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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 1
'RI INFORMATION DISTRIBUTION OSTEM (RIDE)
U ACCESSION NBR:9709090323 . DOC.DATE: 97/08/29 NOTARIZED: YES DOCKET FACIL:50-400 Shearon 'Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides closeout documentation Harris Nuclear Plant re GL 92-08, "Thermo-Lag 330-1 Fire Barriers." Plant will restore Thermo-Lag Barrier configurations to svc 6 discontinue compensat'ory actions accordingly.
A DISTRIBUTION CODE: A029D COPIES RECEIVED:LTR , ENCL SIZE:
TITLE: Generic Letter 92-008 Thermo-Lag 330 Fire Barrier T NOTES:Application for per'mit renewal filed. 05000400 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PD2-1 LA 1 0 PD2-1 PD 1 1 ROONEY,V 1 1 INTERNAL ILE CE T 1 1 NRR/DE/EELB 1 1 R W/PD3-1 1 1 NRR/DSSA/SPLB 1 1 RGN2 FILE 1 1 EXTERNAL: NOAC NRC PDR 1 1 D
U 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 10 ENCL 9
1I C,
1
Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant SERIAL: HNP-97-170 AUG 2 9 1997 10 CFR 50.54(f)
United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 CLOSEOUT DOCUMENTATIONREGARDING NRC GENERIC LETTER 92-08, "THERMO-LAG330-1 FIRE BARRIERS"
Dear Sir or Madam:
Pursuant to 10 CFR 50.54(f), Carolina Power & Light Company (CP&L) hereby provides closeout documentation for the Harris Nuclear Plant (HNP) regarding Generic Letter 92-08, "Thermo-Lag 330-1 Fire Barriers." By letter dated May 16, 1997, CP&L provided a status of Thermo-Lag resolution at HNP.
Enclosure 1 of the May 16, 1997 letter described the Thermo-Lag resolution activities which had been completed and identified three remaining work activities. These remaining items have now been completed and this letter provides a revised Enclosure 1 which summarizes the completed Thermo-Lag resolution activities. Enclosure 2 provides details of HNP actions completed in response to the NRC Request for Additional Information regarding Generic Letter 92-08.
In accordance with the commitment contained in HNP letter, (Serial: NLS-93-101), dated April 16, 1993, this letter serves as written notification of our intent to restore Thermo-Lag Fire Barrier configurations to service and discontinue compensatory actions accordingly.
Questions regarding this matter may be referred to Mr. J. H. Eads at (919) 362-2646.
Sincerely, JHE/jhe Enclosures W. R. Robinson, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are employees, contractors, and agents of Carolina Power & Light Company.
9709090323*'it7082'it PDR ADOCK 05000400 P PDR Notary (Sea] ~ y~
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+o s B Brady NRC Sr. Resident Inspector Z 4~8 Mr. V. L. Rooney, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator e+ "UBL'I< c,I State Road 1134 New Hill NC Tel 919 362-2502 Fax 919 362-2095 +r~4$ >>
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Document Control Desk HNP-97-170 / Page 2 bc: Ms. D. B. Alexander Mr. W. J. Hindman Mr. T. C. Bell Mr. W. D. Johnson Mr. R. K. Buckles (LIS) Mr R. M. Krich Mr. H. Chernoff (RNP) Ms. W. C. Langston (PESRAS File)
Mr. B. H. Clark Mr. R. D. Martin Mr. G. W. Davis Mr. W. S. Orser Mr. J. W. Donahue Mr. R. F. Saunders Mr. W. J. Dorman (BNP) Mr. W. D. Tibbitts Mr. H. W. Habermeyer, Jr. Nuclear Records Harris Licensing File
ENCLOSURE 1 THERMO-LAG RESOLUTION ACTIVITIES The following is a brief summary of completed Thermo-Lag resolution activities for the Harris Nuclear Plant (HNP).
Three full scale fire tests of the plant configurations were performed independent of the NEI generic fire testing program. These fire tests were performed in 1994 and 1995.
Engineering evaluations have been completed to document the acceptance of this testing against the as-found conditions of the fire barrier including the completion of a 10 CFR 50.59 safety evaluation (see Attachment 2) which determined the barrier enclosures are adequate for the hazard.
Chemical testing was completed on Thermo-Lag samples in 1996 as part of NEI's generic chemical testing program.
- 3. Design changes were developed in 1996 to upgrade penetration sleeves located in fire wall and ceiling configurations. These upgrades were developed based on actual fire test configurations. Field installation of these upgrades began in 1996 and were completed in August 1997. This activity included corrective actions for recently identified fire barrier deficiencies (LER 97-006).
The one-hour partial height fire wall configuration in the Reactor Auxiliary Building was redesigned in 1996 and the Thermo-Lag material was removed and replaced with an alternate material in April 1997.
