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MONTHYEARML20249A8751998-06-16016 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 Project stage: RAI 1998-06-16
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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
- .
p ,~ w .-
(
June 16; 1998
'Mr. M. L. Marchi -
Site Vice President - Kewaunee Plant .
l.- Wisconsin Public Service Corporation ~
l
- P.O. Box 19002 l; Green Ba'y; WI 54307-9002 -
SUBJECT:
KEWAUNEE - REQUEST FOR ADDITIONAL INFORMATION REGARDING -
THE REVIEW OF PROPOSED AMENDMENT REGARDING STEAM l /
~ GENERATOR SLEEVED TUBES - (TAC NO. MA1762)
By a letter dated May 14,1998, Wisconsin Public Seivice Corporation.(WPSC) submitted for staff review a proposed amendment (PA155) to redefine the parent tube pressure boundary for Westinghouse mechanical hybrid expansion joint (HEJ) steam generator (SG) tube sleeves.
- The amendment would allow HEJ sleeved tubes having parent tube indications (PTis) to remain ,
in service if PTis exist outside of a specified distance from the bottom of the upper transition f region of the sleeve hardroll joint, in order to continue its review, the staff requests that WPSC-
< respond to the. enclosed questions.
If you have any questions regarding this matter, please contact me at (301) 415-3026.
Sincerely, Original signed by:
l William O. Long, Sr. Project Manager Project Directorate ill-3 Division of React _or Projects lil/lV Office of Nuclear Reactor Regulation
- Docket No. 50-331 -
Enclosure:
As stated
! cc w/ encl: See next page DISTRIBUTION:
Docket File
,/, O
)
PUBLIC PD3-3 Reading '
G. Grant,:lil - .
DOCUMENT NAME: G:\KEWAUNEE\L_ CRIT.RAI OFFICE , PD33:PM E PD33:LA' E PD33:D E NAME-- WLong # - EBarnhill @f < ,
RBellamy bW\
DATE #/y/98 b W/98 ' / - /98 - b /lQ98
- O,FFICIAL RECORD COPY-- - $
7 - , . ,.
- P , .
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r 8 s
,. June 16, 1998
- ' Mr. M. L. Marchl Site Vice President - Kewaunee Plant Wisconsin Public Service Corporation
= P.O. Box 19002 -
Green Bay, WI 54307-9002
SUBJECT:
KEWAUNEE - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF PROPOSED AMENDMENT REGARDING STEAM GENERATOR SLEEVED TUBES '(TAC NO. MA1762) -
By a letter dated May 14,1998, Wisconsin Public Service Corporation.(WPSC) submitted for staff review a proposed amendment (PA155) to redefine the parent tube pressure boundary for Westinghouse mechanical hybrid expansion joint (HEJ) steam generator (SG) tube sleeves.
The amendment would allow HEJ sleeved tubes having parent tube indications (PTis) to remain in service if PTis exist outside of a specified distance from the bottom of the upper transition region of the sleeve hardrolijoint. In order to continue its review, the staff requests that WPSC respond to the enclosed questions.
If you have any questions regarding this matter, please contact me at (301) 415-3026.
Sincerely, Original signed by:
William O. Long, Sr. Project Manager Project Directorate ill-3 _j Division of Reactoc Pro'ects Ill/IV Office of Nuclear Reactor 'Reguiation Docket No. 50-331
Enclosure:
As stated
. cc w/ encl: See next page
- DISTRIBUTION:
Docket File PUBLIC -
PD3-3 Reading G. Grant, Ill DOCUMENT NAME: G:\KEWAUNEE\L_ CRIT.RAI OFFICE PD33:PM E PD331A E PD33:D E NAME- WLong F EBamhilliff RBellamy bW\
DATE A/ A//98 6 g/98 / /98 b /l Q98-OFFICIAL RECORD COPY
_ _ _ _ _ - . __- -_- _ O
e any p 1* UNITED STATES s* NUCLEAR REGULATORY COMMISSION
, WASHINGTON, D.C. 3008H001 1
l June 16, 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 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REVIEW OF PROPOSED AMENDMENT REGARDING STEAM GENERATOR SLEEVED TUBES (TAC NO. MA1762)
By a letter dated May 14,1998, Wisconsin Public Service Corporation (WPSC) submitted for staff review a proposed amendment (PA155) to redefine the parent tube pressure boundary for l Westinghouse mechanical hybrid expansion joint (HEJ) steam generator (SG) tube sleeves.
