Letter Sequence RAI |
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MONTHYEARML20148K7251997-06-16016 June 1997 Forwards RAI Re Mcguire Nuclear Station,Units 1 & 2,Grinell Hydraulic Pipe Supports That McGuire Purchased in Aug of 96 Project stage: RAI ML20198S9451997-10-30030 October 1997 Forwards RAI Re Grinnell Hydraulic Snubbers at Mcguire Nuclear Station,Units 1 & 2 Project stage: RAI ML20203L9501998-02-19019 February 1998 Summary of 980204 Meeting W/Util to Discuss Info Re Design, Operabiliy & Qualifications of Grinnell Snubbers at Plant. Meeting Scheduled to Resolve Issues Re Staff Rai.List of Participants & Handouts Provided by Util Encl Project stage: RAI ML20206L5631999-05-11011 May 1999 Forwards Two Documents Requesting That NRC Place on Docket 50-369 & 50-370,technical Interface Agreement 97-02 & Related Staff Evaluation Project stage: Other 1997-06-16
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20206L5631999-05-11011 May 1999 Forwards Two Documents Requesting That NRC Place on Docket 50-369 & 50-370,technical Interface Agreement 97-02 & Related Staff Evaluation ML20206N3451999-05-11011 May 1999 Forwards SE of Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206M2121999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created ML20206C0451999-04-23023 April 1999 Forwards Insp Repts 50-369/99-02 & 50-370/99-02 on 990214-0327.No Violations Noted ML20205Q6641999-04-15015 April 1999 Forwards Amend 10 to Indemnity Agreement B-83 for Signature & Return to Document Control Desk ML20205M6741999-04-13013 April 1999 Discusses 980318 Telcon of Licensing Bases Record Change Re Duke Energy Corp License Amend Request, & Staff Approval in Form of TS Amends 184 & 166,dtd 980930.Forwards Revised Pp to SE of 980930 ML20205T1711999-04-0909 April 1999 Informs That on 990317 Ho Christensen & a Orton Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates for Wks of 000508 & 22 for Approx 13 Candidates ML20205M2601999-03-25025 March 1999 Informs That NRC Completed PPR of Plant on 990201.Plant Issues Matrix & Insp Plan for Next 8 Months Encl ML20205A9371999-03-24024 March 1999 Forwards Evaluated & Final Rept from Ferc,Related to 981014 Dam Safety Audit Conducted at McGuire Nuclear Station for Category I Standby Service Water Pond Dam.List of Actions That Should Be Taken by Util to Ensure Safety of Dam,Encl ML20205H9201999-03-18018 March 1999 Forwards Exam Repts 50-369/99-301 & 50-370/99-301 on 990125- 0205.Of Eleven SRO & RO Candidates Taking Written Exam & Operating Tests,Nine Passed & Two Failed,Representing 82% Pass Rate ML20204E3221999-03-10010 March 1999 Forwards Insp Repts 50-369/99-01 & 50-370/99-01 on 990103- 0213.Non-cited Violation Noted ML20207M9091999-03-0505 March 1999 Informs That Info Submitted by Application, Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20203J0431999-02-16016 February 1999 Discusses Review of Plant,Units 1 & 2 IPEEE Submittal.Staff Concludes That Util IPEEE Process,Capable of Identifying Most Likely Severe Accidents & Severe Accidents Vulnerabilities.Intent of Suppl 4 to GL 88-20 Met ML20203C2411999-02-0505 February 1999 Discusses Draft Operation Insp Rept for McGuire Nuclear Station Standby Nuclear Service Water Pond Dam Conducted on 981028.Draft Rept States That Dam Appeared to Be in Good Condition & Adequately Maintained ML20203G3361999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Names of Candidates for Exam ML20202E3861999-01-28028 January 1999 Refers to GL 96-05 Issued on 960918 & DPC 980331 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verfication at Mcguire.Rai Re JOG Program McGuire Encl ML20199L4421999-01-25025 January 1999 Informs That by Encl Ltrs & 981223,NRC Has Responded to WOG Positions Re C/As to Address Generic Aspects of part-length CRD Mechanism Housing Issue That Originated as Result of 980123 Leak at Pings ML20203A4171999-01-22022 January 1999 