Letter Sequence RAI |
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MONTHYEARML20249B7471998-06-23023 June 1998 Forwards RAI Re 980601 Proposed Amend to Revise F* & Ef* Criteria for SG Tubes in Kewaunee Tss.Proposed Amend Would Revise Existing F* & Ef* Distances in TS 4.2.b to Reflect Changes to Primary to Secondary Differential Pressure Project stage: RAI 1998-06-23
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211D7501999-08-23023 August 1999 Responds to NRC Re Violations Noted in OI Rept 3-98-043 & EA 99-183.Corrective Actions:Oversight of Training Program & Contractor Policies That Implement Parts of Security Program Have Been Increased by Addl Position ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls ML17230A3661999-03-18018 March 1999 Forwards Listed Nelia Insurance Policy Endorsements for Kewaunee Nuclear Power Plant,Per Requirements of 10CFR140.15 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C ML20154F1481998-10-0202 October 1998 Forwards Insp Rept 50-305/98-15 on 980831-0904.No Violations Noted.Insp Exam of Activities Conducted Under License Re Physical Security & to Compliance with Commission Rules & Regulations & with Conditions of License ML20237E0881998-08-24024 August 1998 Clarifies Info Provided Re Containment Ventilation Sys & Use of Mixing Factor of 0.5,in Response to NRC Request Made During Telcon ML20237A2301998-08-0707 August 1998 Forwards Original & Three Copies of Rev 11 to Knpp Security Manual.Screening Criteria Form for Each Change W/Description & Criteria of Review Has Been Included as Attachment A. Reissued Security Manual Included in Attachment B.W/O Encls ML20236R9051998-07-21021 July 1998 Informs That Document Entitled, WCAP-14677,Rev 1 F* & Elevated F* Tube Alternate Repair Criteria for Tubes W/Degradation within Tubesheet Region of Kewaunee Sgs, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20249B7471998-06-23023 June 1998 Forwards RAI Re 980601 Proposed Amend to Revise F* & Ef* Criteria for SG Tubes in Kewaunee Tss.Proposed Amend Would Revise Existing F* & Ef* Distances in TS 4.2.b to Reflect Changes to Primary to Secondary Differential Pressure ML20249A8751998-06-16016 June 1998 Forwards Request for Addl Info Re Proposed Amend to Redefine Parent Tube Pressure Boundary for Westinghouse Mechanical Hybrid Expansion Joint SG Tube Sleeves,Submitted by Util ML20248M2521998-06-0909 June 1998 Forwards Assessment of Kewannee Cycle 22 Alternate Repair Criteria 90 Day Rept,For Info ML20217F3401998-04-23023 April 1998 Forwards Annual Environ Monitoring Rept Jan-Dec 1997, Per TS 6.9.b.1.Results of 1997 Land Use Census,Iaw Plant ODCM, Section 3/4.7.1,included in Rept ML20216B3281998-04-0707 April 1998 Discusses Amend 132 to License DPR-43.Requested Revised Analysis Reflecting Higher Source Term Encl.Results of Analysis Conclude That Potential Thyroid Doses to Public Continue to Be Less than Guideline Values of 10CFR100 ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217H4031998-03-27027 March 1998 Informs That NRC Staff Has Initiated Variety of Activities Re Mgt of Licensing Basis Info as Result of Problems Encountered at Millstone & Maine Yankee Facilities ML20217G1461998-03-25025 March 1998 Responds to NRC Re Violations Noted in Insp Rept 50-305/98-03 on 980128-0203.Corrective Actions:Controlling & Properly Securing SGI ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl ML20212H0121997-11-0404 November 1997 Forwards Insp Rept 50-305/97-14 on 970915-19.No Violations Noted.Rept Identifies Areas Examined within Security Program ML20217P3511997-08-26026 August 1997 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Proposed by NRC in . Corrective Actions Will Be Examined During Future Insp ML20217J9641997-08-11011 August 1997 Responds to NRC Re Violations Noted in Insp Rept 50-305/97-02 on 970106-31.Corrective Actions:Will Revise IST Procedures to Use More Accurate Instrumentation Satisfying Requirements & to Include Acceptance Criteria ML20140E8861997-06-0707 