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| {{#Wiki_filter:July 17, 2006 Mr. Dav id A. Chri stian Senior Vi ce President and Chief Nucl ear Officer Innsbrook Technical Center 5000 D omini on Bou leva rd Glen Alle n, VA 2306 0-6711 SUBJE CT: KEW AUNEE POW ER ST ATI ON - I SSUAN CE OF AMENDMEN T RE: STEA M GENERATOR TUBE IN TEGRITY (TAC NO. MC 9581)Dear Mr. C hristian: The U.S. Nucle ar Regulatory Commission (N RC) has iss ued the encl osed Amendment N o.188 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revi ses the Technic al Specifica tions (TSs) in response to y our applica tion dated Janua ry 12 , 2006 , as su ppleme nted b y le tter da ted Ju ne 2, 2 006. The amendment rev ises the ex isting steam generato r (SG) tube surv eillance program to be consistent w ith TS Task Force (TSTF) Ch ange TSTF-449, Rev ision 4, "S team Generator Tube Integrity," and th e model safety evaluati on prepared b y the NRC and publi shed in the Federal Register on March 2, 2005 (70 FR 10298) un der the consol idated li ne item improv ement proces s. A copy of the Safety Eval uation is also enclo sed. The Notic e of Issuance w ill be i ncluded i n the Commis sion's ne xt regu lar biweek ly Federal Reg ister notice.Since rely , /RA/David H. Jaffe, Senior Project Manager Plant Lice nsing B ranch III-1 Divisi on of Operating Reac tor Licensin g Office of Nuclear Reacto r Regulation Docket No. 50-305 Enclo sures: 1. Ame ndment No. 18 8 to Li cense No. DP R-43 2. Safety Ev aluation cc w/enc ls: See nex t pag e July 17, 2006 Mr. Dav id A. Chri stian Senior Vi ce President and Chief Nucl ear Officer Innsbrook Technical Center 5000 D omini on Bou leva rd Glen Alle n, VA 2306 0-6711 SUBJE CT: KEW AUNEE POW ER ST ATI ON - I SSUAN CE OF AMENDMEN T RE: STEA M GENERATOR TUBE IN TEGRITY (TAC NO. MC 9581)Dear Mr. C hristian: The U.S. Nucle ar Regulatory Commission (N RC) has iss ued the encl osed Amendment N | | {{#Wiki_filter:July 17, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 |
| : o. 188 to Facility Operating License No. DPR-43 f or the Kewaunee Power Station. This amendment revi ses the Technic al Specifica tions (TSs) in response to y our applica tion dated Janua ry 12 , 2006 , as su ppleme nted b y le tter da ted Ju ne 2, 2 006. The amendment rev ises the ex isting steam generato r (SG) tube surv eillance program to be consistent w ith TS Task Force (TSTF) Ch ange TSTF-449, Rev ision 4, "S team Generator Tube Integrity," and th e model safety evaluati on prepared b y the NRC and publi shed in the Federal Register on March 2, 2005 (70 FR 10298) un der the consol idated li ne item improv ement proces s. A copy of the Safety Eval uation is also enclo sed. The Notic e of Issuance w ill be i ncluded i n the Commis sion's ne xt regu lar biweek ly Federal Reg ister notice.Since rely , /RA/David H. Jaffe, Senior Project Manager Plant Lice nsing B ranch III-1 Divisi on of Operating Reac tor Licensin g Office of Nuclear Reacto r Regulation Docket No. 50-305
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| | ==SUBJECT:== |
| | KEWAUNEE POWER STATION - ISSUANCE OF AMENDMENT RE: STEAM GENERATOR TUBE INTEGRITY (TAC NO. MC9581) |
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| | ==Dear Mr. Christian:== |
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| | The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No.188 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the Technical Specifications (TSs) in response to your application dated January 12, 2006, as supplemented by letter dated June 2, 2006. |
| | The amendment revises the existing steam generator (SG) tube surveillance program to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the NRC and published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process. |
| | A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice. |
| | Sincerely, |
| | /RA/ |
| | David H. Jaffe, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305 |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Amendment No | | : 1. Amendment No. 188 to License No. DPR-43 |
| .188 to Li cense No. DP R-43 2. Safety Ev aluation cc w/enc ls: See nex t pag e DISTRIBUTION: | | : 2. Safety Evaluation cc w/encls: See next page |
| PUBLIC LPL3-1 R/F RidsNrrDor lLple RidsNr rPMDJa ffe RidsNrrLATHa rris RidsOgcRp RidsAcrsAcnwMai lCenter RidsNr rDirs ltsb G. Hil l, OIS RidsRgn3Ma ilCenter RidsNrrDor lDpr ADAMS ACCESSION NUM BER: ML061700208 - PACKAGE: ML061700091 - TS:ML061720131 OFFICE NRR/L PL3-1/PM NRR/LPL3-1/L A NRR/TS B/BC OGC NRR/L PL3-1/BC NAME DJaffe THarris TKobetz*APH P. Tam for LRag havan DATE 6/30/06 6/30/06 6/15 /0 6 7/6/06 7/17/06 OFFICE NRR/C SGB/BC NRR/TS B/BC NAME A.Hetser ACH CSchul ten fo r TKob etz DATE 7/13/06 7/17/06 OFF ICIAL R ECORD COPY *SE I nput vi a memora ndum wi th minor changes.
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| Kewaunee Power S tation cc: Resident Insp ectors Office U.S. Nuclear Regulatory C ommission N490 Highw ay 42 Kewaunee , WI 54216-9510 Region al Ad minis trator, Region III U.S. Nuclear Regulatory C ommission Suite 210 2443 Warrenville R oad Lisle, IL 60532-4351 David Z ellner Chairman - Tow n of Carlton N2164 Cou nty B Kewaunee , WI 54216 Mr. Jeffery Kitse mbel Electric Di vision Public Service Commission of W isconsin PO Box 785 4 Madison , WI 53707-7854 Mr. Mi chael G. Gaffney Dominion E nergy Kew aunee, Inc. | | ML061700208 - PACKAGE: ML061700091 - TS:ML061720131 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/TSB/BC OGC NRR/LPL3-1/BC NAME DJaffe THarris TKobetz* APH P. Tam for LRaghavan DATE 6/30/06 6/30/06 6/15 /06 7/6/06 7/17/06 OFFICE NRR/CSGB/BC NRR/TSB/BC NAME A.Hetser ACH CSchulten for TKobetz DATE 7/13/06 7/17/06 |
| Kewaunee Power S tation N490 Highw ay 42 Kewaunee , WI 54216 Mr. C hris L. Fund erburk Director, Nucl ear Licensi ng and Operat ions Suppo rt Innsbrook Technical Center 5000 D omini on Bou leva rd Glen Alle n, VA 2306 0-6711 Mr. Thomas L. B reene Domin ion E nergy Kewa unee, Inc. Kewaunee Power S tation N490 Highw ay 42 Kewaunee , WI 54216 Ms. Lil lia n M. Cu oco, Esq.Senior Cou nsel Dominion R esources Serv ices, Inc. | | |
| Mills tone Powe r Station Building 4 75, 5th Floo r Rope Ferry Road Waterf ord, CT 06385 Plant M anager Kewaunee Power S tation N490 Highw ay 42 Kewaunee , WI 54216-9511 DOMINION ENERGY KEW AUNEE, INC.
