ML100690007
| ML100690007 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire  |
| Issue date: | 08/24/2010 |
| From: | Stang J Plant Licensing Branch II |
| To: | Baxter D, Morris J, Repko R Duke Energy Carolinas |
| Stang, JF, NRR/DORL/LPD II-1, 415-1345 | |
| References | |
| TAC ME2497, TAC ME2498, TAC ME2499, TAC ME2500, TAC ME2501, TAC ME2502, TAC ME2503 | |
| Download: ML100690007 (35) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 24, 2010 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745 Mr. Regis T. Repko Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2, MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, AND OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3, ISSUANCE OF AMENDMENTS REGARDING PERFORMANCE TESTING OF CONTAINMENT SPRAY NOZZLES (TAC NOS. ME2497, ME2498, ME2499, ME2500, ME2501, ME2502 AND ME2503)
Dear Messrs. Morris,
Repko, and Baxter:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 261 to Renewed Facility Operating License NPF-35 and Amendment No. 256 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, Amendment No. 259 to Renewed Facility Operating License NPF-9 and Amendment No. 239 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2, and Amendment Nos. 369, 371, and 370 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 30, 2009.
These amendments revise the Technical Specifications to allow testing containment spray nozzles for nozzle blockage following activities which could result in nozzle blockage, rather than a fixed periodic basis. Currently the testing for nozzle blockage is performed every 10 years.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
J. Morris, R. Repko and D. Baxter
- 2 If you have any questions, please call me at 301-415-1345.
Sincerely,
~ng, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413, 50-414, 50-369, 50-370, 50-269, 50-270, and 50-287
Enclosures:
- 1. Amendment No.
- 2. Amendment No.
- 3. Amendment No.
- 4. Amendment No.
- 5. Amendment No.
- 6. Amendment No.
- 7. Amendment No.
261 256 259 239 369 371 370 to NPF-35 to NPF-52 to NPF-9 to NPF-17 to DPR-38 to DPR-47 to DPR-55
- 8. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 261 Renewed License No. NPF-35
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility)
Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Carolinas, LLC, acting for itself, and North Carolina Electric Membership Corporation (licensees), dated September 30,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-35 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 261
, which are attached hereto, are hereby incorporated into this license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION G{~
Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-35 and the Technical Specifications Date of Issuance: August 24, 2010
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 256 Renewed License No. NPF-52
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility)
Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC, acting for itself, North Carolina Municipal Power Agency NO.1 and Piedmont Municipal Power Agency (licensees), dated September 30,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-52 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 256
, which are attached hereto, are hereby incorporated into this license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION G lG-"-"-----
Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-52 and the Technical Specifications Date of Issuance: August 24, 2010
ATTACHMENT TO LICENSE AMENDMENT NO. 261 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 256 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Licenses Licenses NPF-35, page 4 NPF-35, page 4 NPF-52, page 4 NPF-52, page 4 TSs TSs 3.6.6-2 3.6.6-2
- 4 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No 261 which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
(4) Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program (Section 9.5.1, SER, SSER #2, SSER #3, SSER #4, SSER #5)*
Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, as amended, for the facility and as approved in the SER through Supplement 5, 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.
- The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplement wherein this renewed license condition is discussed.
Renewed License No. NPF-35 Amendment No. 261
-4 (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No 256 Nhich are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than February 24, 2026, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
(4)
Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.
(5)
Fire Protection Program (Section 9.5.1, SER, SSER #2, SSER #3, SSER #4, SSER #5)*
Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, as amended, for the facility and as approved in the SER through Supplement 5, 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.
- The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplements wherein this renewed license condition is discussed.
Renewed License No. NPF-52 Amendment No. 256
Containment Spray System SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.6.6.2 Verify each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head.
SR 3.6.6.3 Verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.*
SR 3.6.6.4 Verify each containment spray pump starts automatically on an actual or simulated actuation signal.*
SR 3.6.6.5 Verify that each spray pump is de-energized and prevented from starting upon receipt of a terminate signal and is allowed to manually** start upon receipt of a start permissive from the Containment Pressure Control System (CPCS).