June 1997 Forwards Amend 133 to License DPR-43 & Safety Evaluation. Amend Establishes New Design Basic Flow Rate for AFW Pumps Consistent W/Assumptions Used in Reanalysis of Limiting Design Basis Event for AFW Sys ML20140F2171997-04-30030 April 1997 Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR IA-97-130, Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR1997-04-30030 April 1997 Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR ML20140F2211997-04-0404 April 1997 FOIA Request for Documents Re Recently Issued TIA for Plant Concerning Safety Question on Auxiliary Feedwater Sys ML20137A2111997-03-14014 March 1997 Transmits Info Pertaining to NRC Staff Review of Weld Defects in CE Designed SG Tube Sleeves ML20134Q0981997-02-21021 February 1997 Ninth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App P.App Q Documents Partially Withheld (Ref FOIA Exemption 6).Documents Also Available in PDR ML20134Q1251997-02-20020 February 1997 Forwards Original & Three Copies of Rev 10 to Knpp Security Manual.Manual Is Being Changed to Incorporate Use of Vehicle Barrier Sys,Per 10CFR73.55 & 73.1(a).Encl Withheld ML20133E7031997-01-0606 January 1997 Forwards Insp Rept 50-305/96-12 on 961118-27 & Notice of Violation ML20133G2291997-01-0606 January 1997 Ltr Contract:Task Order 115, Kewaunee Safety Sys Operational Performance Insp, Under Contract NRC-03-93-026 ML20129K1131996-11-0505 November 1996 Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key for Info.W/O Encl ML20129J2641996-10-29029 October 1996 Ack Receipt of 960613 & 1024 10CFR50.54(a) Submittals Re Changes to Quality Assurance Program Description.Based on Review,Nrc Concludes That Revision Continues to Meet Requirements of 10CFR50,App B & Acceptable ML18065B0081996-10-14014 October 1996 Informs That Overheads Will Be Presented by Licensee at 961016 Meeting at NRC Headquarters in White Flint.Encl Withheld ML20117P6861996-09-20020 September 1996 Forwards Rev 9 to Security Manual.Encl Withheld ML20117L7171996-09-0505 September 1996 Forwards Proposed Tech Specs Re Amend for Use of Westinghouse Laser Welded Steam Generator Tube Sleeves,Per Discussion W/Nrc ML20100M7451996-02-29029 February 1996 Provides Revised Description of Proposed Vehicle Control Measures.Encl Withheld ML20217H4281996-01-24024 January 1996 Discusses Review of Nuclear Energy Inst Guidance Document, Guideline for Managing NRC Commitments, Rev 2,dtd 951219 ML20094H8491995-11-0606 November 1995 Forwards Rev 8 to Security Manual.Rev Withheld ML20091P4951995-08-28028 August 1995 Forwards Clarification of Rev 7 to Security Manual.Encl Withheld ML20094D9291995-08-10010 August 1995 Forwards Scenario Package for 951011 Emergency Exercise at Plant,Per from Cj Paperiello ML20087K2451995-08-0202 August 1995 Forwards Revised Description of Proposed Vehicle Control Measures.Primary Change in Design Is Use of Jersey Barriers in Lieu of Combination Cable & Rock Design.Encl Withheld ML20084L1091995-05-30030 May 1995 Forwards Rev 7 of Kewaunee NPP Security Manual.Encl Withheld ML20080N0061995-02-28028 February 1995 Forwards Summary Description of Plant Proposed Vehicle Control Measures & Results of Vehicle Bomb Comparison.Encl Withheld ML20078R3291994-12-19019 December 1994 Discusses Results & Conclusions of Osre Conducted During 940815-18.Weakness Noted as Being Unique & Only Possible During Specific Time Periods ML20072J3401994-08-22022 August 1994 Responds to NRC Re Violations Noted in Insp Rept 50-305/94-09 on 940516-0704.Corrective Actions:Memo,Stating That Turbine Driven AFW Pump Should Be Declared Inoperable Whenever AFW-10A or 10B Closed or Inoperable,Issued ML20070P5811994-03-29029 March 1994 Requests Meeting W/Nrc & Appropriate Members of NRC Dept Re Disposal of high-level Radwaste from NPP ML20059E9511994-01-0707 January 1994 Requests Addl Info Re Graded Approach for GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20058E6581993-12-0101 December 1993 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 940209.Informs That Facility Must Submit Ltr Identifying Individuals Who Will Take Exam ML20058A1291993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide Re Proposed Rule for Protection Against Manevolent Use of Vehicles at Nuclear Power Plants.Encl Withheld ML20059D2761993-10-26026 October 1993 Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key.W/O Encl 1999-08-23
