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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
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CATEGORY REGULA RY INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:9712230009 DOC.DATE: 97/12/16 NOTARIZED: NO DOCKET ¹ FACIL:50-.400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH,~RAIMI~~ .- AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power &. Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Requests relief from criteria of 10CFR50.55a(g) (6) (ii) (A) (2) for augmented exams of RPV welds at plant. Relief requested from listed ASME B&PV Code,Section XI,requirements for final insp period of first 20 year insp interval.
DISTRIBUTION CODE: A047D TITLE: OR COPIES RECEIVED: LTR Submittal: Inservice/Testing/Relief from J ENCL I SIZE: ICI 4 ASME Code - GL-89-04 H.
NOTES:Application for permit renewal filed. 05000400 G
RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 ROONEY, V 1 1 Y
INTERNAL: ACRS 1 1 AEOD/SPD/RAB 1 1 E CE E 1 1 1 NRR/DE/EMEB 1 .'1 NUDO -ABSTRACT 1 1 OGC/HDS2 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
A
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Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris NUclear Plant SERIAL: HNP-97-217 DEC 16 1997 10 CFR 50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50<00/LICENSE NO. NPF-63 ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI INSERVICE INSPECTION PROGRAM RELIEF REQUEST REACTOR PRESSURE VESSEL
Dear Sir or Madam:
In accordance with 10 CFR 50.55a(a)(3), Carolina Power & Light Company (COL) hereby requests relief from the criteria of 10 CFR 50.55a(g)(6)(ii)(A)(2) for augmented examinations of reactor pressure vessel (RPV) welds at the Harris Nuclear Plant (HNP). Specifically, relief is requested from the following American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BkPV) Code,Section XI, requirements for the final inspection period of the first 10-year inspection interval:
)
"Essentially 100%" (i.e., 90%) volumetric coverage for each reactor pressure vessel shell weld in accordance with Table IWB-2500-1, Examination Category B-A, Item Number B1.11 (one weld).
"Essentially 100%" (i.e., >90%) volumetric coverage for each reactor pressure vessel weld (other than shell welds) in accordance with Table IWB-2500-1, Examination Category B-A, Item Numbers B1.21 (one weld), B1.22 (one weld) and B1.30 (one weld); Examination Category B-D, Item Number B3.90 (three welds); and Examination Category B-F, Item Number B5.10 (two welds).
The required 10-year Inservice Inspection (ISI) examinations performed on the RPV welds in accordance with ASME BAPV Code 1983 Edition, with Addenda through Summer 1983,Section XI, were completed in May 1997. Allexaminations were performed to the maximum extent possible utilizing automated examination equipment, techniques, and data I recording/analysis systems. The RPV welds were volumetrically (UT) examined using +0 qualified in accordance with Appendix VIIIof Section XI, as implemented by the ('rocedures utility Performance Demonstration Initiative. In addition, the welds were subject to visual 97i2230009 97i2i6 Ifllllflllfllllfllfll jl fffl/illlff/fll 5413 Shearon Harris Road New Hill NC Tel 919 362-2502 Fax 919 362-2095
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Document Control Desk e
SERIAL: HNP-97-217 Page 2
'(VT-2) examinations. As a result of the examinations, six recordable indications were detected, but were within the allowable Code limits. By letter dated August 29, 1997 (HNP-97-169),
CP8cL forwarded the HNP ISI Summary Report documenting the inspections performed during Cycle 7 operations, including Refueling Outage No. 7 (RFO-7).
As stated in the CP8cL letter to the NRC dated March 11, 1997 (HNP-97-060), CP&L committed to notify the NRC ifthe augmented examinations conducted during RFO-7 could not obtain "essentially 100%" volumetric coverage for each RPV weld. Due to RPV design configuration obstructions and/or limitations, several welds did not receive "essentially 100%" volumetric coverage examination. Therefore, CPS's requesting relief from the "essentially 100%"
volumetric coverage requirement for these welds.
The detailed request for relief number R1-011 is provided in Attachment 1 to this letter. This relief request indicates the specific components for which relief is requested, the basis for requesting relief, the alternate examinations performed, and the justification that an acceptable level of quality and safety has been achieved. Attachment 2 to this letter provides the results of the 1997 automated inservice examination of the RPV and adjacent piping welds at HNP.
Please refer any questions regarding this submittal to Mr. J. H. Eads at (919) 362-2646.