| | Kewaunee Power Station cc: |
| DOCKET NO. 50-305 KEWAUNEE P OWER STATION AMENDMENT TO FACILITY OPERATING LICENSE
| | Resident Inspectors Office Ms. Lillian M. Cuoco, Esq. |
| | U.S. Nuclear Regulatory Commission Senior Counsel N490 Highway 42 Dominion Resources Services, Inc. |
| | Kewaunee, WI 54216-9510 Millstone Power Station Building 475, 5th Floor Regional Administrator, Region III Rope Ferry Road U.S. Nuclear Regulatory Commission Waterford, CT 06385 Suite 210 2443 Warrenville Road Plant Manager Lisle, IL 60532-4351 Kewaunee Power Station N490 Highway 42 David Zellner Kewaunee, WI 54216-9511 Chairman - Town of Carlton N2164 County B Kewaunee, WI 54216 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin PO Box 7854 Madison, WI 53707-7854 Mr. Michael G. Gaffney Dominion Energy Kewaunee, Inc. |
| | Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominion Energy Kewaunee, Inc. |
| | Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 |
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| Amendment No. 1 88 | | DOMINION ENERGY KEWAUNEE, INC. |
| | DOCKET NO. 50-305 KEWAUNEE POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. DPR-43 |
| | : 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: |
| | A. The application for amendment by Dominion Energy Kewaunee, Inc. dated January 12, 2006, as supplemented by letter dated June 2, 2006, 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. 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 Facility Operating License No. DPR-43 is hereby amended to read as follows: |
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| License N
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, are hereby incorporated in the license. The licensees shall operate the facility in accordance with the Technical Specifications. |
| : o. DPR-43 1.The U.S. Nucl ear Re gulato ry Co mmissi on (the Commis sion) has fou nd tha t: A.The applicati on for amendment by Dominion Energy Kew aunee, Inc. date d January 12, 2006, as supp lemented by letter dated J une 2, 2006, complies w ith the standards and requirements of the Atomi c Energy Act o f 1954, as amended (the Act), a nd the Commis sion's rule s and regula tions set forth in 10 CFR C hapter I;B.The faci lity wil l ope rate i n confor mity w ith th e appl icati on, the prov isio ns of the Act, and the rule s and regulati ons of the Commissi on;C.There is reasona ble assuranc e (I) that the acti vities a uthorized by this a mendment can be conducted without endangering the health and safety of the public, and (ii) that su ch acti viti es wi ll be condu cted i n compl iance wit h the C ommissi on's regulations; D.The issuance o f this amendment w ill not b e inimical to the common de fense and security or to the health and safety of the p ublic; and E.The issuance o f this amendment is in accordan ce with 10 CFR Part 51 of the Commis sion's regul ation s and all a ppli cable requir ements have been satisfi ed. 2.Accordingly , the licens e is amended by changes to the Technical Specificatio ns as indi cated in the attach ment to this l icens e amend ment, an d para graph 2.C.(2) of Faci lity Operati ng Lice nse No. DPR-43 is hereb y amen ded to read a s follo ws: (2)Technical Sp ecifications The Te chni cal Spe cifi cati ons cont ain ed i n Ap pend ix A, a s rev ise d thr ough Amendment No. 188, are here by incorporated in the license. The licensees shall operat e the fa cili ty in accord ance w ith th e Techn ical Speci ficatio ns. 3.This license amendment is e ffective as of its da te of issuance a nd shall be implemented with in 90 days of the d ate of i ssuanc e. FOR THE NUCL EAR R EGULA TORY COM MISS ION/RA/L. Raghavan, Chief Plant Lice nsing B ranch III-1 Divisi on of Operating Reac tor Licensin g Office of Nuclear Reacto r Regulation
| | : 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance. |
| | FOR THE NUCLEAR REGULATORY COMMISSION |
| | /RA/ |
| | L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation |
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| ==Attachment:== | | ==Attachment:== |
| Chan ges to the Facil ity Operatin g License
| | Changes to the Facility Operating License and Technical Specifications Date of Issuance: July 17, 2006 |
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| | ATTACHMENT TO LICENSE AMENDMENT NO. 188 FACILITY OPERATING LICENSE NO. DPR-43 DOCKET NO. 50-305 Replace the following page of Facility Operating License No. DPR-43 with the attached revised page. The changed area is identified by a marginal line. |
| | REMOVE INSERT Page 3 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 INSERT TS i TS i TS ii TS ii TS iii TS iii TS iv TS iv TS v TS v |
| | - TS 1.0-7 TS 3.1-8 TS 3.1-8 |
| | - TS 3.1-11 TS 4.2-2 TS 4.2-2 TABLE TS 4.2-2 TABLE TS 4.2-2 |
| | - TS 4.18-1 |
| | - TS 4.19-1 |
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| | C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR, Chapter 1: (1) Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, (2) 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 (3) 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 1772 megawatts (thermal). |
| | (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, are hereby incorporated in the license. The licensee shall operate the facility In accordance with the Technical Specifications. |
| | (3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the licensee's Fire Plan, and as referenced in the Updated Safety Analysis Report, and as approved in the Safety Evaluation Reports, dated November 25, 1977, and December 12, 1978 (and supplement dated February 13, 1981) 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. |
| | (4) Physical Protection 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 combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision 0)" submitted by letter dated October 18, as supplemented by letter dated October 21, 2004. |
| | (5) Fuel Burnup The maximum rod average burnup for any rod shall be limited to 60 GWD/MTU until completion of an NRC environmental assessment supporting an increased limit. |
| | Amendment No. 188 3 |
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| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. DPR-43 DOMINION ENERGY KEWAUNEE, INC. |
| | KEWAUNEE POWER STATION DOCKET NO. 50-305 |
| | |
| | ==1.0 INTRODUCTION== |
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| | By letter dated January 12, 2006, as supplemented on June 2, 2006 (Agencywide Documents Access and Management System Accession Nos. ML060250524 and ML061560144, respectively), Dominion Energy Kewaunee (the licensee) submitted a request for changes to the Kewaunee Power Station Technical Specifications (TSs). The requested changes would revise the existing steam generator (SG) tube surveillance program to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the U.S. Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases. |
| | The June 2, 2006, letter provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 14, 2006 (71 FR 7806). |
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| | ==2.0 REGULATORY EVALUATION== |
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| | The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model safety evaluation (SE) published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process, published in the Federal Register on May 6, 2005 (70 FR 24126), made the model SE available to licensees for use. |
| | ENCLOSURE |
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| | ==3.0 TECHNICAL EVALUATION== |
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| | 3.1 Overview In its January 12, 2006, application, as supplemented by a letter dated June 2, 2006, the licensee proposed changes to the TSs that are consistent, with one exception, with the proposed changes approved in TSTF-449. The NRC model SE provides a detailed evaluation of the proposed changes that are requested based upon the NRCs Standard Technical Specifications (STS) as contained NUREGs 1430 - 1432. Since the licensee uses TS that do not conform to the STS, the TS section numbers in its application do not reflect those listed in TSTF-449. Consistent with TSTF-449, the proposed TS changes include: (1) new TS 1.0.t, LEAKAGE, (2) a revised TS 3.1.d, "RCS Operational LEAKAGE," (3) a new TS 3.1.g, "Steam Generator (SG) Tube Integrity," (4) a new TS 4.18, RCS Operational Leakage, (5) a new TS 4.19, Steam Generator (SG) Tube Integrity which replaces existing TS 4.2.b, Steam Generator Tubes, (6) a new TS 6.9.b.3, Steam Generator Tube Inspection Report,, (7) a new TS 6.22, Steam Generator (SG) Program, and (8) revised Table of Content pages to reflect the proposed changes. |
| | The NRC staff reviewed the licensees application for consistency with TSTF-449 to ensure the generic safety evaluation was bounding. The NRC staff made the following observations as a result of its review. |