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C ML20154F1481998-10-0202 October 1998 Forwards Insp Rept 50-305/98-15 on 980831-0904.No Violations Noted.Insp Exam of Activities Conducted Under License Re Physical Security & to Compliance with Commission Rules & Regulations & with Conditions of License ML20236R9051998-07-21021 July 1998 Informs That Document Entitled, WCAP-14677,Rev 1 F* & Elevated F* Tube Alternate Repair Criteria for Tubes W/Degradation within Tubesheet Region of Kewaunee Sgs, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20249B7471998-06-23023 June 1998 Forwards RAI Re 980601 Proposed Amend to Revise F* & Ef* Criteria for SG Tubes in Kewaunee Tss.Proposed Amend Would Revise Existing F* & Ef* Distances in TS 4.2.b to Reflect Changes to Primary to Secondary Differential Pressure ML20249A8751998-06-16016 June 1998 Forwards Request for Addl Info Re Proposed Amend to Redefine Parent Tube Pressure Boundary for Westinghouse Mechanical Hybrid Expansion Joint SG Tube Sleeves,Submitted by Util ML20248M2521998-06-0909 June 1998 Forwards Assessment of Kewannee Cycle 22 Alternate Repair Criteria 90 Day Rept,For Info ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217H4031998-03-27027 March 1998 Informs That NRC Staff Has Initiated Variety of Activities Re Mgt of Licensing Basis Info as Result of Problems Encountered at Millstone & Maine Yankee Facilities ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl ML20212H0121997-11-0404 November 1997 Forwards Insp Rept 50-305/97-14 on 970915-19.No Violations Noted.Rept Identifies Areas Examined within Security Program ML20217P3511997-08-26026 August 1997 Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Proposed by NRC in . Corrective Actions Will Be Examined During Future Insp ML20140E8861997-06-0707 June 1997 Forwards Amend 133 to License DPR-43 & Safety Evaluation. Amend Establishes New Design Basic Flow Rate for AFW Pumps Consistent W/Assumptions Used in Reanalysis of Limiting Design Basis Event for AFW Sys ML20140F2171997-04-30030 April 1997 Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR IA-97-130, Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR1997-04-30030 April 1997 Final Response to FOIA Requests for Documents.Records in App B Encl & Will Be Available in PDR ML20137A2111997-03-14014 March 1997 Transmits Info Pertaining to NRC Staff Review of Weld Defects in CE Designed SG Tube Sleeves ML20134Q0981997-02-21021 February 1997 Ninth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App P.App Q Documents Partially Withheld (Ref FOIA Exemption 6).Documents Also Available in PDR ML20133G2291997-01-0606 January 1997 Ltr Contract:Task Order 115, Kewaunee Safety Sys Operational Performance Insp, Under Contract NRC-03-93-026 ML20133E7031997-01-0606 January 1997 Forwards Insp Rept 50-305/96-12 on 961118-27 & Notice of Violation ML20129K1131996-11-0505 November 1996 Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key for Info.W/O Encl ML20129J2641996-10-29029 October 1996 Ack Receipt of 960613 & 1024 10CFR50.54(a) Submittals Re Changes to Quality Assurance Program Description.Based on Review,Nrc Concludes That Revision Continues to Meet Requirements of 10CFR50,App B & Acceptable ML20217H4281996-01-24024 January 1996 Discusses Review of Nuclear Energy Inst Guidance Document, Guideline for Managing NRC Commitments, Rev 2,dtd 951219 ML20059E9511994-01-0707 January 1994 Requests Addl Info Re Graded Approach for GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance ML20058E6581993-12-0101 December 1993 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 