Engineering evaluations were started in 1995 and completed in August 1997 addressing Thermo-Lag material thickness, use of Thermo-Lag on fire door transoms, revisions to combustible loading calculations to reflect the combustibility of Thermo-Lag, ampacity derating evaluations and revisions to the safe shutdown analysis to reduce dependence on Thermo-Lag protection.
A design change was developed in 1996 to reroute safe shutdown cables (source range cable) to eliminate the need for existing Thermo-Lag protection. This reroute was completed prior to Refueling Outage Number 7 (RFO-7).
- 7. A design change was developed in 1996 to reroute safe shutdown cables (cables for pressurizer and reactor head vent valves) to eliminate the need for the existing Thermo-Lag protection. This design change also specified removal of Thermo-Lag material associated with conduits protected with Thermo-Lag. A small portion of Thermo-Lag material associated with these conduits could not be removed due to physical accessibility restrictions. Analyses to support the retention of this material (including evaluation of cable ampacity derating, combustible loadings, and seismic requirements) were completed. Implementation of this design change was completed during the RFO-7 outage.
I A review of the seismic requirements for Thermo-Lag installations was started in 1995 which included a field walkdown of the installed configurations to determine interactions with safety related components. An engineering evaluation of these interactions was completed in May 1996 and a site specific seismic test was also performed in July 1996 to envelope several configurations that required additional test data to support acceptance of their installations. The engineering evaluations associated with the seismic reviews and testing were completed in February 1997.
- 9. A determination of the Quality Attributes necessary to support future procurement of required Thermo-Lag material was started in 1996 and completed in March 1997.
ENCLOSURE 2 HNP ACTIONS COMPLETED IN RESPONSE TO NRC REQUEST FOR ADDITIONALINFORMATION
- 1. Thermo-Lag Materials 1.a. Describe the specific tests and analyses that will be performed to verify that the Thermo-Lag fire barrier materials that are currently installed at the Shearon Harris Nuclear Power Plant, Unit 1 (SHNPP), or that will be installed in the future, are representative of the materials that were used to address the technical issues associated with thermo-lag barriers and to construct the fire endurance and ampacity derating test specimens. The tests and analyses shall address the material properties and attributes that were determined or controlled by TSI during the manufacturing process and the quality assurance program. The tests and analyses shall also address the material properties and attributes that contribute to conclusions that the Thermo-Lag materials and barriers conform to NRC regulations. These include:
(1) chemical composition (2) material thickness (3) material weight and density (4) the presence of voids, cracks, and delaminations (5) fire endurance capabilities (6) combustibility (7) flame spread rating (8) ampacity derating (9) mechanical properties such as tensile strength, compressive strength, shear strength, and flexural strength.
The scope of Thermo-Lag 330-1 material used at HNP and covered by this response includes the following:
A fire area enclosure located in the Cable Spreading Rooms and a fire area enclosure located in the Auxiliary Control Panel room, A partial height fire wall located in the Reactor Auxiliary Building (wall subsequently reconstructed without Thermo-Lag),
Fire door transoms and mullion fire proofing protection, and Conduit protection (Thermo-Lag conduit protection will no longer be credited as a fire barrier based on rerouting of several safe shutdown cables and crediting alternate safe shutdown components. The alternate component evaluation was completed in April 1997 and the cable reroute
modifications, including removal of thermo-lag material where possible, were completed prior to the completion of RFO-7).
Future installations of Thermo-Lag to support repairs or upgrades will be performed in accordance with the CP&L Quality Assurance Program for Fire Protection Systems. Quality attributes have been developed from industry test results which can be utilized by HNP during receipt inspections to verify acceptability of the Thermo-Lag material.
(1) Chemical Composition Status: Complete Comments: HNP participated in NEI chemical testing program. The chemical testing results are described in HNP letter dated July 12, 1996 (HNP-96-112).
(2) Material Thickness Status: Complete Comments: HNP performed thickness measurements in accordance with the guidance provided in ASTM E605-93 for the area enclosures. Fire door transoms and mullions were evaluated per Generic Letter 86-10.
(3) Material Weight and Density Status: Complete Comments: HNP participated in NEI chemical testing program and no additional material property testing was identified.
(4) Presence of Voids, Cracks, and Delaminations Status: Complete Comments: Material subject to voids, cracks, and delaminations used on conduits is no longer credited as a fire barrier at HNP. Other applications of thermo-lag (flat panels and trowel grade material) used at HNP are not subject to this concern.
(5) Fire Endurance Capabilities Status: Complete Comments: Testing complete; however, additional analyses of the area enclosures and penetration reevaluation and/or upgrades were required. Additional analyses required for the evaluation of the Thermo-Lag area enclosures were completed in August 1997.
Reevaluation and/or upgrades of twenty-eight barrier penetrations were completed in August 1997. This activity included corrective actions for recently identified fire barrier deficiencies (LER 97-006). In addition, fire door transoms and mullions were evaluated per Generic Letter 86-10.