Sincerely, AEC/aec Attachments (2) c: Mr. J. B. Brady (NRC Senior Resident Inspector)
Mr. L. A. Reyes (NRC Regional Administrator, Region II)
Mr. V. L. Rooney (NRR Project Manager, HNP)
Document Control Desk SERIAL: HNP-97-217 Page 3 bc: Ms. D. B. Alexander Ms. W. C. Langston (PEARAS File)
Mr. T. C. Bell Mr. C. W. Martin (BNP)
Mr. H. K. Chernoff (RNP) Mr. R. D. Martin Mr. B.H. Clark Mr. P. M. Odom (RNP)
Mr. G. W. Davis Mr. W. S. Orser Mr. J. W. Donahue Mr. R. F. Saunders Mr. W. J. Dorman (BNP) Mr. D. L. Tibbitts Mr. W. J. Hindman Mr. C. A. VanDenburgh Mr. W. D. Johnson Nuclear Records Mr. R.M. Krich Licensing File File: H-X-0710
ATTACHMENT1 TO SERIAL: HNP-97-217 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL
A ACHMENT I TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAINING WELDS IN REACTOR VESSEL COMPONENTS FOR WHICH RELIEF IS REQUESTED:
B1.11 STHW-RV-04 Lower shell to bottom head 1)
B1.21 CHW-RV-17 Bottom Head Dome (Table 2)
B1.22 MHW-RV-16 Meridional (Table 2)
FTSW-RV-01 to Upper Shell (Table
@45'lange B1.30 2)
B3.90 RVNOZB0-N-02 Outlet Nozzle 9265'utlet 9265'Table (Table 2)
B3.90 RVNOZ CO-N-04 Nozzle (Table 2) 6145'utlet B3.90 RVNOZAO-N-06 Nozzle 925'afe (Table 2)
B5.10 RVNOZAI-N-01-SE End to Inlet Nozzle (Table 2) 9335'utlet B5.10 RVNOZB0-N-02-SE Nozzle to Safe End (Table 2)
Table 1 provides the results of the augmented RPV examinations for the RPV shell welds.
Table 2 provides the results of the RPV examinations for RPV welds other than shell welds.
INSERVICE INSPECTION REQUIREMENTS:
ASME Section XI, 1983 Edition with Addenda through Summer 1983.
Examination Category B-A, Item Number B1.11, B1.21, B1.22, B1.30 Examination Category B-D, Item Number B3.90 Examination Category B-F, Item Number B5.10 CODE RELIEF REQUEST:
Relief is requested from 100 percent volumetric (UT) examination coverage due to pressure retaining welds not being 100 percent accessible over the entire length. The examinations are limited because of physical obstructions and surface geometry such as instrumentation tubes, support lugs, weld transition, integral extension and counterbore geometry.
BASIS FOR REQUESTING RELIEF:
The subject welds received limited examination coverage due to physical obstructions and nonconducive geometric surface conditions. The obstructions physically prevent 100 percent examination coverage of the subject weld volume. The nonconducive geometric surface conditions prevent sufficient sound propagation into the weld examination volume at specific locations, therefore 100 percent examination coverage is not achievable. Attempting to perform supplemental examinations from the outside surface would have required extensive surface preparation and expended unwarranted dose without a commensurate increase in the level of reliability, quality, or safety.
Page A1-1
A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. Rl-011 PRESSURE RETAINING WELDS IN REACTOR VESSEL
'ALTERNATEEXAMINATIONS:
The Reactor Pressure Vessel (RPV) pressure retaining welds are volumetrically (UT) examined to the maximum extent possible in accordance with the Inservice Inspection Program schedule.
In addition, the welds are subject to visual (VT-2) pressure tests during each refueling outage.
TECHNICALJUSTIFICATION FOR REQUESTING RELIEF:
Pressure retaining welds in the RPV have been volumetrically (UT) examined to the maximum extent possible during preservice and first interval inservice examinations with no rejectable indications noted. The design configuration introduces obstructions and nonconducive surface conditions that prevent 100 percent volumetric examination coverage. The minimal number and magnitude of indications recorded during the preservice examinations and first interval inservice examinations indicate that the majority of the vessel examination volume is free of detrimental discontinuities. Therefore, the likelihood of the limited areas not examined due to physical obstructions having a rejectable indication is minimal. The RPV examinations have been performed utilizing the state of the art examination equipment, techniques and data recording/analysis systems. Additionally, Performance Demonstration Initiative procedures, qualified personnel and techniques were utilized as a conservative measure to incorporate the current industry practice and technology.
CONCLUSION Approval of this relief request will have no impact on overall plant quality, safety or reliability, since the welds have been subject to extensive construction code, preservice, and inservice examinations. In addition, the pressure retaining welds are subject to visual (VT-2) pressure tests during refueling outages.