940209.Informs That Facility Must Submit Ltr Identifying Individuals Who Will Take Exam ML20058A1291993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide Re Proposed Rule for Protection Against Manevolent Use of Vehicles at Nuclear Power Plants.Encl Withheld ML20059D2761993-10-26026 October 1993 Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key.W/O Encl ML20057E3341993-10-0101 October 1993 Forwards Enforcement Conference 50-305/93-20 on 930923 ML20149D4501993-09-10010 September 1993 Forwards Insp Rept 50-305/93-18 on 930823-31.Apparent Violation Being Considered for Escalated Enforcement Action ML20056E9641993-06-22022 June 1993 Ltr Contract,Mod 1 to Task 17,providing Incremental Funding in Listed Amount & Increasing Obligated Amount,To Individual Plant Exam Reviews,Internal Events - Back End Only ML20056E9551993-05-25025 May 1993 Ltr Contract,Awarding Task 17,to Individual Plant Exam Reviews,Internal Events-Back-End Only ML20056F1641993-04-16016 April 1993 Ltr Contract,Awarding Task Order 16, IPE Reviews - Internal Events - Front End Only (Kewaunee), to Contract NRC-04-91-066 ML20056F0691993-04-14014 April 1993 Ltr Contract NRC-04-91-069,task Order 16,to IPE Reviews, Internal Events - Human Reliability Analysis Only (Kewaunee) ML20128E3091992-12-0202 December 1992 Informs of NRC Plans to Administer Generic Fundamentals Exam Section of Written OL Exam on 930210.Forwards Ltr Utils Should Follow in Order to Register Personnel to Take Generic Fundamentals Exam IR 05000305/19900171990-11-0505 November 1990 Forwards Safety Insp Rept 50-305/90-17 on 900909-1020.No Violations Noted.Record Copy ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20056A4981990-08-0101 August 1990 Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls ML20059M8981990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20247H3721989-07-25025 July 1989 Forwards Safeguards Insp Rept 50-305/89-09 on 890620-26 & Notice of Violation.Corrective Actions for Weaknesses Re Testing of Security Power Supply Sys & Metal Detectors Requested within 30 Days.Notice Withheld (Ref 10CFR73.21) ML20248B1471989-06-0202 June 1989 Forwards Requalification Exam Rept 50-305/OL-89-02 of Exams Administered During Wk of 890501 ML20247M8271989-03-30030 March 1989 Discusses Licensee Requests for Changes to Requalification Program.Requests Include Extension of Max Time Period of 24 Months for Requalification Cycle to Account for Changes in Outage Schedules & Reorganization of Training Programs ML20205S3841988-10-13013 October 1988 Partial Response to FOIA Request for Documents.App D,E & F Records Encl & Available in Pdr.App F Records Partially Withheld (Ref FOIA Exemption 6) ML20154P6861988-09-27027 September 1988 Forwards Safeguards Insp Rept 50-305/88-17 on 880725-28 & Notice of Violation.Notice of Violation & Portion of Insp Rept Withheld (Ref 10CFR73.21) ML20154A1521988-08-17017 August 1988 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Also Available in Pdr. App B Documents Totally Withheld (Ref FOIA Exemption 5).App C Documents Partially Withheld (Ref FOIA Exemption 5) ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20155K0211988-06-13013 June 1988 Partial Response to FOIA Request for Documents.Forwards App D Documents.App C Documents Available in Pdr.App E Documents Completely Withheld (Ref FOIA Exemption 5) ML20153G4421988-05-0505 May 1988 Forwards Reactive Insp Rept 50-305/88-10 on 880404-07 & 15. No Violations Noted ML20153C3841988-05-0303 May 1988 Forwards Reactive Safeguards Insp Rept 50-305/88-04 on 880125-29 & 0202-04.No Violations Noted 1999-04-13
[Table view] |
Text
1
. .e+
June:23, 1998 Mr. MfL. Marchi -
- l. ,
Site Vice President - Kewaunee Plant ~
Wisconsin Public Service Corporation '
_ _ P.O. Box 19002. 'w
- j. Green Bay, WI 5430729002
SUBJECT:
KEWAUNEE NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL--
INFORMATION REGARDING THE REVIEW OF PROPOSED AMENDMENT REGARDING F* AND EF* CRITERIA FOR STEAM. GENERATOR TUBES (TAC .