| | In TSTF-449, the limit on normal operating primary-to-secondary leakage rate through any one SG was significantly less than that assumed in the Kewaunee safety analysis. However, for Kewaunee, the normal operational primary-to-secondary leakage limit (150 gallons per day per steam generator) is identical to the accident induced primary-to-secondary leakage limit for design basis accidents (DBAs) other than a steam generator tube rupture. Given this situation, the NRC staff evaluated the acceptability of this difference between TSTF-449 and the licensees submittal. Since the leakage rate observed during operation may increase during a design-basis accident, in order to meet both limits, it may be necessary to ensure that the operational leak rate is kept well below the operational leak rate limit. This increase in leak rate can be a result of either: (1) the higher differential pressure between the primary coolant system and the secondary system associated with a DBA causing the leak rate from flaws leaking during normal operation to leak at higher rates; or (2) the higher loadings associated with a DBA causing a flaw that was not leaking during normal operation to leak during the accident. |
| | Responding to the NRC staffs question on this issue, the licensee, in its letter dated June 2, 2006, described controls and procedures to ensure that the accident-induced leakage limit is not exceeded as a result of operational leakage. These controls and procedures are intended to ensure that the accident-induced leakage limit (and operational leakage limit) is not exceeded. These controls and procedures include combinations of monitoring, notifications, setpoint verifications, and shutdown preparations when the primary-to-secondary steam generator tube leak rate reaches certain values. The NRC staff reviewed the adequacy of the proposed TS criteria for operational and accident-induced leakage. The TS criteria on operational and accident-induced leakage are consistent with TSTF-449 and the licensees accident analysis; therefore, the NRC staff finds the licensees proposed TS criteria on these values acceptable. |
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| | As a result of adopting TSTF-449, the licensee also proposed changes to the requirements pertaining to reactor coolant system operational leakage (e.g., adding definitions to TS 1.0.t, modifying action statements in TS 3.1.d, and adding surveillance requirements in TS 4.18). |
| | These TS changes were necessary to facilitate adopting the proposed changes in TSTF-449. |
| | Since these proposed TS changes pertaining to reactor coolant system operational leakage were generally consistent with the STS and the plant's licensing basis, the NRC staff determined that the proposed changes were acceptable. |
| | 3.2 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. |
| | The NRC staff finds that maintaining these performance criteria provides reasonable assurance that the SGs can be operated safely without increase in risk. |
| | The proposed TSs changes contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. |
| | However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained. |
| | Failure to meet the performance criteria will be reportable pursuant to the requirements in 10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented. |
| | In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its January 12, 2006, application, as supplemented by a letter dated June 2, 2006, conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety. |
| | |
| | ==4.0 ENVIRONMENTAL CONSIDERATION== |
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| and Techn ical Spec ifications Date of Issuance: | | This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. |
| July 17, 2006 ATTACHMENT TO LICE NSE AM ENDMEN T NO. 188 FACILITY OPERATING L ICENSE NO. D PR-43 DOCKET NO. 50-305 Replace the followin g page of Facility Operating Licen se No. DPR-4 3 with th e attached rev ised page. Th e chan ged are a is i denti fied by a margi nal l ine.
| | The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 7806). Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment. |
| REMOVE
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| INSERT Page 3 Page 3 Replace the followin g pages of the Append ix A Techn ical Spec ifications w ith the attache d revised p ages. The revi sed pages are i dentified by amendment number a nd contain ma rginal line s ind icati ng the a reas o f change.
| | ==5.0 CONCLUSION== |
| REMOVE
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| INSERT TS i TS i TS ii TS ii TS iii TS iii TS iv TS iv TS v TS v-TS 1.0-7 TS 3.1-8 TS 3.1-8-TS 3.1-11 TS 4.2-2 TS 4.2-2 TABLE TS 4.2-2 TABLE TS 4.2-2-TS 4.18-1-TS 4.19-1 C.This license shall be deemed to contain and is subject to the condit ions specified in the followi ng Commission re gulations in 10 CFR, Ch apter 1: (1) Pa rt 20, Section 30.34 of Part 30, S ection 40.41 of Part 40, Sectio n 50.54 and 50.59 of Part 50, a nd Section 70.32 of Part 70, (2) is subject to al l applic able prov isions of the Act and to the rules, regul ations, and o rders of the Commissi on now o r hereafter in effect, and (3) is sub ject to th e addi tion al con ditio ns sp ecif ied or incor pora ted b elow: (1) Maximu m Power Lev el The li censee is au thoriz ed to o perate the faci lity at ste ady-s tate re actor c ore powe r lev els n ot in exce ss of 17 72 megaw atts (th ermal).(2) Technical Sp ecifications The Te chni cal Spe cifi cati ons cont ain ed i n Ap pend ix A, a s rev ise d thr ough Amendment No. 18 8, are hereby incorporated in the li cense. The li censee shall ope rate the facili ty In accorda nce with the Technical Specification s.(3) Fire Protecti on The licensee shall i mplement and mai ntain in e ffect all provis ions of the approved F ire Protection Program as descri bed in the licensee's Fire Plan, and as referenced in the Updated S afety Analy sis Report, an d as approv ed in the Safety Eval uation Repo rts, dated Nov ember 25, 1977, and December 1 2, 1978 (and suppleme nt dated Februa ry 13, 1981) subject to the fol lowing pro vision: The licensee may make changes to the approv ed Fire Prote ction Program without p rior approv al of the Commiss ion, only if those changes would n ot adversely affect the ability to achiev e and maintai n safe shutdow n in the ev ent of a fire.
| | The NRC staff 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 this amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| (4) Physical Protection The licensee shall full y implemen t and maintai n in effect all p rovision s of the Commission-app roved phy sical secu rity, traini ng and qualificati on, and safeguard s conti ngency plan s incl uding amendme nts mad e purs uant to provi sions of the M iscel laneo us Ame ndments and S earch Requir ements revision s to 10 CFR 73.55 (51 FR 27817 and 2 7822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protec ted under 10 CFR 73.21, i s entitled:
| | Principal Contributor: Eric M. Thomas Date: July 17, 2006}} |
| "Nuclear Management Co mpany Kew aunee Nucl ear Power Plant Phy sical Secu rity Plan (Revisio n 0)" submitted b y letter da ted October 18, as supplemented by letter dated October 21, 2004.(5) Fuel Burnup The m axi mum r od a ver age b urnu p for any rod shal l be lim ited to 6 0 GWD/M TU until compl etion of an NR C environ mental assessmen t supporting an increased limit.Amendment No. 18 8 3 ENCLOSURE SAFETY EVAL UATION B Y THE OF FICE OF NUCL EAR R EACTOR REGUL ATION RELATING TO AME NDMENT N O. 188 TO FACILITY OPER ATING LICENSE N O. DPR-43 DOMINION ENERGY KEW AUNEE, INC.
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| KEWAUNEE P OWER STATION DOCKET NO. 50-305 1.0 INTRODU CTION By l etter d ated J anuary 12, 20 06, as suppl emented on Ju ne 2, 2 006 (A gencyw ide D ocumen ts Access and M anagement System Accession N os. ML060250524 and ML061560144, respec tive ly), Domin ion E nergy Kewa unee (the li censee) submi tted a request for chan ges to the Kewaunee Power Station Technical Specifications (T Ss). The request ed changes would rev ise the exi stin g ste am ge nera tor (SG) t ube surv eil lan ce p rogra m to b e co nsi sten t wi th TS Task Force (TSTF) Change TSTF-449 , Revisi on 4, "Steam Genera tor Tube Integrity," a nd the model safety ev aluation p repared by the U.S. Nucl ear Regulatory Commission (N RC) and published in the Federal Reg ister on March 2, 2005 (70 FR 10298) un der the consol idated li ne item improveme nt process (CLIIP
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| ). In this regard, th e scope of the ap plication includes chan ges t o the defi niti on o f lea kage, cha nges to th e pri mary-to-seco ndar y l eaka ge requirements, changes to the SG tube su rveilla nce program (SG tube i ntegrity), changes to the SG reporting requiremen ts, and associ ated changes to th e TS Bases.