SR 3.6.6.6 Verify that each spray pump discharge valve closes or is prevented from opening upon receipt of a terminate signal and is allowed to manually** open upon receipt of a start permissive from the Containment Pressure Control System (CPCS).
SR 3.6.6.7 Verify each spray nozzle is unobstructed.
3.6.6 FREQUENCY In accordance with the Inservice Testing Program 18 months 18 months 18 months 18 months Following activities which could result in nozzle blockage
- Following implementation of the modifications associated with ECCS Water Management on the respective unit, the requirements of SR 3.6.6.3 and SR 3.6.6.4 shall no longer be applicable.
- Following implementation of the modifications associated with ECCS Water Management on the respective unit, spray pump starting and spray pump discharge valve opening are manual functions.
Catawba Units 1 and 2 3.6.6-2 Amendment Nos. 261, 256
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 259 Renewed License No. NPF-9
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility),
Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas, LLC (licensee), dated September 30,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-9 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 259
,are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-9 and the Technical Specifications Date of Issuance:
August 24, 2010
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 239 Renewed License No. NPF-17
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),
Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated September 30,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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. NPF-17 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
239 are hereby incorporated into this I
license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-17 and the Technical Specifications Date of Issuance:
August 24, 2010
ATTACHMENT TO LICENSE AMENDMENT NO. 259 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 239 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License Pages License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TS Pages TS Pages 3.6.6-2 3.6.6-2
-3
. (4)
Pursuant to the Act and 10 CFR Parts 30,40 and 70', to recelw.. possess and use In amounts as ntqulAJd afry bypnxluct, source or spee.' nuclear materia' without nts~UOn to cherTl'ee1 or physical form, for. sample.NI~
or instrument calibration or associated wtth nldloacttw appandU15 or components:
(5) Pursuant to the Act and 10 CFR Parts 30,40 and 70, to paSINS, but not separate, such byproduc* and special ru;lear materials as may be produced by the operalton of McGuIre Nuclear Slatlon, Units l' and Z and*'
I 1
(8) Pursuant to the Act and 10 CFR Parts 30 and 40,' to nteelve, possess and process for release or transfer IUch byproduct matertal as may be produced by the Duke Training Ind Technology Center.
C. This renewed operating license shall be deemed' to contain and is sUbjecl to. the,
condlUons specified In the Commission's regulations sot foith In 10 CFR Chapter Jand is subject to allappUcable provisions of the Act and to the rules, regulaUons, and orders of the Commllslon now or hereafter In effect; and Is subject to the addiUonai conditions, tpeclfled or incorporated below:
(1 ) Maximum Power Level The licensee Is authorized to operate the facility at a reBetor core fUll steady state power level of 3411 megawatts thermal (100*"').
(2) Technl(;81 S pec~cations The Technical Specifications contained in Appendlx'A, as revIsed through Amendment No. 259,are hereby Incorporated into this renewed operating license. Tne licensee shall operate lhe facility In accordance with the Technical Specifications.
(3) Updated Final Safety Analysis Report
,The Updated Final Safety Anal)1ls Report supplement submitted pu~u8nt to 10 CFR S4.21(d). lilt ",vised on December 16, 2002, doacrl~s ceMIn future actlvitle. to be completed before the period of extendec:l openttlon.
Duke shall complete these actlvltle$ no later then June 12, 2021. and shall notify the NRC In wntlng when Implementation of these activities Is complete and can be verified by NRC Inspection.
The Updated Final Safety Analysis 'Report supplement as reviled on December 16,2002, described above, shall be included In the next scheduled update to the Updated Final Safety Analysis Report requirvd by 10 CFR 50.71(e)(4), following Issuance of ttlis renewed aperaUng license.
Until that update Is complete I Duke may make cha'9'S lo the prQgrams desc'rlbed in such supplement wIthOut prior Commission approvel, provided that Duke evaluates each such change pursuant to the aiteria 38t forth In 10 orR 50,59 and othcrwl3o compliM with the rOGulramcma:, In that section.