Refers to 990119 Meeting Conducted in Region II Ofc for Presentation of self-assessment of McGuire Nuclear Station Performance & Future Plant Initiatives.List of Attendees & Presentation Handouts Encl ML20198Q7711999-01-0505 January 1999 Informs That Staff Review of GL 97-05, SG Tube Insp Technique, Did Not Identify Any Concerns with SG Tube Insp Techniques Employed at McGuire That Would Indicate That Util Not in Compliance with Current Licensing Bases for Plant ML20198Q7551999-01-0505 January 1999 Forwards RAI Re 980722 Request for Amend to Plant,Units 1 & 2 TSs to Permit Use of Westinghouse Fuel.Response Requested on or Before 990131 ML20199F6031998-12-23023 December 1998 Submits Summary of 981105 Training Managers Conference.List of Attendees & Matl Used in Presentation Enclosed ML20198N8771998-12-18018 December 1998 Forwards Insp Repts 50-369/98-10 & 50-370/98-10 on 981004- 1121.No Violations Noted ML20198N7001998-12-14014 December 1998 Confirms 981210 Conversation Between M Cash & E Lea Concerning Meeting Scheduled for 990119.Purpose of Meeting to Present self-assessment of Plant Performance ML20198A4221998-12-11011 December 1998 Forwards SE Accepting Licensee 980115 Request for Relief from Requirements of ASME BPV Code,Section Xi,Table IWB-2500-1,for Plant ML20196F2901998-11-23023 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plan for Next Four Months & Historical Listing of Plant Issues Called PIM Encl ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20195J5401998-11-19019 November 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations. Staff Requests Response to RAI by 990205 ML20196C7681998-11-13013 November 1998 Forwards Copy of Answer Key & Master Bwr/Pwr GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl 1999-09-23
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( October 30, 1997 Mr. H. B. Barron Vice President - McGuire Site i Duke Energy Corporation 12700 Hagers Ferry Road Huntersville, North Carolina 28078
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, GRINNELL HYDRAULIC (
SNUBBERS (TAC NOS. M97753 AND M97754)
Dear Mr. Barroi :
The NRC staf' has reviewed your response of August 28,1997, to the staffs previous request for additional inform 0 tion (RAl) of June 16,1997, pertaining to the Grinnell hydraulic snubbers at McGuire Nuclear Station, Units 1 and 2. The staff dete mined that the enclosed RAI is necded in order to complete its review of this lasue.
Sincerely, ORIGINAL SIGNED BY:
Victor Narses, Senior Project Manager Project Directorate ll-2 Divisicn of Reactor Projects - t/II C F ;e of Nuclear Reactor Regulation Docket Noe 50-369 and 50-?70
Enclosure:
As stated DISTRIBUTION YCLi LDeeket9lWA OGC cc wiencl: See next page PUBLIC ACRS P0ll-2 Reading JJohnson,Ril BBoger COgle,Ril HBerkow VNerses DOCUMENT NAME: G:\MCGUIRE', SNUBBER.RAI To receive a copy of this document, indicate in the box C= Copy w/o tidachment/onclosure E= Copy with attachment! enclosure N = No copy ' _
oFHCE Pp3 2(IPM E PDil-2/LA n h E PDt_t@f5 E NAME E h LBERRY H NR h DATE /p /A f)/97 h/ hD/97 [jf 3 : /97 OFFICIAL RECORD COPY IT i
dsi;U .f. in.C
- 1. fyIM7*%Q (SOOTF u,.a e rm j n ze y 9711140175 971030 . ,
DR a
l soo no;p p \ UNITED STATES s* NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30eeHooi
% ,,, g October 30, 1997 Mr. H. B. Barron Vice rresideat - McGuire Site Duke Energy Copration 12700 Hagers Ferry Road Huntersville, North Carolina 28078
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, GRINNELL HYDRAULIC SNUBBERS (TAC NOS. M97753 AND M97754)
Dear Mr. Barron:
The NRC staff has reviewed your response of August 28,1997, to the staff's previous request for additional inforrnation (RAI) of June 16,1997, pertaining to the Grinnell hydraulic snubbers at McGuire Nuclear Station, Unie l and 2. The staff determined that the enclosed RAI is needed in order to complete itn rev:s ; c' this issue.
