ML090490010
| ML090490010 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/11/2009 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Waldrep B Carolina Power & Light Co |
| Saba, F E, NRR/DORL/LPL2-2 301-415-1447 | |
| References | |
| TAC MD9184, TAC MD9185 | |
| Download: ML090490010 (16) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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March 11, 2009
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- ""'l~ Ijenjamin Waldrep, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING REVISIONS TO TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS 3.6.1.6.1 AND 3.6.1.6.2, CONCERNING TESTING OF SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS (TAC NOS. MD9184 AND MD9185)
Dear Mr. Waldrep:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 251 to Renewed Facility Operating License No. DPR-71, and Amendment No. 279 to Renewed Facility Operating License No. DPR-62, Brunswick Steam Electric Plant, Units 1 and 2, respectively. The amendments are in response to your application dated July 7, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081980056), as supplemented by letters dated December 17, 2008 (ADAMS Accession No. ML083657358), and March 9, 2009. The amendments revise Surveillance Requirement (SR) 3.6.1.6.1 to add a new requirement to verify that each vacuum breaker is closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open and revises SR 3.6.1.6.2 by removing the requirement to perform functional testing of each vacuum breaker within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following an operation that causes any of the vacuum breakers to open.
A copy of the related safety evaluation is also enclosed. A notice of issuance will be included in the NRC's biweekly Federal Register notice.
Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosures:
- 1. Amendment No. 251 to Renewed License No. DPR-71
- 2. Amendment No. 279 to Renewed License No. DPR-62
- 3. Safety Evaluation cc w/enclosures: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 251 Renewed License No. DPR-71
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated July 7,2008, as supplemented by letters dated December 17, 2008, and March 9, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-71 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 251, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
,~f7{?~7m ~...
Thomas H. BOy<;;cite~-
Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance:
~1arch 11, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 251 RENEWED FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace Page 4 of Renewed Operating License DPR-71 with the attached Page 4.
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.6-19 3.6-19
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 251, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
For Surveillance Requirements (SRs) that are new in Amendment 203 to Renewed Facility Operating License DPR-71, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 203. For SRs that existed prior to Amendment 203, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 203.
(a)
Effective June 30, 1982, the surveillance requirements listed below need not be completed until July 15, 1982. Upon accomplishment of the surveillances, the provisions of Technical Specification 4.0.2 shall apply.
Specification 4.3.3.1, Table 4.3.3-1, Items 5.a and 5.b (b)
Effective July 1, 1982, through July 8, 1982, Action statement "a" of Technical Specification 3.8.1.1 shall read as follows:
ACTION:
- a. With either one offsite circuit or one diesel generator of the above required AC. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining AA sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.aA within two hours and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter; restore at least two offsite circuits and four diesel generators to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(3)
Deleted by Amendment No. 206.
D.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security Plan, Revision 2," and "Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006, and "Guard Training and Qualification Plan, Revision 0,"
submitted by letter dated September 30, 2004.
Renewed License No. DPR-71 Amendment No. 251
Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1
NOTE------------------------------
Not required to be met for vacuum breakers that are open during Surveillances.
Verify each vacuum breaker is closed.
14 days Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after any discharge of steam to the suppression chamber from any source Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open SR 3.6.1.6.2 Perform a functional test of each required vacuum breaker.
92 days Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after any discharge of steam to the suppression chamber from the SRVs SR 3.6.1.6.3 Verify the full open setpoint of each required vacuum breaker is $ 0.5 psid.
24 months Brunswick Unit 1 3.6-19 Amendment No. 251
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 279 Renewed License No. DPR-62
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated July 7,2008, as supplemented by letters dated December 17, 2008, and March 9, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-62 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 279, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION s:h~
---//1/2 Thomas H. Boy
,Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Operating License and Technical Specifications Date of Issuance: ~1arch 11, 2009
ATTACHMENT TO LICENSE AMENDMENT NO. 279 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace Page 3 of Renewed Operating License DPR-62 with the attached Page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.6-19 3.6-19
as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source, and special nuclear materials without restriction to chemical of physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70 to posses, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Brunswick Steam Electric Plant, Unit Nos. 1 and 2, and H. B. Robinson Steam Electric Plant, Unit No.2 (6)
Carolina Power & Light Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Report dated November 22, 1977, as supplemented April 1979, June 11, 1980, December 30, 1986, December 6, 1989, July 28, 1993, and February 10, 1994 respectively, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2923 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 279, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
Renewed License No. DPR-62 Amendment No. 279
Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1
N()TE-------------------------------
Not required to be met for vacuum breakers that are open during Surveillances.
Verify each vacuum breaker is closed.
14 days AND Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after any discharge of steam to the suppression chamber from any source AND Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open SR 3.6.1.6.2 Perform a functional test of each required vacuum breaker.
92 days AND Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after any discharge of steam to the suppression chamber from the SRVs SR 3.6.1.6.3 Verify the full open setpoint of each required vacuum breaker is :;;; 0.5 psid.