Renewed Llcenae No. NPF-9 Amendment No, 259
(4) Pursuant to the Act and 10 CFR Parts 30. 40 snd 70",.to nteelve, possess and use In amounts as required' any byproduct, soun::e or special nuclear meterlal without restriction to chemical or phYSlc81 form, for sample anelyels or Instrument calbratlon or associated with radioactive apparatus or components; (5) P\\nuant to the Act and 10 CFR Parts 30, 40 and 70. to posaess~ but riot separate, such byprvducls and'speclal nuclear materials as may be produced' by the operation of McGuire Nuclear Station, units, and 2; Ind, (6) Pursuant to the Act and 10 CFR'PsrtI 30 and 40, to reeoive, possess and process for release or transfer such byproduct material as mey be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and Is subject to the conditions specified In the Commission's regulations set for1h In 10 CFR Chapter I and Is subject to all applicable provisions of tha Act and to the Nlel, regulations, and ordm of the commission now or hereafter In effect; and Is subject to the additional ~dltlons specified or Incorporated below:
(1) M,ximum Powgr Level The licensee is authoriZed to operate the facitity at a reactor core full steady state power level of 3411 megawlltts thermal (1 00%).
(2) IechnicalSp!df!cations
. The Technical SpAcifqUons contained in Appendix A, as revised through Amendment No. 239,~re hereby Incorporated Into this renewed operating license. ;The licensee shall operate the fBc'1ty In accordance with the Technical SpeclflC8t1o.ns.
(3) Updated Final ~fety AnalysIs Report The Updated Final Safety.Analysls Report supplement submitted pursuant to '0 CFR 54.21(d), as revised on December '6,2002, delcribe1 certaIn future actM1les to be completed bofore the period of o~onded opef1ltlon.
Duke.haD complete lhesa actlvltles no later than March 3,2023, and shall notify the NRC In writing when implementation of these actl"itles is complete and can be verified ~y NRC Inspection.
Tl'8 Upduted Final Safety Anulysil Report supplement al reVised on December 16, 2002, described above, ahan be Included In the neXf scheduled update to the Updated Final Safety Analysla Report rvqulred by
'0 CFR 50.71 (eX4), following Inuance of this renewed operltlng license.
Until thet update Is complete, Duke may make changes to the programs described In suCh supplement without prior CommissiOn approval, provided that Duke evaluates each such change pursuant to the crtter1a set forth in 10 CFR 50.59, and otherwise Complies with the requirements in thst section.
Renewed License No. NPF*17 Amendment No. 239
Containment Spray System 3.6.6 FREQUENCY SURVEILLANCE SR 3.6.6.2 Verify each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head.
SR 3.6.6.3 Verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.6.6.4 Verify each containment spray pump starts automatically on an actual or simulated actuation signal.
SR 3.6.6.5 Verify that each spray pump is de-energized and prevented from starting upon receipt of a terminate signal and is allowed to start upon receipt of a start permissive from the Containment Pressure Control System (CPCS).
SR 3.6.6.6 Verify that each spray pump discharge valve closes or is prevented from opening upon receipt of a terminate signal and is allowed to open upon receipt of a start permissive from the Containment Pressure Control System (CPCS).
SR 3.6.6.7 Verify each spray nozzle is unobstructed.
In accordance with the Inservice Testing Program 18 months 18 months 18 months 18 months Following activities which could result in nozzle blockage McGuire Units 1 and 2 3.6.6-2 Amendment Nos. 259, 239
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 369 Renewed License No. DPR-38
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility),
Renewed Facility Operating License No. DPR-38 filed by the Duke Energy Carolinas, LLC (the licensee), dated September 30,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as setforth 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 set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 369
. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION C(G_~---
Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-38 and the Technical Specifications Date of Issuance: August 24, 2010
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 371 Renewed License No. DPR-47
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility),
Renewed Facility Operating License No. DPR-47 filed by the Duke Energy Carolinas, LLC (the licensee), dated September 30, 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 as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
371
' are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-'J
.. /
6../1 <.,..A-_
Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-47 and the Technical Specifications Date of Issuance: August 24,2010
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 370 Renewed License No. DPR-55
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility),
Renewed Facility Operating License No. DPR-55 filed by the Duke Energy Carolinas, LLC (the licensee), dated September 30,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 370
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 6 {6....--.---
Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. DPR-55 and the Technical Specifications Date of Issuance:
August 24, 2010
ATIACHMENT TO LICENSE AMENDMENT NO. 369 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 371 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 370 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) 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 Licenses Licenses License No. DPR-38, page 3 License No. DPR-38, page 3 License No. DPR-47, page 3 License No. DPR-47, page 3 License No. DPR-55, page 3 License No. DPR-55, page 3 3.6.5-5 3.6.5-5
- 3.
