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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:INCOMING CORRESPONDENCE
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 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 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station 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 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 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 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 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 ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 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 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 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 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 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 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 ML20206S9151999-05-11011 May 1999 Forwards Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. Section 16.11-16.2 Has Been Revised to Apply Guidance of NUREG-0133 for Performing Gaseous Effluent Dose Pathway Calculations ML20206K1341999-05-0303 May 1999 Forwards 1999 Interim UFSAR for McGuire Nuclear Station. UFSAR Update Includes Items Relocated During Improved Tech Specs Implementation.Next Regular UFSAR Update as Required 10CFR50.71(e) Is Due in Oct 1999 ML20206F3321999-04-28028 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for McGuire Nuclear Station. Listed Attachments Are Contents of Rept.Revised ODCM Was Submitted to NRC on 990203 ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20206B4791999-04-20020 April 1999 Requests Exemption from GDC 57 Re Reactor Containment - Closed Sys Isolation Valves,As Described in 10CFR,App a for Containment Penetrations M393 & M261.Detailed Technical Evaluation & Justification for Exemption Request,Encl ML20205S9731999-04-19019 April 1999 Submits Info Re Quantity of SG Tubes Inspected,Tube Indications of Imperfections & Tubes Removed from Svc by Plugging,Per TS 5.6.8,part B 05000369/LER-1999-001, Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence1999-04-16016 April 1999 Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence ML20205P8891999-04-13013 April 1999 Forwards Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Feb 1999 Encl ML20206K3561999-04-13013 April 1999 Forwards Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual. Significant Changes Are Marked by Vertical Bars on Right Margin ML20205K5131999-04-0707 April 1999 Forwards Complete Response to NRC 981209 & 990105 RAIs on Question 11 Re LARs for McGuire & Catawba Nuclear Stations. Addl Info Received from W & Contained in Encl W ML20205B6011999-03-23023 March 1999 Requests That NRC Place Technical Interface Agreement 97-02 Re URI 96-11-03,raising Operability & Design Criteria Conformance Issues Re Hydraulic Snubbers Installed at Plant & NRR Response on Dockets to Provide Record of Issue ML20205C4611999-03-23023 March 1999 Submits Correction to Violation Against 10CFR50 App B, Criterion VII, Control of Purchased Matl,Equipment & Svcs, Issued to McGuire Nuclear Station on 980807 ML20205B6161999-03-23023 March 1999 Provides Addl Info & Correction to Typo in Re License Bases Record Change Re License Amend Submittals ,approved as FOL NPF-9 & NPF-17,amends 184 & 166, respectively.Marked-up TS Pages,Encl ML20204J0051999-03-19019 March 1999 Forwards Response to 990127 & 28 RAIs Re GL 96-05 for Catawba & McGuire Nuclear Stations ML20204E1791999-03-18018 March 1999 Reflects 990318 Telcon Re License Bases Record Change for License Amend Submittals ,approved as Amends 184 & 166,respectively for Licenses NPF-9 & NPF-17.TS Pages Encl ML20204C8821999-03-15015 March 1999 Forwards Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Jan 1999 Encl ML20207C2071999-02-25025 February 1999 Informs of Revised Expected Submittal Date of Proposed License Amend Presented at 990127 Meeting Re Soluble Boron & Boraflex.Util Plans to Submit Proposed License Amend in First Quarter of 1999 ML20207C7691999-02-22022 February 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998. Rept Provides Tabulation of Number of Station,Utility & Other Personnel Receiving Exposure Greater than 100mRem/yr Followed by Total Dose for Each Respective Worker ML20207C6851999-02-22022 February 1999 Forwards Revised TS Bases Pages,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20206S3341999-01-28028 January 1999 Forwards Proprietary & non-proprietary Responses to NRC 981209 & 990105 RAIs Re Util Lars,Permitting Use of W Fuel at McGuire & Catawba Stations.Proprietary Info Withheld,Per 10CFR2.790 ML20199E0081999-01-12012 January 1999 Forwards MOR for Dec 1998 & Revised MOR for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199C9861999-01-0707 January 1999 Forwards Annual Lake Norman Environ Summary Rept for 1997,as Required by NPDES Permit NC0024392,including Detailed Results & Data Comparable to That of Previous Years.With Corrected Pages 3 & 19 to 1994-95 Lake Norman Creel Rept 1999-09-09
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Duke 1% er O>mpany T C McMWn M:Gwn Nudear Generahon inanment Vtce hevdent I}iU9 Hagm Terry Rwd (MGOI\T) (IN ?754800 lluntenns, hC 2WSXh5 (704$754%9 Fat DUKE POWER June 24, 1994 Document Control Desk U.S. Nuclear Regulatory Commission Wachington, D.C. 20555
Subject:
McGuire Nuclear Station McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 50-370 Section XI, Inservice Inspection Second Interval, Unito 1 and 2 Rollef Request,94-005 g Dear Sirl Pursuant to Ju CFR50.55a (g) (5) (iii), I am cubmitting the attached relief requev .for NRC review and approval. This request for relief from ASME Code requirements involves both the 1986 (Unit 1) and 1989 (Unit 2) Edition of Section XI, IWA5242, Insulated Components snd IWA-5250, Corrective Measures. The bolted connections under consideration include pipe flange to pipe flange joints as well as other component configurations such as valve bonnet to body connections. Attachment 1 discusses INA-5242 and the proposed Alternate Method while Attachment 2 addresses IWA-5250 requirements.