Page Al-2
A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 1: Results of Harris Augmented Reactor Pressure Vessel Examinations 1" 10- Year Interval WELD ITEM NO. DESCRIPTION COVERAGE LIMITATION CSW-RV-02 B1.11 Upper Shell to Intermediate Shell 100% N/A CSW-RV-03 B1.11 Intermediate Shell to Lower Shell 100% N/A STHW-RV-04 B1.11 Lower Shell to Bottom Head 80% Radial Support Lugs and Weld Transition LSW-RV-05 B1.12 Upper Shell Longitudinal 91% Noz. AON-06 and Flange Taper (>90%)
LSW-RV-06 B1.12 Upper Shell Longitudinal 96% Noz. BIN-03 and Flange Taper (>90%)
LSW-RV-07 B1.12 Intermediate Shell Longitudinal 100% N/A LSW-RV-08 B1.12 Intermediate Shell Longitudinal 100% N/A LSW-RV-09 B1.12 Lower Shell Longitudinal 100% N/A LSW-RV-10 B1.12 Lower Shell Longitudinal 100% N/A Page Al-3
A ACHMENT 1 TO SERIAL HNP 7 REQUEST FOR RELIEF NO. Rl-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 2: Results of Harris Reactor Pressure Vessel Examinations 1" 10- Year Interval WELD ITEM NO. DESCRIPTION LIMITATION CHW-RV-17 B1.21 Bottom Head Dome 67% Instrumentation Tubes MHW-RV-11 B1.22 Meridional 94% Instrumentation Tubes and Radial Support Lug (>90%)
8345'eridional MHW-RV-12 B1.22 94% Instrumentation Tubes and Radial Support Lug (>90%)
8285'eridional MHW RV-13 B1.22 95% Instrumentation Tubes
(>90%)
8225'eridional MHW-RV-14 B1.22 95% Radial Support Lug (>90%)
8165'eridional MHW-RV-15 B1.22 91% Instrumentation Tubes and Radial Support Lug (>90%)
8105'eridional MHW-RV-16 B1.22 8215'OVERAGE 90% Instrumentation Tubes
@45'lange FTSW-RV-01 B1.30 to Upper Shell 67% ID Surface Taper RVNOZAI-N-01 B3.90 Inlet Nozzle 93% Nozzle Inner Radius 8335'utlet
(>90%)
RVNOZB0-N-02 B3.90 Nozzle 80% Integral Extension
@265'nlet RVNOZBI-N-03 B3.90 Nozzle 93% Nozzle Inner Radius
@215'utlet
(>90%)
RVNOZCO-N-04 B3.90 Nozzle 80% Integral Extension
@145'nlet RVNOZCI-N-05 B3.90 Nozzle 93% Nozzle Inner Radius 895'utlet
(>90%)
RVNOZAO-N-06 B3.90 Nozzle 80% Integral Extension 825'nlet RVNOZAO-N B3.10 Nozzle 100% N/A IRS @335'utlet RVNOZB0-N B3.10 Nozzle 100% Integral Extension IRS 8265'nlet RVNOZBI-N B3.10 Nozzle 100% N/A IRS Page Al-4
A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 2: Results of Harris Reactor Pressure Vessel Examinations 1" 10-Year Interval WELD ITEM NO. DESCRIPTION LIMITATION RVNOZCO-N Integral Extension B3.10 Outlet Nozzle 100%
IRS 8145'nlet RVNOZCI-N B3.10 Nozzle 100% N/A IRS 895'utlet RVNOZAO-N B3.10 Nozzle 100% Integral Extension IRS RVNOZAI-N B5.10 825'OVERAGE End to Inlet Nozzle 825'afe 74% ID Surface Counterbore SE 8335'utlet RVNOZB0-N B5.10 Nozzle to Safe End 76% ID Surface Counterbore SE 8265'afe RVNOZBI-N B5.10 End to Inlet Nozzle 95% No Relief Requested SE (>90%)
8215'utlet
'VNOZCO-N 85.10 Nozzle to Safe End 94% No Relief Requested SE 6 (>90%)
145'afe RVNOZCI-N B5.10 End to Inlet Nozzle 92% No Relief Requested SE (>90%)
95'utlet RVNOZAO-N B5.10 Nozzle to Safe End 99% No Relief Requested SE (>90%)
Page A1-5
ATTACHMENT2 TO SERIAL: HNP,-97-217 1997 AUTOMATEDINSERVICE EXAMINATIONOF THE REACTOR PRESSURE VESSEL AND ADJACENT PIPING WELDS AT THE HARRIS NUCLEAR PLANT