Part 70; Is sUbject to all apJ)licable provisions of the Act and to th~ rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or Incorporated below:
A.
Maximum Power Level The licensee Is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thennal.
B, Technical Specifications The Technical SpAcifications contained in Appendix A, as revised through Amendment No. 369,. are hereby Incorporated in the license. The licensee shall operate the facility in cJccordance wIth the Technical' Specifications.
C.
This license is subject to the following antitrust conditions:
Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to selVe the public interest. In addition, where there are net benefits to all participants, such arrangements also selVe the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of Ihe environmental effects of Ihe production and sale of electricity.
Any particular bulk power supply transaction may afford greater benefits to one participant than.to another. The benefllsrealized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction, Accordingly, applicant will enter into proposed bulk power transactions of th~ types hereinafter describedwhich, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined In ~1 (d) hereof) and there is no demonstrable net detriment to applicanl arising from that transaction.
1.
As used herein:
(a)
"Bulk Power" means electric power and any attendant energy.
supplied or made available at transmission or sub-transmission voltage by one electric system to another.
(b)
"Neighboring Entity" means a private or public corporation. a govemmental agency or authority, a municipality, a cooperative, or a lawfUl association of any of the foregoing owning or operating, Or Renewed License No. DPR*38 Amendment No. 369
- 3 Part 70; Is subject to aJr applicable provisions of the Act ana to the rules, regulations, and orders of the Commission now or hereafter in effect; and is stJbject to the additional cOr:lditions specified or in<;orporated below:
A.
Max.imum Power Level The licensee is authorized to operate the facility at steady stale reactor core power levels not in ex.cess of 2568 megawatts thermal.
B.
Technical Specifications The T..r.hnical Specifications contained in Appen~ix A, as revi5ed through Amendment No. 371 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
This license is subject to the following antitrust conditions:
Applicant makes the commitments contained hereir.l;. recognizing that bulk power supply arTangements between neighboring entities normally teno to serve the public interest. In addition, where there are net benefits to all participants, such.arrangements also serve the best Interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction In the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.
Any particular bulk power supply tran5action may afford greater benefits to one participant than to another. The benefits realized by a small'system may be proportionately greater than those realized by a.larger system. The relative benefits to be derived by the parties from a proposed tran5aclion, however. should not be controlling upon a decision with respect to the desirability of participatiRg in the transaction. Accordingly, applicant will, enter Into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant.
There are net benefits in a transaction. If applicant recovers the cost of the transaction (as defined in 111 (d) hereoO and there is no demonstrable net detriment to applicant arising from that transaction.
- 1.
As used herein:
(a)
~Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission vollage by one electric system to another.
(b)
~Neighborlng Entlly" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or alawful association of any or the foregoing owning or operating. or Renewed License No. DPR-47 Amendment No. 371
- 3*
Part 70; Is subject to all' applicable provisions of the Act and to the rules, regulations, and orders of. the Commission J:lOW or hereafter In effect: and is sUbject to the additional conditions specified or Incorporated below:
A.
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not' in excess of 2568 megawatts thermal.
B.
Technical" Specifications The Technical Sr..,.;fications contained in AppendiX A, as revised through Amerldment No. 370, are hereby incorporated in the license. The licensee Shall operate, the facllrty in accordance with the Technical SpecIfications.
C.