Should there be any questions regarding this matter, please contact John M. Wacham at (704) 875-4181.
Very truly yours, t r/ ,, g -
T. C. McMeekin _
w' 9407060192 940624 PDR ADOCK 05000369 D PDR l
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U.S. Nuclear Regulatory Commission June 24 1994 page 2 xc: Mr. S.J. Ebneter Admin'.strator, Region II U.S. ~1uclear Regulatory Commission 101 Parietta St., NW, Suite 2900 Atlanta, Ga. 30323 Mr. Victor Nernes U.S. Nuclear Regulatory Commission office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. George .4axwell Senior NRC Resident Inspector, McGuire McGuire Nuclear Station l
DUKE POWER COMPANY Request for Relief From Inservice Inspection Requirement ATTACHMENT 1 Stationt McGuire Nuclear Station Unit 1 and 2 Reference Code (s): 1986 Edition of Section XI for Unit 1 1989 Edition of Section XI for Unit 2
- 1. Component for which exemption is requested:
A. 5.me and Identification Number:
Insulated bolted connections in ASME Class 1, 2, and 3 Systems borated for reactivity control within the scope of a system pressure test. Bolted connections include pipe flange to pipe flange joints as well as other component connections such as valve bonnet to valve body.
B. Function:
These bolted connections provide a pressure boundary function for ASME Class 1, 2, and 3 systems.
C. ASME Section XI Code Case:
None D. Construction Code and Class (If Applicable):
ASME Section III, Class 1, 2 and 3 E. Valve Category (If Applicable):
Not applicable F. Attachments (list) or
References:
None II. Reference Code Requirement from which relief in desired:
ASME Boiler and Pressure Vessel Code,Section VI, 1986 and 1989 Editions, Article IWA-5242.
l III. Basis for Hoquesting Relief The ASME Boiler and Pressure Vessel Code,Section XI, 1986 and 1989 Edition, Article IWA-5242, Insulated Components states in part:
"(a) For systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2. For other componenta, visual examination VT-2 may be conducted without the removal of insulation by examining the accessible and exposed surfacas and joints of the insulation...."
The purpose of this requirement is to verify that no unacceptable pressure boundary degradation has occurred to the bolting connection covered by the insulation. '
This relief is requested as a result of the development of an alternative inspection methodology which is equivalent in determining condition of the bolted connection while increasing the safety of station personnel.
The burden imposed by IWA-5242 (a) that will be relieved by this request is as follows:
Current ASME XI requirements involving inspection of bolted connections increase the probability of personnel burn accidents. Susceptibility to the increased risk results from rising containment temperature as a result of the removal of the insulation for inspecticn of ASME Class i bolted connections at high system pressure and temperature.
Containment temperatures rise as a result of the removal of the insulation and could affect the integrity of the Ice Condenser by sublimation of a portion of the ice. This mandates that the insulation remain in place until just prior to the VT-2, thus placing plant personnel in a rigorous environment with the relatively high potential for burn accidents.
n ._. - . .~ .- _ ___ ~ .. . ..
IV. Alternatu Examinat ion :
'lhe proposed alte> native methodology will meet the intent of the IWA-5242 requirement while avoiding or limiting the imposed burden as stated above. The Alternative Examination will be applied at the discretion of station personnel for each ppecific bolted conaection.
(1) All bolted connections within the scope of the planned system pressure testing will be identified.
(2) The identified connections will be compared with the bolted connections scbeduled for disassembly during the subject outage.
(3) The bolted connections which are not scheduled for disassembly 6; ring the outage will have the insulation removed and will be inspected for borated water leakage.
residue. The inspection rea tits and date of inspection for i the specific connection will be documented in the station work management system.
(4) If a connection is found to be a source cf leakage, the ccnnection will be disassembled and the bolting inspected during the subject outage.
(5) The insulation will be replaced on al'. bolted connections.
(6) System pressure testing aunc 1-t u with the outage will be coaducted as norms'ly caneduled. The insulated bolted connections on be. rated systems will treated as "other componorts" as apecified in IWA-5242 (a).
This proposed Alternative Examination procedure will provide an acceptable level of quality and safety. As per code, the insulation is removed from borated systems because the Owner has no evidence of the condition of bolted connection. . With the 3 Alternative Examination procedure, station personnel can document the bolting is without visually detectable degradation prior to Mode 3 (operating pressure and temperature with-a suberitical core) Unit restart. Therefore the r&toval of the insulation will not be required prior to pressure testing since the owner knows the condition.of the insulated bolted connection 1.
By implementing the proposed Alternative Examination procedure, there is a signifiaant d- :- se in the risk associated with burn injuries to station personnel, but no decrease in the quality of Nuclear Safety.