The amendment would allow HEJ sleeved tubes having parent tube indications (PTis) to remain in service if PTis exist outside of a specified distance from the bottom of the upper transition region of the sleeve hardroll joint. In order to continue its review, the staff requests that WPSC respond to the enclosed questions.
If you have any questions regarding this matter, please contact me at (301) 415-3026.
Sincerely, i
i William O. Long, Sr. Project Manager Project Directorate lil-3 Division of Reactor Projects Ill/IV )
Office of Naclear Reactor Regulation Docket No. 50-331
Enclosure:
As stated cc w/ encl: See next page
, M. L Marchl 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 Chairman Town of Carlton Route 1 Kewaunee,WI 54216 .
Harold Reckelberg, Chairman Kewaunee County Board Kewaunee County Courthouse Kewaunee, WI 54216 Attomey General 114 East, State Capitol Madison,WI 53702 U.S. Nuclear Regulatory Commission
~ Resident inspectors Office Route #1, Box 999 Kewaunee, WI 54216-9511 Regional Administrator - Region lil 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 HYBRID EXPANSION JOINT SLEEVED TUBES IN STEAM GENERATORS AT KEWAUNEE NUCLEAR POWER PLANT DOCKET NO. 50-305 By a letter dated May 14,1998, the Wisconsin Public Service Corporation (WPSC) submitted for staff review a proposed amendment to redefine the parent tube pressure boundary for Westinghouse mechanical hybrid expansion joint (HEJ) steam generator (SG) tube sleeves.
The amendment would allow HEJ sleeved tubes having parent tube indications (PTis) to remain in service if PTis exist outside of a specified distance from the bottom of the upper transition region of the sleeve hardrolljoint. In order to continue its review, the staff requests that WPSC respond to the following questions.
Questions related to WCAP-15050. "HEJ Sleeved Tube Lenath-based Degradation Acceptance Criterion." an attachment to the May 14.1998. aoolication:
- 1. On page 3, there is a discussion of tensile tests on HEJ sleeve specimens as a part of previous license amendments (References 1 and 2). Clarify whether the specimens used in those tensile tests are applicable to the HEJ sleeve configuration in the proposed amendment. Provide statistical results of those tensile tests (e.g., the mean, standard deviation).
- 2. Table 4 indicates a calculated mean failure pressure of 7051 psi with a standard deviation of 2206 psi. Under steam line break conditions, the mean is 9673 psi with a standard deviation of 2721 psi. Discuss causes, especially structural, that could have contributed
, to such a large uncertainty.
- 3. Although the mean failure pressure is above the Regulatory Guide (RG) 1.121 allowable value of 4800 psi (i.e., acceptable), the failure pressure at the 95th percentile and 90%/90% tolerance is below the allowable at 4054 psi and 4062 psi, respectively. Also, the calculated probability is 0.091 that the failure pressure would be below the allowable value. Considering that there are about 1500 HEJ sleeved tubes with PTis, the failure pressure of about 136 tubes (1500 x 0.091) would be below the allowable. Discuss the potential impact of failure probabilities calculated in Table 4 on the structural integrity of the HEJ sleeved tubes. .