- NO. MA1977) L
Dear MrLMarchi:
. By application dated June 1,1998, Wisconsin Public Service Corporation (WPSC) submitted for staff review a proposed amendment (PA156) to revise the F* and EF* criteria for steam generator (SG) tubes in the Kewaunee Technical Specifications (TS). The proposed amendment would revise the existing F* distance and EF* distance in TS 4.2.b to reflect the changes to the primary to secondary differential pressure due to SG tube plugging and sleeving and a minor error made in the original calculations. In order to continue its review, the staff requests that WPSC respond to the attached questions.
If you have any questions regarding this request, please contact me at (301) 415-3026.
Sincerely, Original signed by:
William O. Long, Sr. Project Manager Project Directorate lll-3 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION: ..
f
-JTsao PD3-3 Reading' PUBLIC ^
Docket File' G. Grant,' Ill g j
{;l ,j DOCUMENT NAME: G:\KEWAUNEE\F_STARP.Al OFFICE - PD33:PM E PD33:LA - E PD33:D E.
NAME WLong EBamhill 9p RBellamy P DATE. V / C/98 - b /19/98 / /98 (s /l?/98
- OFFICIAL RECORD COPY
^
40145'980Mt3 0 i
~. ,
.PDR ADOCK 05000331
$ > , N,A '
~
d_ hm_L_ _s___._ _ . . .
June 23, 1998 t Mr. M. L. Marchi Site Vice President - Kewaunee Plant Wisconsin Public Service Corporation P.O. Box 19002 Green Bay, WI 54307-9002
SUBJECT:
KEWAUNEE NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF PROPOSED AMENDMENT REGARDING F* AND EF* CRITERIA FOR STEAM GENERATOR TUBES (TAC NO. MA1977)
Dear Mr. Marchi:
By application dated June 1,1998, Wiscor.w Public Service Corporation (WPSC) submitted for staff review a proposed amendment (PA156) to revise the F* and EF* criteria for steam generator (SG) tubes in the Kewaunee Technical Specifications (TS). The proposed amendment would revise the existing F* distance and EF* distance in TS 4.2.b to reflect the changes to the primary to secondary differential pressure due to SG tube plugging and sleeving and a minor error made in the original calculations. In order to continue its review, the staff requests that WPSC respond to the attached questions.
If you have any questions regarding this request, please contact me at (301) 415-3026.
Sincerely, Original signed by:
William O. Long, Sr. Project Manager Project Directorate lil-3 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc wlencl: See next page QlSJRIBUTION:
JTsao Docket File PD3-3 Reading G. Grant,111 PUBLIC DOCUMENT NAME: G:\KEWAUNEE\F_ STAR.RAI OFFICE PD33:PM E PD33:LA E PD33:D E NAME WLong EBarnhill f'fpf RBellamy I" DATE V / C/98 6 /19 /9 8 / /98 la /l)/98 OFFICIAL RECORD COPY
pW "%,,
t UNITED STATES ff j
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 June 23, 1998 Mr. M. L. Marchi Site Vice President- Kewaunee Plant Wisconsin Public Service Corporation P.O. Box 19002 Green Bay, WI 54307-9002
SUBJECT:
KEWAUNEE NUCLEAR POWER PLANT- REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF PROPOSED AMENDMENT REGARDING F* AND EF* CRITERIA FOR STEAM GENERATOR TUBES (TAC NO. MA1977)
Dear Mr. Marchi:
By application dated June 1,1998, Wisconsin Public Service Corporation (WPSC) submitted for staff review a proposed amendment (PA156) to revise the F* and EF" criteria for steam generator (SG) tubes in the Kewaunee Technical Specifications (TS). The proposcJ amendment would revise the existing F* distance and EF* distance in TS 4.2.6 to reflect the changes to the primary to secondary differential pressure due to SG tube plugging and sleeving and a minor error made in the original calculations. In order to co:1tinue its review, the staff requests that WPSC respond to the enclosed questions.
If you have any questions regarding this request, please contact me at (301) 415-3026.
Sincerely, n
William O. Long, Sr. Project anager Project Directorate lll-3 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/ encl: See next page l
l l
\
l t M. L. Marchi Wisconsin Public Service Corporation Kewaunee Nuclear Power Plant cc:
Foley & Lardner ATTN: Bradley D. Jackson One South Pinckney Street P.O. Box 1497 ,
Madison, WI 53701-1497 i
)
l Chairman .