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| The June 2, 200 6, letter prov ided addi tional in formation that clari fied the appli cation, did not expand the scope of the application as originally noticed, and did not chang e the NRC staff's original prop osed no signi ficant hazards consideratio n determinatio n as publi shed in the Federa l Reg ister on Feb ruary 14, 20 06 (71 FR 78 06).2.0 REGUL ATORY E VALUA TION The background, descrip tion, and ap plicabil ity of the prop osed changes as sociated w ith the SG tube integrity issue and the applicable regulat ory requirements were included in the NRC staff's model safety ev aluation (S E) publish ed in the Federal Reg ister on March 2, 2005 (70 FR 10298
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| ). The "Notice o f Availabi lity of M odel Appl ication Co ncerning Technic al Specification
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| ; Improvement To M odify Requiremen ts Regarding Steam Gen erator Tube Integrity; Usi ng the Consoli dated Line Item Improvement Proc ess," publis hed in the Federal Register on May 6, 2005 (70 FR 24126), made the model S E avail able to li censees for use. 3.0 TECHNI CAL E VALUA TION 3.1 Overview In its January 12, 2006, ap plication, as supplemente d by a l etter dated June 2, 2006, the licensee p roposed changes to the TSs that are consistent, w ith one ex ception, w ith the proposed chan ges approved in TSTF-449. The N RC model S E provide s a detail ed evalu ation of the proposed ch anges that are requeste d based upon the NRC's Standard Techni cal Specification s (STS) as contai ned NUREGs 1 430 - 1432.
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| Since the l icensee use s TS that do not conform to t he STS, the TS section number s in its application do not reflect those listed in TSTF-449. Cons isten t wi th TSTF-4 49, the propo sed TS changes incl ude: (1) new TS 1.0.t,"LEAKAGE," (2) a revised TS 3.1.d, "RCS Ope rational LE AKAGE," (3) a ne w TS 3.1.g, "Steam Gene rato r (SG) Tub e Int egri ty," (4) a ne w TS 4.18 , "RC S Ope rati onal Lea kage," (5) a ne w TS 4.19, "Steam Generato r (SG) Tube Integrity" which rep laces exi sting TS 4.2.b, "Steam Generator Tubes," (6) a new TS 6.9.b.3 , "Steam Generator Tube Inspection Re port,", (7) a new TS 6.22, "Steam Genera tor (SG) Program," and (8) revised Tabl e of Content pages to reflect the pro posed change s. The NRC staff revie wed the l icensee's applicatio n for consistency with TSTF-449 to ensure the generic safety ev aluation w as bounding.
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| The NRC staff made the foll owing obse rvations as a resu lt of its re view.In TSTF-449, the li mit on normal o perating primary-to-secondary leakage rate through an y one SG was si gnificantly l ess than that a ssumed in the Kewaunee safety analy sis. How ever, for Kewaunee , the normal op erational p rimary-to-second ary leakage l imit (150 gall ons per day per steam generator) is i dentical to the accident induced pri mary-to-secondary leakage limit for design basis accidents (DB As) other than a steam generator tube rupture. Give n this situa tion, the NRC staff eval uated the acce ptability of this difference betw een TSTF-449 and the licensee's submittal. S ince the l eakage rate observ ed during opera tion may i ncrease durin g a design-basis a ccident, in order to meet both limits, it may be necessary to ensure that the operat ional leak ra te is kept w ell b elow the op eratio nal l eak rate limi t. This incre ase i n lea k rate can be a resu lt of either: (1) the higher differential pressure betw een the primary coolant syst em an d the seco ndar y syste m ass ocia ted wit h a DBA caus ing t he lea k ra te f rom flaws leaking during no rmal operation to leak at hi gher rates; or (2) the higher loadi ngs associated with a D BA causing a flaw that w as not leakin g during normal op eration to l eak during the accid ent.Responding to the NRC staff's questi on on this issue, the l icensee, in its letter da ted June 2, 2 006, des crib ed c ontr ols and proc edur es to ens ure t hat t he a cci dent-ind uced lea kage limit is no t exc eeded as a r esult of oper ation al le akage. Th ese co ntrols and p rocedu res are intended to ensure that the accident-ind uced leakage li mit (and operati onal leakage l imit) is not exceeded.
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| These controls a nd procedures include co mbinations o f monitoring, notificati ons, setpoint ve rifications, and shutdown preparations w hen the primary-to-secondary steam generator tube le ak rate reaches ce rtain val ues. The NRC staff reviewed the adequacy of the proposed TS cri teria for operatio nal and ac cident-induc ed leakage. The TS cri teria on operational and accident-induced leakag e are consistent with TSTF-449 and the licensee's accident ana lysis; the refore, the NRC sta ff finds the licensee
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| 's proposed TS criteria on these valu es acc eptabl e. As a re sult o f adopti ng TSTF-4 49, the lice nsee a lso p ropose d chan ges to th e requi rements pertai ning to reacto r cool ant sy stem op eratio nal l eakage (e.g., add ing de finiti ons to TS 1.0.t, modify ing act ion s tatemen ts in TS 3.1.d , and a dding surve illa nce re quireme nts in TS 4.18). These TS change s wer e nece ssary to faci litat e adop ting th e prop osed c hanges in TSTF-449. Sin ce th ese prop osed TS ch ange s pe rtai nin g to r eact or co ola nt sy stem ope rati onal lea kage we re g ene ral ly con sis ten t w ith the STS an d th e p la nt's l ice nsi ng b asi s, t he NRC sta ff determined that the proposed c hanges were acceptable.
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| 3.2 Conclusio n The pro posed TS cha nges es tabli sh a p rogrammat ic, l argely performa nce-ba sed re gulato ry framework for ensuring SG tub e integrity i s maintained. The NRC staff finds tha t it addresses key shortcomings o f the current framework by ensuring that S G programs are focused on accomplishi ng the overal l objectiv e of maintainin g tube integrity.
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| It incorporates performance criteria for ev aluating tube integrity that the NRC staff finds con sistent wi th the structural margins and th e degre e of le ak tightn ess as sumed i n the c urrent plant lice nsing b asis. The NRC staff finds that mai ntaining these performance criteria provides reasonable assurance that the SGs c an b e op erat ed s afel y w itho ut i ncre ase in r isk.The proposed TSs chang es contain limited specific details concerning how the SG Program is to achiev e the required o bjective of mai ntaining tube integrity; the intent bein g that the lice nsee wil l hav e the fl exib ilit y to d etermi ne the speci fic stra tegy for meetin g this o bjecti ve. Howeve r, the NRC staff finds tha t the revise d TSs includ e sufficient regulatory constraints on the establishment and implement ation of the SG Progr am such as to provide reasonable assurance that tu be integrity will be maintaine d.Failure to meet the perfo rmance criteria will be reportable pursuant to the requirements in 10 CFR Parts 50.72 and 5 0.73. The NRC reactor oversi ght process prov ides a proce ss by which the NRC staff can ve rify that the l icensee has identified a ny SG Program de ficiencies tha t may have contributed to such an occurre nce and that a ppropriate corre ctive acti ons have been implemented.
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| In conclusi on, the NRC staff finds that the TS changes proposed by the licen see in its January 12, 2006, appli cation, as su pplemented by a letter dated June 2, 2006 , conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assura nce that SG tube in tegr ity is maint ained witho ut undue risk to public heal th and saf ety.4.0 ENVIR ONME NTAL C ONSIDE RATION This am endmen t chan ges a re quireme nt wi th resp ect to insta llati on or u se of a fa cili ty component loca ted withi n the restricted area as define d in 10 C FR Part 20.