This license is subject to the following antitrust conditions:
Applicant makes the commitments contained herein, re90gniZlngthat bulk power
. supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants. such arrangements also serve the best interests of each of the pal1icipants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.
Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportlonately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance. provide net benefits to.
applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ~11 (d) hereoO and there is no demonstrable net detriment to applicant arising from that transaction.
- 1.
As used herein:
(a)
"BUlk Power" means electric power and any attendant energy.
supplied or made available at transmission or sub-transmission voltage by one electric system to 'another, (b)
"Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or Renewed license No. DPR-55 Amendment No. 370
Reactor Building Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.5.5
N()TE--------------------------
Applicable for RB cooling system after the completion of the LPSW RB Waterhammer Modification on the respective Unit.
Verify each automatic reactor building spray and cooling valve in each required flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
18 months SR 3.6.5.6 Verify each required reactor bUilding spray pump starts automatically on an actual or simulated actuation signal.
18 months SR 3.6.5.7 Verify each required reactor building cooling train starts automatically on an actual or simulated actuation signal.
18 months SR 3.6.5.8 Verify each spray nozzle is unobstructed.
Following activities which could result in nozzle blockage.
()C()NEE UNITS 1, 2, & 3 3.6.5-5 Amendment Nos. 369, 371, 370 I
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 261 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AND DUKE ENERGY CAROLINAS, LLC AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NPF-52 AMENDMENT NO. 259 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AMENDMENT NO. 239 TO RENEWED FACILITY OPERATING LICENSE NPF-17 AMENDMENT NO. 369 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 371 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO. 370 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 OCONEE NUCLEAR STATION, UNITS 1. 2. AND 3 DOCKET NOS. 50-269. 50-270. AND 50-287
1.0 INTRODUCTION
By application dated September 30, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092860067), Duke Energy Carolinas, LLC (Duke, the licensee), requested changes to the Technical Specifications (TSs) for the Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2), McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2) and Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1, 2, and 3).
Enclosure
- 2 The proposed changes would revise the Technical Specifications (TSs) to allow testing containment spray nozzles for nozzle blockage following activities which could result in nozzle blockage, rather than a fixed periodic basis. Currently the testing for nozzle blockage is performed every 10 years.
The Catawba 1, and 2 and McGuire 1 and 2 containment spray systems are designed to remove thermal energy from the containment atmosphere during a loss of coolant accident (LOCA) and maintain containment pressure below the containment design limit of 15 pounds per square inch gauge (psig) after all the ice in the ice condensers has melted. The containment spray systems consist of two parallel, redundant trains each with a spray pump, spray heat exchanger, and associated piping, valves and spray ring headers in each unit. The containment spray nozzles are located on six spray ring headers high in the upper containment to maximize spray droplet fall distance and thus enhance heat transfer effectiveness. The system components exposed to boric acid containing spray water, including the spray nozzles, are constructed of stainless steel or equivalent corrosion resistant material. The spray nozzles are hollow cone ramp bottom design with nominal 0.375-inch throat orifice and are resistant to clogging by objects in the spray flow that are less than 0.25-inch maximum dimension. During the post-LOCA recirculation phase the containment sump strainers, with their 0.0975-inch openings, remove debris from the containment pool water that is potentially large enough to block the spray nozzles.
The Oconee 1, 2 and 3 reactor building spray (RBS) systems are designed to remove thermal energy from the containment atmosphere during an accident and maintain containment pressure below the design pressure of 59 psig. These systems remove heat and fission products from the reactor building atmosphere thereby controlling pressure and reducing potential fission product leakage to the environment. The RBS systems in each unit include two independent, redundant trains consisting of a pump and associated valves, piping, spray headers and spray nozzles. The RBS systems initially draw water from the borated water storage tank and when sufficient water accumulates in the containment, pump suction is switched to recirculation mode drawing from the containment sump. The sump strainers have a maximum opening size of 0.059 inches. RBS components contacting the borated water, including spray nozzles, are constructed of stainless steel. The spray nozzles have an effective orifice size of 0.125 inches and thus are unlikely to clog from objects or material in the strained, recirculated spray water. Currently the Catawba 1 and 2, McGuire 1 and 2, and Oconee 1, 2 and 3 TSs Surveillance Requirements (SRs) require each spray nozzle to be verified unobstructed every 10 years. Performing this surveillance test can involve draining the spray headers and admitting low-pressure compressed air, with or without a smoke agent, into the headers or alternatively by vacuum blower inducing airflow through each nozzle to verify the unobstructed flow condition.