S b a rely, h<j Victor Nerses, Senior Project Manager Project Directorate ll-2 Division of Reactor Projects - 1/li Offico of Nuclear Reactor Regulation Docket Nos: 50-369 and 50-370
Enclosure:
As stated cc w/ encl: See next page IL
McGuire Nuclear Station i
cc:
Mr. Paul R. Newton = Ms. Karen E. Long
- Legal Departme' ' (PB05E) Assistant Attorney General Duke Energy Cnporation North Carolina Department of 422 South Church Street Justice Charlotte, North Carolina 28242 P. O. Box 629 Raleigh, North Carolina 27602 County Manager of Mecklenburg County Mr. G. A. Copp 720 East Fourth Street Licensing - EC050 Charlotte, North Carolina 28202 Duke Energy Corporation !-
526 South Church Street Michael T. Cash Charlotte, North Carolina 28242 Regulatory Compliance Manager Duke Energy Corporation Regional Administrator, Region ll McGuire Nucicar Site _
ll.S. Nuclear Regulatory Commission 12700 Hagsrs Ferry Road Atlanta Federal Center Huntersville, North C.rolina 28078 61 Forayth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 J. Michael McGarry, Ill, Esquire Winston and Strawn Elaine Wathen, Lead REP Planner 1400 L Street, NW. Division of Emergency Management Washington, DC 20005 116 West Jones Street Raleigh, North Carolina 27603-1335 Senior Resident inspector clo U.S. Muclear Regulatory Mr. Richard M. Fry, Director Commi%0n Division of Radiation Protection 12700 Hagers Ferry Road North Carolina Department of Huntersville, North Carolina 28078 Environment Health and Natural Resources Mr. Peter R. Harden, IV 3825 Barrett Drive Account Sales Manager Raleigh, North Carolina 27609-7721 Westinghouse Electric Corporation Power Systems Field Sales Mr. T. Richard Puryear P, O. Box 7288 Owners Group (NCEMC)
Charlotte, North Carolina 28241 Duke Energy Corporation 4800 Concord Road Dr. John M. Barry York, South Carolina 29745 Mecklenberg County Department of Environmental ]
Protection p 700 N. Tryon Street .
Charlotte. Nodh Carolina 28202
I REQUEST FOP, ADDITIONAL INFORMATION MCGUlRE GRINNELL SNUBBER ,
1, in its letter dated August 28,1997, to the Nuclear Regulatory Commission (NRC), the licensee stated that "The[Grinnell) snubbers are completely mechanical in nature and
- contain no electro-mechanical components," and, "The review of the regulatory d: *nts and the current license basis reveals that completely mechanical equipment doe 1, i have specific regulatory required methods of demonstrating qualification to environmental conditions."
It should be noted that the NRC does include the environmental qualification of mechanical equipment under General Design Criterion 4, " Environmental and Dynamic Effects Design Bases," which states, in part, that " Structures, systems, and componen% important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents," Therefore, the staff requests that you provide the technicaljustification for how all of the safety-related snubbers at McGuire comply with General Design Criterion 4.
- 2. In its letter dated August 28,1997, to the NRC, the licensee stated that, 'Further irview by Duke Energy and Grinnell have not verified whether or not original temperature qualification testing was performed for the snubbers. Grinnell has not stated conclusively whether or not such testing was performed, but has not produced records of past testing."
Chapter 10 to the Code of Federal Reaulations (CFR) Part 50, Appendix B, Criterion
- XVil, " Quality Assurance Records," states, in part, that, " Sufficient records shall be maintained to fumish evidence of activities affecting quality. The records shall also include closely-related data such as qualifications of equipment. Records shall be identifiable and retrievable." Therefore, how do all of the safety-related snubbers at McGuire comply with 10 CFR Part 50, Appendix B, Criterion XVil?
- 3. It is the staffs understanding that there are approximately 150 Grinnell snubbers that .
were purchased in August 1996 and installed for the Steam Generator (SG)
Replacement Project that did not meet the purchase specifications for environmental conditions. Specifically, the specifications for temperature (350 degrees F) and radiation (2 x 10E8 rads) were not met.