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| The NRC staff has determined that the amendment in volves no significant increase in the amounts, and no significant change in the typ es, of any effluent tha t may be rel eased offsite and tha t there is no signifi cant i ncreas e in i ndiv idual or cumu lativ e occu patio nal ra diati on ex posure. The Commission has previ ously i ssued a propo sed finding that th is amendment i nvolve s no sign ific ant h aza rds c onsi dera tion and ther e ha s be en n o pu bli c co mmen t on such find ing (71 FR 7806).
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| Accordingly , this amendment meets the eli gibility criteria for categori cal exclusio n set forth in 10 CFR 51.22(c)(9
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| ). Pursuant to 1 0 CFR 51.22 (b) no envi ronmental impact statement or environmenta l assessment n eed be prepa red in conne ction wi th the issua nce of th is ame ndment. 5.0 CONCL USION The NRC staff has concluded, based on the considerations discussed above, th at: (1) there is reasonable a ssurance that the health and safety of the publ ic wil l not be en dangered by operation i n the proposed manner, (2) such activiti es wil l be condu cted in compl iance w ith the Commission's re gulations, and (3) the issua nce of this amend ment will not be ini mical to the common defense and s ecuri ty or to the healt h and safety of the p ubli c. Princ ipal Contri butor: Eric M. Tho mas Date: July 17, 2006}}
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Letter Sequence Approval |
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TAC:MC9581, Steam Generator Tube Integrity (Approved, Closed) |
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Category:Letter
MONTHYEARML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24136A1952024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report ML24130A0022024-05-0909 May 2024 Summary of Facility Changes, Tests and Experiments and Commitment Changes IR 05000305/20240012024-05-0202 May 2024 NRC Inspection Report No. 05000305/2024001 ML24121A2472024-04-29029 April 2024 and Three Mile Island, Unit 2 - 2023 Occupational Radiation Exposure Annual Report ML24101A0422024-04-22022 April 2024 Solutions Inc. – Exemption from Select Requirements of 10 CFR Part 73 ((Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24106A0492024-04-15015 April 2024 2023 Annual Radioactive Effluent Release Report ML24080A0702024-03-20020 March 2024 Decommissioning Trust Fund Annual Report ML24079A0162024-03-19019 March 2024 Annual Property Insurance Status Report ML24073A2312024-03-13013 March 2024 and Three Mile Island Nuclear Station, Unit 2 - Management Change ML24061A0202024-02-15015 February 2024 (Ksp) ISFSI, Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 6 ML23339A1332024-01-26026 January 2024 Exemption from the Req of 10 CFR Part 50.82(a)(8)(i)(A) to Use the Kewaunee Decommissioning Trust Fund for the Management of Site Restoration Activities IR 05000305/20230022023-12-27027 December 2023 NRC Inspection Report 05000305/2023002 (Drss); 07200064/2023001 (Drss) ML23332A1922023-11-28028 November 2023 Solutions, Inc., Request for Exemptions from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23278A1002023-10-0505 October 2023 Response to Request for Additional Information (RAI) Application for Kewaunee Solutions (Ks) Site Restoration Activities ML23222A1522023-08-29029 August 2023 Letter RAI KPS Exemption Site Restoration Final Repaired IR 05000305/20230012023-08-17017 August 2023 NRC Inspection Report No. 05000305/2023001-Kewaunee Power Station ML23171B0822023-07-0505 July 2023 Letter - Kewaunee Power Station - Issuance of Exemption from Certain Requirements from 10 CFR Part 20, Appendix G, Section Iii.E ML23132A0012023-05-11011 May 2023 2022 Annual Radiological Environmental Operating Report ML23116A2182023-04-26026 April 2023 2022 Annual Radioactive Effluent Release Report ML23089A3042023-03-30030 March 2023 Decommissioning Fund Status Report ML23093A0312023-03-29029 March 2023 Solutions, Inc., Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 50.75(h)(1)(iv) for Site Restoration Activities ML23088A2752023-03-29029 March 2023 Solutions, Inc., Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML23087A0402023-03-27027 March 2023 Annual Property Insurance Status Report ML23087A0292023-03-27027 March 2023 2022 Annual Report of Occupational Radiation Exposure ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring IR 05000305/20220022023-01-0303 January 2023 NRC Inspection Report Nos. 05000305/2022002(DRSS) Kewaunee Power Station ML22292A2302022-11-25025 November 2022 U.S. Nuclear Regulatory Commissions Analysis of Dominion Energy Kewaunees Decommissioning Funding Status Report for Kewaunee Power Station, Docket No. 50-305 ML22290A0052022-10-13013 October 2022 Resubmittal of Kewaunee Power Station Independent Spent Fuel Storage Installation (ISFSI) Only Emergency Plan (Ioep) and IOEP- Emergency Action Level (EAL) Basis Document, Revision 0KS ML24061A0182022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Pla11, Training and Qualification Plan and Safeguards Contingency Plan Revision 5 ML22241A0302022-08-25025 August 2022 (Ksp) ISFSI Submittal of Security Plan, Training and Qualification Plan and Safeguards Contingency Plan, Revision 5 IR 05000305/20220012022-08-0101 August 2022 NRC Inspection Report Nos. 05000305/2022001(DNMS) - Kewaunee Power Station ML22215A1512022-07-27027 July 2022 Executed Financial Assurance Instruments for the Kewaunee License Transfer License No. DPR-43 (Docket Nos. 50-305, 72-64) ML22209A1252022-07-26026 July 2022 Amendment No. 11 to Indemnity Agreement No. B-53 for Kewaunee Power Station (KPS) - Signed by Kewaunee Solutions, Inc ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure ML22160A5262022-06-28028 June 2022 Letter - KPS - Issuance of Conforming License Amendment Regarding Indirect Transfer of License from DEK, Inc. to Kewaunee Solutions, Inc ML22160A5272022-06-28028 June 2022 Enclosure 1 - Amendment No. 221 to Renewed Facility Operating License No. DPR-43 ML22160A5282022-06-28028 June 2022 Enclosure 2 - Amendment No. 11 to Indemnity Agreement B-53 ML22188A0812022-06-23023 June 2022 ISFSI, Virgil C. Summer Nuclear Station, Unit 1 & ISFSI, North Anna Power Station, Units 1 & 2 & ISFSI, Surry Power Station, Units 1 & 2 & ISFSI - Submission of Revision 32 of the Quality Assurance Topical Report ML22172A2452022-06-22022 June 2022 Notification of Planned Closing Date and Required Regulatory Approvals for the Kewaunee License Transfer Transaction ML22175A0662022-06-17017 June 2022 Designation of Additional Reviewing Official for ISFSI and 10 CFR Part 37 Program Security Background Investigations ML22166A3392022-06-13013 June 2022 Notification of Nuclear Insurance ML22138A2552022-05-10010 May 2022 Submittal of 2021 Annual Radiological Environmental Operating Report ML22158A2112022-05-10010 May 2022 Summary of Facility Changes, Tests and Experiments and Summary of Commitment Changes ML22091A1892022-04-0101 April 2022 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML22108A0352022-04-0101 April 2022 License Transfer to Kewaunee Solutions, Inc ML22089A2432022-03-30030 March 2022 Decommissioning Funding Status Report, Financial Test and Independent Public Accountants' Letter of Attestation ML22076A0652022-03-15015 March 2022 Energy Solutions and Dominion Energy Kewaunee - Supplement to License Transfer Application Related to Use of Existing Dominion Energy Quality Assurance Program ML22060A1912022-02-25025 February 2022 Response to Request for Additional Information Related to Submittal for Approval of the Kewaunee Solutions Decommissioning Quality Assurance Program (Dqap), Revision O for Kewaunee Power Station (KPS) 2024-06-03