2.0 REGULATORY EVALUATION
Catawba 1 and 2 and McGuire 1 and 2 design and construction was in compliance with Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, "General Design Criteria (GDC) for Nuclear Plants." The principle design criteria (PDC) for Oconee 1I 2, and 3 were developed in consideration of the Atomic Energy Commission's 70 General Design Criteria for Nuclear Power Plant Construction Permits contained in the proposed rulemaking published in the Federal Register on July 11, 1967.
- 3 Applicable GDCs and Applicable PDCs GDC 38 - Containment heat removal GDC 40 - Testing of containment heat removal system PDC 52 - Containment heat removal systems PDC 60 - Testing of containment spray systems GDC 38 and PDC 52 states, in part, the requirements for design of a containment heat removal system. The requested revision of the TSs to change a test frequency does not directly affect these criteria.
GDC 40 states, in part, that the systems design permit appropriate periodic functional testing of the delivery. PDC 60 states, in part, that a capability be provided to periodically test the delivery capability of the system. The associated discussion states, in part, that the delivery capability of the spray nozzles will be tested by blowing low pressure air through the system and verifying flow through the nozzles. The requested TS changes do not affect the ability to verify that spray nozzles are not obstructed. Although a calendar based periodic nozzle flow test would no longer be required, an event-or condition-based test requirement would provide reasonable assurance that the spray nozzles will perform their safety function.
The NRC staff has approved similar license amendments, examples include:
Prairie Island Units, 1 and 2 (November 6,2008, ADAMS Accession No.ML082740226)
Millstone Power Station, Unit 2 (March 31,2008, ADAMS Accession No. ML080720304)
Arkansas Nuclear One Unit 1 (July 9,2008, ADAMS Accession No. ML081540218).
3.0 TECHNICAL EVALUATION
The containment spray system piping and components which may be in contact with borated water are made of uncoated stainless steel which is resistant to corrosion and thus minimizes the potential for time-based accumulation of potential nozzle obstructing corrosion and degraded coating deposits in the supply piping and spray headers.
The spray lines within the containment are normally filled with borated water up to the static height of water in the Refueling Water Storage Tank (Catawba 1 and 2, and McGuire 1 and 2 ) or Borated Water Storage Tank (Oconee 1, 2, and 3) and with air above that elevation in the risers and spray headers. This assures that the spray headers and nozzles remain dry during normal plant operation.
Due to their location at the top of the containment, introduction of foreign material through the spray nozzles into the headers is unlikely. Because maintenance that could introduce foreign material is by far the most likely cause for obstruction, testing or inspection following maintenance with that potential would suffice to verify the system's capability to perform its safety function.
Performing calendar based nozzle tests is of little value given the likelihood of detecting an obstructed nozzle if there have been no events since the previous test that would introduce potentially obstructing materials into the system or carry them to the spray headers. Verifying that the nozzles are not obstructed following maintenance or inadvertent system actuations that could introduce or transport foreign materials to the spray ring headers (due, for example, to a loss of
- 4 foreign material control) are more appropriate. The proposed change to the TSs expands on the earlier extension of the test interval from 5 to 10 years based on Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27,1993. The proposed TS change is also based on the information contained in NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements," dated December 1992. NUREG-1366 documents the review of containment spray system experience throughout the industry with the conclusion that nearly all spray nozzle obstruction events were related to original construction foreign material left in the system or to accumulation of corrosion products in the piping/headers. Periodic testing to date has revealed the legacy foreign material within the containment spray systems. If system materials of construction do not support accumulation of corrosion or coating products within the system, then the spray nozzles are unlikely to become obstructed as a result of passive weathering with the passage of time. Periodic testing is unlikely to reveal obstructions without there having been a loss of foreign material control during maintenance or a system actuation and water flow that could entrain and transport the foreign material to the headers or nozzles or deposit boric acid crystal residue in the headers.