How do the remaining safety-related snubbers (inside containment) that are currently insta!!ed at McGuire differ from those that were installed for the SG Replacement Project? What are the temperature limits and radiation limits on the purchase specifications for the remaining installed safety rstated snubbers? Do these remaining snubbers meet their purchsse specifications? Are there any qualifying data to demonstrate the environmental qualifications (EQ) for the remaining snubbers? Do the as-installed specific ttions for the remaining safety-related snubbers differ from the design basis documents? If so, was a 10 CFR 50.59, " Changes, Tests, and Experiments," performed to justify the change to the design basis? Moreover, do the Enclosure
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2 EQ requirements for the snubbers purchased in 1996 differ from the requirements used j for those remaining saubbers inside containment? If yes, provide the basis to justify why different EQ requirements are used?.
- 4. As discussed in Question 2 of the staffs RAI dated June 16,1997, in its assessment of the snubbers operability during a postulated main steamline break (MSLB) event. the licensee relies upon a time lag between the peak dynamic load due to pipe rupture and -
o the peak containment temperature transient for the double-ended steam lir.e break such that the temperature peaks after the pipe rupture dynamic load is over. Howaver, Figure 6 24 of the McGuire Final Safety Analysis Report shows that for a 1.4 ft8 double-ended MSLB, the temperature in the lower compartment peaks at 315 dogmes F immediately after the postulated MSLB and eventually drops and steadies at about 250 degrees F indefinitely. It is not clear how the licensee justifies the time lag between the peak pipe rupture dynamic load transient and the peak temperature transient. The licensee is requesied to provide's detailed comparison of these two trans'ents and to assess the snubber's operability accordingly.
- 5. The licensee's letter dated August 28,1997, indicated that the two snubbers that were recently tested were manufactured in 1W8 by Grinnell. However, as noted in Question 3 of this RAI, those Grinnell snubbers that did not meet the McGuire purchase specifications were purchased in August 1996. It does not appear that the tested snubbera were from the population that did not meet the purchase specifications.
The licensee is requested to provide an explanation of testing the 1978 anubbers in lieu of tne affected snubbers that were purchased in August 19967
- 6. Explain in detail how the test conditions as described in Section 3 of the Grinnell's test report (attachment 2 of the licensee's August 28,1997, latter) simulate the postulated MSLB accident conditions for McGuire. The explanation should include the length of time that the snubber is required to operate for the dynamic load transient and for the associated containment temperature transient.
- 7. li is noted in a letter dated August 23,1996, that Grinnell informed the licensee that for the snubbers purchased in 1996, it has no qualifying data to subelantiate the environmental conditions lishd in the licensee's specifications. It also stated thd the s reservoir material will exponence significant distortion at temperatures above 250 degrees F, and it will not maintain a proper seal. However, in its August 28,1997 letter, the licensee stated that the vendor assured the licensee that the snubbers are designed by acceptable engineering methods to be compatible with post accident environmental conditions. The licensee further stated that it concurs with the vendor. Based on the vendor's statement in its letter to the licensee dated August 23,1996, and the review of the information provided to the staff by the licensee, the staff determined that the licensee has not provided adequate technical basis to justify the above conclusion statements as stated in its Augus; 28,1997, letter. The licensee is requested to provide further details to justify the above conclusion statements.
Furthermore, it is noted that Section 6, Test Results, of Grinnell's report stated that no restriction of motion was encountered with either snubber. It is also noted that during
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this recent snubber ts st, the snubbers were heated up to 350 degrees F for 10 minutes.
However, as discussed in the above paragraph, Grinnell has previously stated that the snubbers will experience severe distortion and fluid leakage for temperatures above 250 degrees F. Were any leaks noted during this recent snubber testing? The licensee is requested to provide more details of the test results. The details should include the -
results of the visual examination of the snubbers after the tests and the identification of observed damage (e.g., seal leakage, reservoir distortion, etc.).
Finally, based on Grinnelfs statements in the August 23,1996, letter and observed snubber damage during testing, the licensee is requested to explain the basis for concluding that the observed damage would not affect the snubber's functionality of restraining piping movements during a seismic event and to discuss the cons:squential effect on the operability of the affected safety related systems.
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