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML17123A0282017-06-0707 June 2017 Enclosure 1 - KPS Amendment 220 Regarding Permanent Removal of Spent Fuel for the Spent Fuel Pool - LAR260 ML17052A5912017-05-0909 May 2017 KPS Amendment 219 - Removal of Cyber Security Requirements for Operating License ML16341C7912017-03-0202 March 2017 Enclosure 1 - Amendment to Facility Operating License ML16320A0442016-11-30030 November 2016 Amendment No. 217 ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML14237A0452015-02-13013 February 2015 Issuance of Amendment No. 215, Revise Operating License and Technical Specifications to the Permanently Defueled Technical Specifications Consistent with Permanent Cessation of Reactor Operation ML14008A2972014-06-23023 June 2014 Issuance of Amendment No. 213 - Deletion of License Conditions Associated with Extended Operations ML14111A2342014-06-0909 June 2014 Issuance of Amendment No. 212 Revise Operating License and Technical Specifications to the Permanently Defueled Technical Specifications Consistent with Permanent Cessation of Reactor Operation ML11192A2492011-08-31031 August 2011 Issuance of Amendment Regarding Cyber Security to Dominion Plants ML11102A0272011-07-29029 July 2011 Issuance of Amendment License Amendment Request to Change the Current Licensing Basis for Automatic Operation of Transformer Load Tap Changers ML1110105232011-04-29029 April 2011 Issuance of Amendment 208 Regarding Technical Specification Change Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection for 52.1 Effective Full Power Years ML0530403522011-02-24024 February 2011 Current Facility Operating License DPR-43, Tech Specs, Revised 10/07/2015 ML1101006002011-02-24024 February 2011 Renewed License ML1101005752011-02-24024 February 2011 Issuance of Renewed Facility Operating License No. DPR-043 for Kewaunee Power Station ML1033706912011-02-0202 February 2011 Part 080 ME2139 List of Acronyms and Abbreviations ML1020206622011-02-0202 February 2011 Issuance of Amendment for Conversion to Improved Technical Specifications with Beyond Scope Issues ML1002110292009-08-0303 August 2009 2009 Kewaunee Power Station Retake Examination Proposed Exam Files ML0912710592009-06-0101 June 2009 License Amendment No. 206, Containment Purge and Vent Isolation Valves Surveillance Requirement ML0905707102009-04-30030 April 2009 Issuance of Amendment No. 205 Seismic Analysis Methodology for the Auxiliary Building Crane ML0905708922009-04-27027 April 2009 Issuance of Amendment No. 204 Re. One-time Extension of the 15-Year Containment Integrated Leak Rate Test Interval ML0902805812009-02-0606 February 2009 Issuance of Amendment No. 203 Regarding Diesel Generator Fuel Storage Tank Capacity Requirement ML0833607832009-01-0909 January 2009 Issuance of Amendment Steam Line Isolation Function Applicability (Tac No. MD8544) ML0832906532008-12-30030 December 2008 License Amendment, Issuance of Amendment No. 201 Shield Building and Auxiliary Building Special Ventilation Train Filter Heater Requirements ML0829710792008-11-20020 November 2008 Issuance of Amendment to Relocate Spent Fuel Pool Crane Requirements from the Technical Specifications to the Technical Requirements Manual ML0829405472008-11-0606 November 2008 License Amendment, Increased the Minimum Required Safety Injection Accumulator Boron Concentration from 1900 parts-per-million (Ppm) to 2400 Ppm ML0816201402008-07-0202 July 2008 Issuance of Amendment Deletion of License Condition on Fuel Burnup ML0804603632008-03-28028 March 2008 Issuance of Amendment Regarding Nuclear Instrumentation System Permissive Setpoints ML0807701792008-03-28028 March 2008 Issuance of Amendments Licensing Basis Design Criteria Associated with Internal Flooding ML0728802892007-10-31031 October 2007 License Amendment Regarding Relocation of Technical Specifications Requirements ML0721300932007-08-0202 August 2007 Revised Pages of Facility Operating License No. DPR-43 ML0711100062007-05-18018 May 2007 Issuance of Amendment Refueling Water Storage Tank Boron Concentration ML0712001862007-05-0101 May 2007 Issuance of License Amendment 191 Regarding Emergency Diesel Generator Rated Load Testing ML0704300202007-03-0808 March 2007 Radiological Accident Analysis ML0631800362006-12-14014 December 2006 License Amendment 189 Regarding Referencing the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Operation and Maintenance of Nuclear Power Plants ML0617002082006-07-17017 July 2006 Issuance of Amendment Steam Generator Tube Integrity ML0616402862006-07-12012 July 2006 Issuance of Amendment Surveillance Interval Extension ML0532100822005-11-18018 November 2005 Correction to Amendment 186 ML0521504282005-10-0404 October 2005 Issuance of License Amendment 186 Regarding Technical Specification Changes for Radioactive Effluents Control Program and Off-Site Dose Calculation Manual ML0518801062005-07-0505 July 2005 Issuance of Conforming Amendment Re Transfer of Facility Operating License from Nuclear Management Company, Wisconsin Public Service Corp and Wisconsin Power and Light Company to Dominion Energy Kewaunee, Inc ML0517100302005-06-21021 June 2005 Emergency License Amendment, Revises the TSs to Remove the Requirement to Have a Containment Spray Pump Suction Flow Path from the Containment Sump ML0516000912005-06-20020 June 2005 Issuance of Amendment Auxiliary Feedwater System ML0503902742005-04-0606 April 2005 Issuance of License Amendment 182 Relocation of Surveillance Requirements ML0505407072005-03-24024 March 2005 License Amendment, Revised Technical Specification Rod Position Indication ML0435001062005-02-15015 February 2005 Issuance of License Amendment 180 Administrative Changes to Technical Specifications ML0433800022004-12-22022 December 2004 Issuance of Amendment Deletion of Requirements for Submittal of Occupational Radiation Exposure Reports, Reports of Challenges to and Failures of the Pressurizer Power Operated Relief Valves and Safety Valves ML0431200302004-10-29029 October 2004 Administrative Change to Facility Operating License in Conjunction with the Commission Order EA-03-086 Regarding Revised Design Basis Threat... ML0514402972004-10-26026 October 2004 Revision to Emergency Action Levels, Facility Operating License as Amended Through October 21, 2004 Document ML0426400982004-10-0505 October 2004 License Amendment, Revises TS 3.3.a.2.B, by Extending Completion Time from 1 Hour to 24 Hours for an Accumulator That Is Inoperable for Any Reason Other than Failure to Meet Minimum Boron Concentration Requirements ML0416100952004-09-24024 September 2004 Issuance of Amendment No. 177 Re. Revision of TS 3.3.e, Service Water System ML0422300682004-09-22022 September 2004 License Amendment No. 176, Revise TS 3.10.f.2 to Add an Allowed Outage Time for the Individual Rod Position Indication (Irpi) System of 24 Hours with More than One Irpi Group Inoperable & Adds the Definition of Immediately to TS Section 1.0 2017-06-07
[Table view] Category:Safety Evaluation