V. Implomontation Schedule The proposed Alternative Examination, if found acceptabj e, will be implemented during refueling outage End of Cycle (EOC) 9 for Units 1 and 2.
l I
1
DUKE POWER COMPANY Request for Relief From Inservice Inspection Requiremont ATTACHMENT 2 Station: McGuire Nuclear Statior Un i t. : 1 and 2 Reference Code (s): 1986 Edition of Section XI for Unit 1 1989 Edition of Section XI for Unit 2
- 1. Component for which exemption is requested:
A. Name and Identification Number:
Bolted connections in ASME Class 1, 2, and 3 Systems within the scope of a system pressure test. Bolted connections include pipe flange to pipe flange joints as well as other component connections such as valve bonnet to valve body.
B. Function:
I These bolted connections provide a pressure bounder function for ASME Class 1, 2, and 3 systems.
C. ASME Section XI Code Case: 3 None D. Construction Code and Claos (If Applicable)!
ASME Soetion III, Class 1, 2, and 3
(
E. Valve Category (If Applicable):
Not applicable F. Attachments (list) or Ref3rences:
None II. Reference Code Requiremotet from which relief is desired:
ASME Boiler and Pressure Vessel Code,Section XI, 1986 and 1989 Edition, Article IWA-5250.
t l
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l III. flants for Requenting Rolleft The ASME Boiler and Pressure Vessel Code,Section XI, 1986 and 1989 Edition, Article IWA-5250, CORRECTIVE ME4SUR35, states in ;
part:
"(a) The source of leakages detected during the conduct of a system pressure test shall be located and evaluated by the owner for corrective measures as follows:
(1) buried components....
(2) if leakage occurs at a bolted connection, the bolting shall be comoved, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-31003 (3) repairs or replacements..."
If a leaking bolted connection is observed during a system pressure test, IWA-5250 (a) (2) requires the removal and inspection of all tha bolting associated with the subject connection. McGuire Nuclear Station Engineering personnel have determined that tha purpose of this requirement is to verify that no unscceptable bolting degradation has occurred (a) ale. : 'ho length s of the bolting or 'b) in the head or nut area wh.c' ,
inter. faces with the mating components of the connection at,.;e the ,
duration of the leakage is unknown.
1 Station personnel have developed in alternative inspection methodology which is equivalent in determining-the condition of the bo'*ad connection while reducing the possibility of personnel injur3 .a burden imposed by IWA-5250 (a) (2) that will be relieved by thin request is as follows:
Current ASME XI requirements involving inspection of bolted connections increase the probability of personnel burn accidents. Susceptibility to the increased risk resuLts from rising containment temperature as a result of the removal of the insulation for inspection of ASME Class 1 bolted connections at high syntem pressure and temperature.
Containment temperatures rine as a result of the removal of the insulation and could affect the integrity of the Ice condenser by sublimation of a portion of the ice. This mandates that the insulation remain in place until just-prior to the VT-2, thus placing plant personnel in a rigorous environment with the relatively high potential for burn accidents.
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tf the proposed Alternative Examination is not available for o' plication and a bolted connection leakage is observed r ating system pressure testing just prior to restart of the Units (Hode 3), an unwarranted delay in unit restart will occur.
IV. Alternate Examinations ,
The proposed alternative methodology will meet t he intent of the IWA-5250 requirement while avoiding or limiting the imposed burdens as stated above. The Alternative Examination will be opplied &c the discretion of station personnel for each Lpecific bolted connection.
(1) All bolted cor.nections within the scope of the planned system pressure testing will be ident. fled.
(2) Tr.e identified connections will be compared to the bolted-connections scheduled for disasocinbly during the outage.
(3) The bolted connections whicn are not schedulod for disassembly during U.e outage will be inspected prior to Mode 5 (cold shutuown) of the outage while the bolted connections are at their normal plant operating pressures.-
The inspection results and / e of inspection for the specific connection will be ocumented in the station work management system.
(4) If a connection is found to be a scurce of leakage, the connection will be disassembled and the bolting inspected
, during the cutage.
(5) System pressure testing associated with the outage will be conducted as normally scheduled. .If a bolted connection is detormined to be a source of leakage, the duration of +.he leakage effect on the bolting will be conservatively determined to be since cne disassembly during the outage.
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(6) With this information, an engineeriaq evaluation can be formally documented to assess the cur.nection. The evaluation will specify the required disassembly date for the bolted connection in order to ensure that unacceptable bolting degradation does not occur. The required disassembly date shall not exceed the nnxt scheduled refueling outage.
The proposed Alternative Examination procedure will provide an acceptable level of quality and safety. Dolting removal and replacemer.t is mandated by the Code because the Owner has no evidence of the condition of bolted connection.
The Alternate Examination procedure permits the performance of either a VT-3 or normal Mechanical Quality control inspection -
documenting the connection disassembly / reassembly thereby identifying all non degraded bolting prior to the system pressure test.
V. Implewnentation Schedule:
The-proposed Alternative E/xminations, if found acceptable, will be implemented during refueting outage End of Cycle (EOC) 9 for both Units 1 and 2.
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