Town of Carlton Route 1 Kewaunee,WI 54216 l Harold Rockelberg, Chairman Kewaunee County Board ,
. Kewaunee County Courthouse j Kewaunee,WI 54216 Attomey General 114 East, State Capitol Madison,WI 53702 l
U.S. Nuclear Regulatory Commission Resident inspectors Office Route #1, Box 999 Kewaunee,WI 54216-9511 Regional Administrator- Region ill U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4531 James D. Loock, Chief Engineer Public Service Commission of Wisconsin P. O. Box 7854 Madison, WI 53707-7854 -
~
. REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED AMENDMENT ON F* AND EF* CRITERIA FOR STEAM GENERATOR TUBING AT KEWAUNEE NUCLEAR POWER PLANT DOCKET NO. 50-305 By application dated June 1,1998, Wisconsin Public Service Corporation (WPSC) submitted for staff review a proposed amendment to revise existing F* and EF* criteria for steam generator (GG) tubes in the Kewaunee technical specifications (TS). The proposed amendment would revise the existing F* distance and EF* distance in TS 4.2.b to reflect the changes to the primary to secondary differential pressure due to SG tube plugging and sleeving and a minor error made in the original calculations. in order to continue its review, the staff requests that WPSC respond to the following questions:
- 1. Discuss the differences between the original analysis and revised analysis in which the primary to secondary differential pressure was increased from 1565 psi to 1600 psi; e.g.,
what were the assumptions Prplied to the SG tubing in the revised antdysis inat were different from the original analysis?
- 2. Confirm that F* and EF* distances, including nondestructive examination (NDE) uncertainty of 0.20 inches, will be 1.31 inches and 1.71 inches, respectively. Confirm that the F* and EF* criteria will not be applied to any non-sleeved hardroll whose length is less than F* and EF* distances of 1.31 inches and 1.71 inches, respectively. Discuss the changes, if any, to the eddy current technique (e.g., probe design) to reflect the proposed changes to the distances. Discuss in detail how the NDE uncertainty of 0.20 inches was derived.
- 3. TS 4.2.b.6.b specifies that the EF* region is located a minimum of 4 inches below the top of the tubesheet. Discuss the technical basis of the 4-inch distance.
- 4. In the footnote on Page 2-1 of WCAP-14677, Revision 1, *F* and Elevated F* Tube Alternate Repair Criteria For Tubes With Degradation in The Tubesheet Region Of The Kewaunee Steam Generators," an attachment to the June 1,1998, application, it is stated that based on NDE, the factory hardrolls in the hot leg tubesheet of SG A in Kewaunee range from about zero to about 2.25 inches in axial length. It is also stated that the typical length is 1.25 inches. The staff understands that the licensee has repaired the undersized, non-sleeved, factory hardrolls by installing additional roll expansion joints directly above the factory hardrolls. However, it is not clear that the average length of the existing non-sleeved hardrolls is 1.25 inches. Provide the average length of the existing non-sleeved hardrolls. Provide the number of the non-sleeved hardrolls that have length shorter than the F* distance of 1.31 inches and assess their structural and leakage integrity.
5 On page 3 of Attachment 1 to the June 1,1998, letter, it is stated that Westinghouse corrected a minor error in the original calculation of F* and EF* distance. Discuss the error in detail: (1) Discuss whether the error affects F* and EF* criteria in existing technical i specifications in plants other than Kewaunee; (2) Discuss whether Westinghouse
4
- investigated the error under 10 Code of Federal Regulation Part 21, " Reporting of Defects and Noncompliance." (3) By removing the error, the F* distance would decrease from 1.12 inches to 1.10 inches and the EF* distance would increase from 1.44 inches to 1,49 inches. Why did the error cause an increase in one case and a decrease in another case?
- 6. Discuss whether the revised F* and EF* distances, which were calculated by theory, can be supported by the tensile test results in WCAP-14679, " Qualification of Additional Roll Expansion for the Kewaunee Nuclear Power Plant Steam Generators," which was submitted on July 3,1996, as a par 1 of license amendment 129.
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