MONTHYEARML23339A1362024-01-26026 January 2024 Safety Evaluation Re NRC Issuance of Exemption for Site Restoration ML23024A0122023-01-26026 January 2023 Letter to Energysolutions Transmitting Threshold Determination for Merger/Restructuring ML22175A1132022-06-30030 June 2022 Solutions, Inc. - Letter for Review and Acceptance of the Energysolutions, LLC Decommissioning Quality Assurance Program with Enclosure ML18225A0202018-08-29029 August 2018 ISFSI; North Anna 1 & 2 Isfsls, and Unit 3; Surry Power 1 & 2, and Isfsls); Dominion Energy Kewaunee, Inc. (Kewaunee Power Station and Isfsi): Request for Threshold Determination Under 10 CFR 50.80 ML17332A0782017-12-12012 December 2017 ISFSI; Millstone and ISFSI; North Anna and ISFSI; Surry and ISFSI - Request for Approval of Revision 24 of the Nuclear Facility Quality Assurance Program Description Topical Report, DOM-QA-1 (CAC Nos. MF9732-MF9739; EPID L-2017-LLQ-0001) ML17123A0292017-06-0707 June 2017 Enclosure 2 - Safety Evaluation Report Related to the Unloaded Spent Fuel Pool at KPS - LAR260 ML17046A3162017-04-0606 April 2017 Connecticut, Virginia, Millstone, North Anna, Surry, Submission of Revision 21 of the Quality Assurance Topical Report for NRC Approval and Submission Revision 22 for Information Only (CAC Nos. MF8128 - MF8234) ML15245A4822015-10-0707 October 2015 Millstone Power Station, Surry Power Station, and North Anna Power Station - Issuance of Amendments to Revise the Cyber Security Milestone 8 Completion Date in the Renewed Facility Operating Licenses ML14237A0452015-02-13013 February 2015 Issuance of Amendment No. 215, Revise Operating License and Technical Specifications to the Permanently Defueled Technical Specifications Consistent with Permanent Cessation of Reactor Operation ML14279A4822014-10-31031 October 2014 Issuance of Amendment, No. 214 Revise Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML14261A2232014-10-27027 October 2014 Letter and Safety Evaluation, Exemptions from Emergency Planning Requirements of 10 CFR 50.47 and 10 CFR 50 Appendix E ML14008A2972014-06-23023 June 2014 Issuance of Amendment No. 213 - Deletion of License Conditions Associated with Extended Operations ML14111A2342014-06-0909 June 2014 Issuance of Amendment No. 212 Revise Operating License and Technical Specifications to the Permanently Defueled Technical Specifications Consistent with Permanent Cessation of Reactor Operation ML14104A0462014-05-12012 May 2014 Approval of Certified Fuel Handler Training Program ML12271A3662012-10-0404 October 2012 Relief Request Number RR-2-4 Regarding Fourth 10-Year Interval Inservice Inspection Program ML12249A4412012-09-20020 September 2012 Evaluation of Relief Request Number RR-G-5 Regarding Fourth 10-Year Interval Inservice Inspection Program ML1200505532012-02-17017 February 2012 Millstone Power Station Units 2 and 3, North Anna Power Station, Units 1 and 2, Surry Power Station Units 1 and 2 - Review of Dominion Fleet Quality Assurance Topical Report, Revision 11 ML11271A1782011-10-0303 October 2011 Review of Topical Report, Revision 11 for Kewaunee Power Station and ISFSI, Millstone Power Station, Units 1, 2, & 3 and ISFSI, North Anna Power Station, Units 1 & 2 and ISFSI, Surry Power Station, Units 1 & 2 and ISFSI (Tac ME6649, ME6650, ML11192A2492011-08-31031 August 2011 Issuance of Amendment Regarding Cyber Security to Dominion Plants ML11102A0272011-07-29029 July 2011 Issuance of Amendment License Amendment Request to Change the Current Licensing Basis for Automatic Operation of Transformer Load Tap Changers ML1110105232011-04-29029 April 2011 Issuance of Amendment 208 Regarding Technical Specification Change Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection for 52.1 Effective Full Power Years ML1033605042011-02-0202 February 2011 Part 002 ME2139 Safety Evaluation and Safety Evaluation Attachments ML1020206622011-02-0202 February 2011 Issuance of Amendment for Conversion to Improved Technical Specifications with Beyond Scope Issues ML1019701932010-08-22022 August 2010 Approval of Revision to Previously Approved IST Relief Request VRR-5 ML1016200342010-06-21021 June 2010 Approval to Remove Mixing Vane Grid Restriction in Appendix B of Dominion Fleet Topical Report DOM-NAF-2-A ML0934106522009-12-22022 December 2009 Authorization of Proposed Alternative RR-1-11 Regarding Visual Examinations for Reactor Pressure Vessel Bottom-Mounted Instrument Penetrations ML0923210792009-09-28028 September 2009 Irradiated Fuel Management Program and Preliminary Decommissioning Cost Estimate ML0905707102009-04-30030 April 2009 Issuance of Amendment No. 205 Seismic Analysis Methodology for the Auxiliary Building Crane ML0905708922009-04-27027 April 2009 Issuance of Amendment No. 204 Re. One-time Extension of the 15-Year Containment Integrated Leak Rate Test Interval ML0902805812009-02-0606 February 2009 Issuance of Amendment No. 203 Regarding Diesel Generator Fuel Storage Tank Capacity Requirement ML0833607832009-01-0909 January 2009 Issuance of Amendment Steam Line Isolation Function Applicability (Tac No. MD8544) ML0829710792008-11-20020 November 2008 Issuance of Amendment to Relocate Spent Fuel Pool Crane Requirements from the Technical Specifications to the Technical Requirements Manual ML0829405472008-11-0606 November 2008 License Amendment, Increased the Minimum Required Safety Injection Accumulator Boron Concentration from 1900 parts-per-million (Ppm) to 2400 Ppm ML0816201402008-07-0202 July 2008 Issuance of Amendment Deletion of License Condition on Fuel Burnup ML0814902822008-05-20020 May 2008 Submittal of Approved Topical Report DOM-NAF-5, Revision 0.0-A, Application of Dominion Nuclear Core Design and Safety Analysis Methods to the Kewaunee Power Station (KPS) ML0807701792008-03-28028 March 2008 Issuance of Amendments Licensing Basis Design Criteria Associated with Internal Flooding ML0804603632008-03-28028 March 2008 Issuance of Amendment Regarding Nuclear Instrumentation System Permissive Setpoints ML0806305402008-03-28028 March 2008 Issuance of License Amendment 196 Nuclear Core Design and Safety Analysis Methods ML0801604122008-02-0707 February 2008 Issuance of Amendment Regarding Emergency Diesel Generator Testing ML0728802892007-10-31031 October 2007 License Amendment Regarding Relocation of Technical Specifications Requirements ML0722903732007-08-30030 August 2007 Safety Evaluation for Topical Report DOM-NAF-5 ML0721102772007-08-14014 August 2007 Reactor Vessel Surveillance Capsule Test Results for Capsule T ML0721200032007-08-0202 August 2007 Conforming License Amendment to Incorporate the Mitigation Strategies Required by Section B.5.b. of Commission Order EA-02-026 Tac No. MD4543) ML0711100062007-05-18018 May 2007 Issuance of Amendment Refueling Water Storage Tank Boron Concentration ML0712001862007-05-0101 May 2007 Issuance of License Amendment 191 Regarding Emergency Diesel Generator Rated Load Testing ML0704300202007-03-0808 March 2007 Radiological Accident Analysis ML0631800362006-12-14014 December 2006 License Amendment 189 Regarding Referencing the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Operation and Maintenance of Nuclear Power Plants ML0624205112006-08-30030 August 2006 Approval of Topical Report DOM-NAF-3 ML0617002082006-07-17017 July 2006 Issuance of Amendment Steam Generator Tube Integrity ML0616402862006-07-12012 July 2006 Issuance of Amendment Surveillance Interval Extension 2024-01-26
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July 17, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
KEWAUNEE POWER STATION - ISSUANCE OF AMENDMENT RE: STEAM GENERATOR TUBE INTEGRITY (TAC NO. MC9581)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No.188 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the Technical Specifications (TSs) in response to your application dated January 12, 2006, as supplemented by letter dated June 2, 2006.