24 months Brunswick Unit 2 3.6-19 Amendment No. 279
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 251 AND 279 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR-71 AND DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324
1.0 INTRODUCTION
By letter dated July 7,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081980056), as supplemented by letters dated December 7,2008 (ADAMS Accession No. ML0836573580), and March 9, 2009, the Carolina Power & Light Company (the licensee) requested amendments to Renewed Operating Licenses DPR-71 and DPR-62 for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2, respectively. The amendments revise Technical Specifications (TSs) Surveillance Requirements (SRs) 3.6.1.6.1 and 3.6.1.6.2 concerning the testing of the suppression chamber-to-drywell vacuum breakers.
The function of the suppression chamber-to-drywell vacuum breakers is to relieve vacuum in the drywell. The vacuum breakers allow nitrogen (the containment is inerted with nitrogen gas replacing air) and steam flow from the suppression chamber to the drywell when the drywell is at a negative pressure with respect to the suppression chamber. This maintains the primary containment structure within its design structural limits.
Currently, SR 3.6.1.6.1 requires that each suppression chamber-to-drywell vacuum breaker be verified closed: (1) every 14 days, and (2) within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after any discharge of steam to the suppression chamber from any source. Currently, SR 3.6.1.6.2 requires functional testing of each reqUired vacuum breaker: (1) every 92 days, (2) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after any discharge of steam to the suppression chamber from the safety relief valves (SRVs), and (3) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following an operation that causes any of the vacuum breakers to open.
The amendments remove the requirement to perform a functional test of each vacuum breaker within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following an operation that causes any of the vacuum breakers to open and instead establish a requirement to verify each vacuum breaker is closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open.
The supplements dated December 17, 2008, and March 9, 2009, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on September 23,2008 (73 FR 54864).
- 2
2.0 REGULATORY EVALUATION
The BSEP design was reviewed for construction under the "General Design Criteria for Nuclear Power Plant Construction" issued for comment by the Atomic Energy Commission in July 1967 and is committed to meet the intent of the General Design Criteria (GDC), published in the Federal Register on May 21, 1971, as Appendix A to Title 10 of the Code of Federal Regulations (10 CFR) Part 50. Appendix A establishes the fundamental regulatory requirements with respect to containment design, inspection, and testing. Specifically, GDC 53 requires that the reactor containment to be designed to permit (1) appropriate periodic inspection of all important areas, such as penetrations, (2) an appropriate surveillance program, and (3) periodic testing at containment design pressure of the leaktightness of penetrations which have resilient seals and expansion bellows.
The BSEP TSs contain requirements that ensure the capability of the vacuum breakers to satisfy their safety function. The suppression chamber-to-drywell vacuum breakers must open to equalize the pressure between the drywell and the suppression chamber to ensure the structural integrity of the primary containment. The suppression chamber-to-drywell vacuum breakers must close to prevent steam from bypassing the suppression pool and overpressurizing the suppression chamber. The BSEP Updated Final Safety Analysis Report Section 3.1.2.5.4 states that penetrations with resilient seals, i.e., air lock, hatches, and electrical penetrations, are designed to permit individual periodic leak testing. Penetrations are equipped with test channels which hermetically cover seal welds; the channels can be pressure tested. Thus, the design, inspection and testing of suppression chamber-to-drywell vacuum breakers meets the intent of GDC 53.
Section 50.36 of 10 CFR contains the requirements for the content of plant TSs. The regulation requires, among other things, that SRs assure that the necessary quality of systems and components is maintained. SRs are used to determine whether or not limited conditions of operation are met by confirming the operability or inoperability of systems and components."
The requirements for inservice testing (1ST) are found in 10 CFR 50.55a (f), which specifies testing requirements for pumps and valves. In accordance with 10 CFR 50.55a (f)(4)(ii),
licensees are required to comply with the requirements of the latest edition and addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) incorporated by reference in the regulations 12 months prior to the start of each 120-month 1ST program interval. The NRC provided further guidance in NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants." The applicable ASME OM Code for BSEP, Units 1 and 2 is the 2001 Edition through 2003 Addenda.
Section ISTC 5230, "Vacuum Breaker Valves," of the ASME OM Code requires that vacuum breakers shall meet the applicable test requirements of ISTC 5220, Check Valve," and Mandatory Appendix I, Inservice Testing of Pressure Relief Devices in Light Water Power Plants."
3.0 TECHNICAL EVALUATION
By letter dated June 20, 2005 (ADAMS Accession No.ML051790195), the licensee requested a change to the BSEP, Unit 1 and Unit 2 TSs revising the frequency of suppression chamber-to-drywell vacuum breaker functional testing, as well as adding a requirement for functional testing of these vacuum beakers after a steam discharge from the SRVs or after the
- 3 opening of a vacuum breaker. The NRC approved this request by letter dated May 5, 2006, and issued Amendment Nos. 240 and 268 for BSEP, Units 1 and 2, respectively (ADAMS Accession No. ML060890283). Since these amendments were implemented, the licensee states that an unexpected and significant number of suppression chamber-to-drywell vacuum breaker functional tests have been required due to momentary vacuum breaker openings that were not associated with SRV steam discharge to the suppression pool. The licensee has determined that these vacuum breaker openings have been the result of momentary pressure differentials between the suppression chamber and the drywell that occur during containment venting.