- 4. On Page 20, there is a discussion of leak rate experience and information on leakage
- measurement based on Argon 41 and tritium. Describe, in detail, the monitoring system for primary-to-secondary leakage, including administrative controls, if any, on leakage limits in the plant operating procedures. Does the leakage monitoring system satisfy the guidance in the EPRI report, "PWR Primary-to-Secondary Leak Guidelines," TR-1047887 L
a Questions related to Attachment 5. *NDE Techniaue to Determine Lenath Measurements in HEJ Sleeved Tubes With Parent Tube Indications." to the May 14.1998. submittal.
- 5. Describe, in detail, the quality control that the manufacturer will use to qualify combination probes proposed for the inspection; Specifically (1) Will every probe used in the field be tested for acceptance in the manufacturing facility prior to shipment? If not, discuss the possibility of unqualified and unacceptable probes being used in the inspection, (2)
Discuss acceptance criteria and the testing method to qualify the probes; specifically, will probes be tested at one frequency or mixed frequencies? What length and associated l tolerance will be specified for the distance between the + Point coil and bobbin coil? Will the probes be qualified at the plant site prior to tube inspection? How will probe variability be controlled and monitored? (3) How many probes will be manufactured and how many probes will be used for the Length criterion application?
- 6. Describe how analysts will be qualified for the HEJ sleeve inspection; Specifically, (1)
Discuss the qualification criteria for the analysts, (2) Will the analyst qualification aM field analysis protocol satisfy EPRI guidelines? (3) How will the analyst variability be monitored and controlled in the field? (4) Describe the test samples used in analyst qualification tests, (5) Discuss WPSC's involvement in the qualification of the analysts.
- 7. Page 3 provides a discussion of the analyst variability test in detecting the center of the
+ Point coil signal response. It is stated that the variability between analysts in reporting flaw locations corresponds to 0.008 inches to 0.018 inches in axial elevation and that 0.018 inches will be used as the analyst variability in calculating the total NDE uncertainty.
(1) What is the mean and standard deviation of the analyst variability from the test, and (2) is the analyst variability of 0.018 inches comparable to that of the industry in similar inspections?
- 8. On Page 4, it is stated that a computer algorithm will be used to determine a lower tangent point of the hardroll upper transition (HRUT) region. Discuss the accuracy and applicability of the computer algorithm with respect to the actual sleeve-parent tube conditions.
- 9. It is not clear to the staff how the parent tube indication (PTI) is defined in the inspection.
In the proposed Bases section, page TS B4.2-4, it is stated that 'the pressure boundary...will allow PTis located in the upper joint to remain in service if there is a minimum non-degraded (i.e., no detectable degradation in the parent tube) hardroll length...." Discuss the procedures that will be used in characterizing and dispositioning indications, e.g., which coil will be used to determine no-detectable degradation (NDD)?
Will the non-quantifiable indication (NQl) be dispositioned as a PTl? Discuss whether the probe would be used to size flaw depth in sleeves because TS 4.2.b.4.b specifies that sleeve indications greater than 24% through wall will be plugged or repaired.
- 10. In NRC Inspection Report 50-305/96011 (DRS), date February 20,1997, and 50-305/97008 (DRS) dated July 16,1997, the NRC inspector identified, during SG inspection in Kewaunee, that PTis having large voltage responses masked signal d
responses from the sleeve such that potential sleeve flaws may not be detected.
Subsequent to the NRC inspector's findings, WPSC used a high frequency 0.080 inch rotating pancake coil to perform sample inspection of HEJ sleeves. No indication of degradation was identified in the sleeves. In light of the NRC findings, discuss the capability of the proposed eddy current technology (ET); specifically, whether ET can distinguish a sleeve indication and PTl that are located at the same elevation across all ranges of voltage responses.
References:
- 1. WCAP-14157, " Technical Evaluation of Hybrid Expansion Joint (HEJ) Sleeved Tubes with Indications Within the Upper Joint Zone," August 1994.
- 2. WCAP-14157, Addendum 1, " Supplemental Leak and Tensile Test Results for Degraded HEJ Sleeved Tubes in Model 44/51 S/G's," September 1994.
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