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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
 
==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:==
==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.
 
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


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:


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


==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
 
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==


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         


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         


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.
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
). 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.
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
). The "Notice o f Availabi lity of M odel Appl ication Co ncerning Technic al Specification
; 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.
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.
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.
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
'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.
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.
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.
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.
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).
Accordingly , this amendment meets the eli gibility criteria for categori cal exclusio n set forth in 10 CFR 51.22(c)(9
). 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}}

Revision as of 17:30, 23 November 2019

Issuance of Amendment Steam Generator Tube Integrity
ML061700208
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 07/17/2006
From: Jaffe D
NRC/NRR/ADRO/DORL/LPLIII-1
To: Christian D
Dominion, Dominion Energy Kewaunee
D. Jaffe LPL3-1
Shared Package
ML061700091 List:
References
TAC MC9581
Download: ML061700208 (10)
v • d • e


Text

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

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