Containment venting is carried out at the BSEP every 2 to 4 days.
The licensee states that the discharge of steam from the SRVs to the suppression pool results in a change in the suppression chamber environment sufficient to warrant a functional test of the vacuum breakers. However, the licensee does not consider a functional test necessary when there is not a change in the suppression chamber environment. Therefore, the licensee proposes to revise the requirements of SR 3.6.1.6.1 and SR 3.6.1.6.2 to verify within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of any vacuum breaker opening that the each vacuum breaker is closed rather than performing a functional test.
The NRC staff asked the licensee, in an October 22, 2008, request for additional information (ADAMS Accession No. ML08281066), whether it had pursued other possible options. The licensee responded to this request in the letter dated December 17, 2008. The licensee attempted to vent the suppression chamber prior to venting the drywell. However, the available lines are too small to reduce the suppression chamber pressure sufficiently and in a reasonable time. Also, the differential pressure setting of the vacuum breaker magnetic latches cannot be adjusted by an amount sufficient to prevent the unnecessary vacuum breaker cycling.
The licensee stated that there had been no failures of the vacuum breakers to open when functionally tested. One vacuum breaker failed to reclose. This was due to a remote actuator used only for testing. Therefore, the testing history of the BSEP, Units 1 and 2 vacuum breakers has been good.
Section ISTC-5220 and Mandatory Appendix I of the ASI\\/IE OM Code require that vacuum breakers be actuated to verify open and closed capability, set pressure, and performance of any pressure and position-sensing accessories. Appendix I of the ASME OM Code also requires that leak tests be performed on containment vacuum breakers at each refueling outage or every two years. The plant 1ST program for pumps and valves at BSEP, Units 1 and 2 requires that the affected vacuum breakers be tested periodically in accordance with ISTC-5220 and Mandatory Appendix I.
Based on its review of the information provided by the licensee, the NRC staff finds that the revisions of SR 3.6.1.6.1 and 3.6.1.6.2 do not involve any changes to the plant 1ST program, and the affected vacuum breakers shall continue to be tested in accordance with the ASME OM Code. Therefore, the NRC staff finds this change acceptable since (1) the testing history of these vacuum breakers has been good, (2) no alternative seems practical to eliminate the frequent opening of the vacuum breakers, and (3) the change to the TSs is acceptable on the basis that the revised SRs and requirements of ASI\\/IE OM Code are sufficient to ensure the operability of the vacuum breakers.
- 4
4.0 STATE CONSULTATION
In accordance with the NRC's regulations, the State of North Carolina official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 EI\\IVIRONMENTAL COI\\ISIDERATION The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the SRs. The NRC staff has determined that the amendments involve 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 NRC has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (73 FR 54864). Accordingly, the amendments meet 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 amendments.
6.0 CONCLUSION
The NRC has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the NRC's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: Richard Lobel John Huang Date: March 11,2009
March 11, 2009 Mr. Benjamin Waldrep, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS REGARDING REVISIONS TO TECHNICAL SPECIFICATIONS SURVEILLANCE REQUIREMENTS 3.6.1.6.1 AND 3.6.1.6.2, CONCERNING TESTING OF SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS (TAC NOS. MD9184 AND MD9185)
Dear Mr. Waldrep:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 251 to Renewed Facility Operating License No. DPR-71, and Amendment No. 279 to Renewed Facility Operating License No. DPR-62, Brunswick Steam Electric Plant, Units 1 and 2, respectively. The amendments are in response to your application dated July 7,2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081980056), as supplemented by letters dated December 17, 2008 (ADAMS Accession No. ML083657358), and March 9, 2009. The amendments revise Surveillance Requirement (SR) 3.6.1.6.1 to add a new requirement to verify that each vacuum breaker is closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following an operation that causes any of the vacuum breakers to open and revises SR 3.6.1.6.2 by removing the requirement to perform functional testing of each vacuum breaker within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following an operation that causes any of the vacuum breakers to open.
A copy of the related safety evaluation is also enclosed. A notice of issuance will be included in the NRC's biweekly Federal Register notice.
Sincerely, IRA!
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosures:
- 1. Amendment No. 251 to Renewed License No. DPR-71
- 2. Amendment No. 279 to Renewed License No. DPR-62
- 3. Safety Evaluation cc w/enclosures: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 Rdg RidsNrrDorlLpl2-2 RidsNrrPMFSaba RidsNrrLACSola RidsOgcRp RidsAcrsAcnw_MailCTR Richard Lobel, NRR RidsNrrDorlDpr RidsNrrDciCptb RidsNrrDssScvb John Huang, NRR RidsNrrDirsltsb RidsRgn2MailCenter (P. Fredrickson)
Accession Number* ML090490010, OFFICE LPL2-2/PM LPL2-2/LA CPTB/BC*
SCVB/BC*
ITSB/BC **
OGC **
LPL-2/BC NAME FSaba CSoia JMcHaie RDenniq RElliott DRoth
- TBoyce DATE 03/03/09 02/24/09 02/12/09 02/12/09 02/24/09 02/27/09 03/11/09
- by memo OFFICIAL RECORD COPY
- wi comments