission.
Robert A. Nelson,
Acting Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. E9-6845 Filed 3-26-09; 8:45 am]
BILLING CODE 7590-01-P
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