The amendment revises the existing steam generator (SG) tube surveillance program to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the NRC and published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
David H. Jaffe, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305
Enclosures:
- 1. Amendment No. 188 to License No. DPR-43
- 2. Safety Evaluation cc w/encls: See next page
ML061700208 - PACKAGE: ML061700091 - TS:ML061720131 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/TSB/BC OGC NRR/LPL3-1/BC NAME DJaffe THarris TKobetz* APH P. Tam for LRaghavan DATE 6/30/06 6/30/06 6/15 /06 7/6/06 7/17/06 OFFICE NRR/CSGB/BC NRR/TSB/BC NAME A.Hetser ACH CSchulten for TKobetz DATE 7/13/06 7/17/06
Kewaunee Power Station cc:
Resident Inspectors Office Ms. Lillian M. Cuoco, Esq.
U.S. Nuclear Regulatory Commission Senior Counsel N490 Highway 42 Dominion Resources Services, Inc.
Kewaunee, WI 54216-9510 Millstone Power Station Building 475, 5th Floor Regional Administrator, Region III Rope Ferry Road U.S. Nuclear Regulatory Commission Waterford, CT 06385 Suite 210 2443 Warrenville Road Plant Manager Lisle, IL 60532-4351 Kewaunee Power Station N490 Highway 42 David Zellner Kewaunee, WI 54216-9511 Chairman - Town of Carlton N2164 County B Kewaunee, WI 54216 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin PO Box 7854 Madison, WI 53707-7854 Mr. Michael G. Gaffney Dominion Energy Kewaunee, Inc.
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominion Energy Kewaunee, Inc.
Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216
DOMINION ENERGY KEWAUNEE, INC.
DOCKET NO. 50-305 KEWAUNEE POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. DPR-43
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Dominion Energy Kewaunee, Inc. dated January 12, 2006, as supplemented by letter dated June 2, 2006, 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. 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 Facility Operating License No. DPR-43 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, are hereby incorporated in the license. The licensees 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: July 17, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 188 FACILITY OPERATING LICENSE NO. DPR-43 DOCKET NO. 50-305 Replace the following page of Facility Operating License No. DPR-43 with the attached revised page. The changed area is identified by a marginal line.
REMOVE INSERT Page 3 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 INSERT TS i TS i TS ii TS ii TS iii TS iii TS iv TS iv TS v TS v
- TS 1.0-7 TS 3.1-8 TS 3.1-8
- TS 3.1-11 TS 4.2-2 TS 4.2-2 TABLE TS 4.2-2 TABLE TS 4.2-2
- TS 4.18-1
- TS 4.19-1
C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR, Chapter 1: (1) Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, (2) 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 (3) 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 1772 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, are hereby incorporated in the license. The licensee shall operate the facility In accordance with the Technical Specifications.
(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the licensee's Fire Plan, and as referenced in the Updated Safety Analysis Report, and as approved in the Safety Evaluation Reports, dated November 25, 1977, and December 12, 1978 (and supplement dated February 13, 1981) 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.
(4) Physical Protection 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 combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision 0)" submitted by letter dated October 18, as supplemented by letter dated October 21, 2004.
(5) Fuel Burnup The maximum rod average burnup for any rod shall be limited to 60 GWD/MTU until completion of an NRC environmental assessment supporting an increased limit.
Amendment No. 188 3
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION DOCKET NO. 50-305
1.0 INTRODUCTION
By letter dated January 12, 2006, as supplemented on June 2, 2006 (Agencywide Documents Access and Management System Accession Nos. ML060250524 and ML061560144, respectively), Dominion Energy Kewaunee (the licensee) submitted a request for changes to the Kewaunee Power Station Technical Specifications (TSs). The requested changes would revise the existing steam generator (SG) tube surveillance program to be consistent with TS Task Force (TSTF) Change TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the U.S. Nuclear Regulatory Commission (NRC) and published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), changes to the SG reporting requirements, and associated changes to the TS Bases.
The June 2, 2006, letter provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 14, 2006 (71 FR 7806).
2.0 REGULATORY EVALUATION
The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model safety evaluation (SE) published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process, published in the Federal Register on May 6, 2005 (70 FR 24126), made the model SE available to licensees for use.
ENCLOSURE
3.0 TECHNICAL EVALUATION
3.1 Overview In its January 12, 2006, application, as supplemented by a letter dated June 2, 2006, the licensee proposed changes to the TSs that are consistent, with one exception, with the proposed changes approved in TSTF-449. The NRC model SE provides a detailed evaluation of the proposed changes that are requested based upon the NRCs Standard Technical Specifications (STS) as contained NUREGs 1430 - 1432. Since the licensee uses TS that do not conform to the STS, the TS section numbers in its application do not reflect those listed in TSTF-449. Consistent with TSTF-449, the proposed TS changes include: (1) new TS 1.0.t, LEAKAGE, (2) a revised TS 3.1.d, "RCS Operational LEAKAGE," (3) a new TS 3.1.g, "Steam Generator (SG) Tube Integrity," (4) a new TS 4.18, RCS Operational Leakage, (5) a new TS 4.19, Steam Generator (SG) Tube Integrity which replaces existing TS 4.2.b, Steam Generator Tubes, (6) a new TS 6.9.b.3, Steam Generator Tube Inspection Report,, (7) a new TS 6.22, Steam Generator (SG) Program, and (8) revised Table of Content pages to reflect the proposed changes.
The NRC staff reviewed the licensees application for consistency with TSTF-449 to ensure the generic safety evaluation was bounding. The NRC staff made the following observations as a result of its review.
In TSTF-449, the limit on normal operating primary-to-secondary leakage rate through any one SG was significantly less than that assumed in the Kewaunee safety analysis. However, for Kewaunee, the normal operational primary-to-secondary leakage limit (150 gallons per day per steam generator) is identical to the accident induced primary-to-secondary leakage limit for design basis accidents (DBAs) other than a steam generator tube rupture. Given this situation, the NRC staff evaluated the acceptability of this difference between TSTF-449 and the licensees submittal. Since the leakage rate observed during operation may increase during a design-basis accident, in order to meet both limits, it may be necessary to ensure that the operational leak rate is kept well below the operational leak rate limit. This increase in leak rate can be a result of either: (1) the higher differential pressure between the primary coolant system and the secondary system associated with a DBA causing the leak rate from flaws leaking during normal operation to leak at higher rates; or (2) the higher loadings associated with a DBA causing a flaw that was not leaking during normal operation to leak during the accident.
Responding to the NRC staffs question on this issue, the licensee, in its letter dated June 2, 2006, described controls and procedures to ensure that the accident-induced leakage limit is not exceeded as a result of operational leakage. These controls and procedures are intended to ensure that the accident-induced leakage limit (and operational leakage limit) is not exceeded. These controls and procedures include combinations of monitoring, notifications, setpoint verifications, and shutdown preparations when the primary-to-secondary steam generator tube leak rate reaches certain values. The NRC staff reviewed the adequacy of the proposed TS criteria for operational and accident-induced leakage. The TS criteria on operational and accident-induced leakage are consistent with TSTF-449 and the licensees accident analysis; therefore, the NRC staff finds the licensees proposed TS criteria on these values acceptable.
As a result of adopting TSTF-449, the licensee also proposed changes to the requirements pertaining to reactor coolant system operational leakage (e.g., adding definitions to TS 1.0.t, modifying action statements in TS 3.1.d, and adding surveillance requirements in TS 4.18).
These TS changes were necessary to facilitate adopting the proposed changes in TSTF-449.
Since these proposed TS changes pertaining to reactor coolant system operational leakage were generally consistent with the STS and the plant's licensing basis, the NRC staff determined that the proposed changes were acceptable.
3.2 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis.
The NRC staff finds that maintaining these performance criteria provides reasonable assurance that the SGs can be operated safely without increase in risk.
The proposed TSs changes contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective.
However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.
Failure to meet the performance criteria will be reportable pursuant to the requirements in 10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.
In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its January 12, 2006, application, as supplemented by a letter dated June 2, 2006, conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 7806). Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
5.0 CONCLUSION
The NRC staff 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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Eric M. Thomas Date: July 17, 2006