Performing the nozzle tests involves personnel radiation dose, industrial safety hazards, potential for inadvertent introduction of foreign material into the systems, and potential for improper realignment of the systems after a test. These consequences or the potential for adverse consequences could be reduced if very low value testing is avoided.
Operation Experience The licensee stated that the containment and reactor building spray system nozzles of these facilities have been pre-operationally inspected and tested and subsequently periodically tested several times with no actual indication of obstruction. Several instances of inadvertent system actuation with some water flow through the nozzles were identified, but with subsequent nozzle testing showing no obstructions.
The licensee stated in the application that their foreign material exclusion (FME) controls provide assurance that the potential for nozzle obstruction will continue to be low. The licensee also indicated that should foreign material with the potential for spray nozzle obstruction be discovered, their corrective action program would direct that the extent of condition be evaluated, and would lead to restoration of cleanliness and a determination as to the need for nozzle testing.
Industry Experience and Failure Mechanisms A Nuclear Regulatory Commission (NRC) staff review of industry experience by searches of the Licensee Event Report databases indicates that spray systems of similar design are highly reliable (i.e., not susceptible to spray nozzle obstructions). The staff found that, with a few exceptions, once successfully tested after construction, containment spray nozzles have not been subject to blockage. There have been very few exceptions. In the case of one pressurized-water reactor (PWR) no longer operating, a chemical added to the inner surface of a spray system pipe to eliminate a corrosion problem detached and the loose material blocked some spray nozzles.
Spray piping that is corrosion resistant avoids this failure mechanism and this experience is not applicable to Catawba 1 and 2, McGuire 1 and 2, or Oconee 1,2, and 3. The licensees at other PWRs have found debris, identified as left from original construction, in the spray nozzle headers.
- 5 The fraction of blockage was not significant and the sprays remained functional. After the initial nozzle testing, debris in the piping and headers has nearly always been discovered by visual inspection, not by subsequent periodic air flow tests.
4.0
SUMMARY
The NRC staff finds the licensee's proposed change to the Catawba 1 and 2 and McGuire 1 and 2 TSs SR 3.6.6.7 and the Oconee 1, 2, and 3 TSs SR 3.6.5.8 to be acceptable based on experience at these units, industry experience at other PWR units, and the licensee's foreign material exclusion control and corrective action programs.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North and South Carolina State officials were notified of the proposed issuance of the amendments. The State officials had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. 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 Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on March 9, 2010 (75 FR 10828).
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.
7.0 CONCLUSION
The Commission 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 Commission'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:
Jerome Bettie, NRRlDSS Date: August 24, 2010
- 2 If you have any questions, please call me at 301-415-1345.
Sincerely, IRA!
John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413, 50-414, 50-369, 50-370, 50-269, 50-270, and 50-287
Enclosures:
- 1. Amendment No. 261 to NPF-35
- 2. Amendment No. 256 to NPF-52
- 3. Amendment No. 259 to NPF-9
- 4. Amendment No. 239 to NPF-17
- 5. Amendment No. 369 to DPR-38
- 6. Amendment No. 371 to DPR-47
- 7. Amendment No. 370 to DPR-55
- 8. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLlI-1 RlF RidsNrrDorlLp2-1 Resource RidsAcrsAcnw_MailCtr Resource RidsNrrDirsltsb Resource RidsNrrDoriDpr Resource RidsNrrDssScvb Resource RidsOgcRp Resource RidsRgn2MailCenter Resource JBettle, NRRlDSS RidsNrrPMOconee Resource RidsNrrPMMcGuire Resource RidsNrrPMCatawba Resource RidsNrrLAMOBrien Resource ADAMS Accession No ML100690007
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AJones (wi comments)
GKulesa JStang DATE 08/19/10 08/11/10 02/01/2010 08/18/10 08/23/10 08/19/10 OFFICIAL RECORD COpy