(6) Combustibility Status: Complete Comments: HNP utilized the information contained in the NEI combustibility evaluation guideline. No plant specific combustibility testing was performed. Applicable area combustible loading calculations have been revised to include thermo-lag as a combustible material.
(7) Flame Spread Rating Status: Complete Comments: HNP utilized the information contained in the NEI combustibility evaluation guideline. No plant specific flame spread rate testing was performed.
(8) Ampacity Derating Status: Complete Comments: Ampacity derating evaluations have been completed. No plant modifications were required.
(9) Mechanical Properties such as Tensile Strength, Compressive Strength, Shear Strength, and Flexural Strength.
Status: Complete Comments: Seismic evaluations (2 over 1) have been completed. Seismic testing of wall configurations has been performed where warranted.
The combination of seismic evaluations and seismic tests demonstrated adequacy. No seismic modifications were required.
l.b. Describe the methodology that will be used to determine the sample size and demonstrate that the sample size will be large enough to ensure that the information and data obtained will be sufficient to assess the total population of in-plant Thermo-Lag barriers and the materials that will be installed in the future.
In determining the sample size, consider the time of installation and manufacture of the various in-plant materials and barrier installations. Give the number and types (e.g., panels, conduit preshapes, trowel-grade material, stress skin) of samples that will be tested or analyzed.
Status: Complete Comments: HNP participated in the NEI chemical testing program. The chemical testing sample size for HNP was described in HNP letter dated July 12, 1996 (HNP-96-112). Sample size for material thickness evaluations for area enclosures was performed in accordance with the guidance provided in ASTM E605-93.
N~C l.c. Submit the schedule for verifying the Thermo-Lag materials.
Status: Complete Comments: This letter provides the overall closeout documentation for the resolution of Thermo-Lag issues at HNP.
N~C l.d. After analyses and tests have been completed, submit a written supplemental report that confirms that this effort has been completed and provide the results of the tests and analyses. Describe any changes to previously submitted plans or schedules that result from the tests or analyses.
Status: Complete
Comments: The HNP response to l.d was submitted to the NRC by letter dated July 12, 1996.
- 2. Important Barrier Parameters N~RC 2.a. Describe the examinations and inspection that will be performed to obtain the important barrier parameters given in Section II of the RAI of December 1993 for the Thermo-Lag fire barrier configurations installed at SHNPP.
Status: Complete Comments: HNP has completed joint utility fire endurance testing; however, additional analyses of the area enclosures and penetration reevaluation and/or upgrades were required. As stated in response to question l.a.(5),
additional analyses of the area enclosures were completed in August 1997.
Reevaluation and/or upgrades of twenty-eight barrier penetrations were completed in August 1997. This activity included corrective actions for recently identified fire barrier deficiencies (LER 97-006). In addition, fire door transoms and mullions were evaluated per Generic Letter 86-10.
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2.b. Describe the methodology that will be applied to determine the number and type of representative in-plant fire barrier configurations that will be examined in detail and demonstrate that the sample size is adequate to ensure that the information and data that willbe obtained are adequate to assess the total population of in-plant Thermo-Lag barriers. A large enough sample of the total population of configurations should be examined to provide reasonable assurance that the materials and important barriers parameters used to construct the in-plant barriers and any future barrier installations or modifications, are representative of the parameters used to construct the fire endurance test specimens.
Status: Complete Comments: HNP participated in the NEI chemical testing program. The chemical testing sample size for HNP was described in HNP letter dated July 12, 1996 (HNP-96-112). Sample size for material thickness evaluations was performed in accordance with the guidance provided in ASTM E605-93.
N~CR 2.c. Submit the schedule for obtaining and verifying all the important barrier parameters.
Status: Complete Comments: This letter provides the overall closeout documentation for the resolution of Thermo-Lag issues at HNP.
2.d. After information has been obtained and verified, submit a written supplemental report that confirms that this effort has been completed and provides the results of the examinations and inspections. Verify that the parameters of the in-plant configurations are representative of the parameters of the fire endurance test specimens. Describe any changes to previously submitted plans or schedules that result from the examinations.
Status: Complete Comments: This letter provides the overall closeout documentation for the resolution of Thermo-Lag issues at HNP. The following attachments provide the documentation of the results of the examinations and inspections of the Thermo-Lag barriers at HNP. As required by the NRC, additional information and documentation concerning Thermo-Lag resolution at HNP has been retained on-site and is available for review during future NRC audits or inspections.
Attachment 1 Fire endurance test summaries Attachment 2 10 CFR 50.59 Safety Evaluation on Thermo-Lag Enclosures installed in the Cable Spreading Rooms and Auxiliary Control Panel Room.
ATTACHMENT 1 FIRE ENDURANCE TEST SUMMARIES
- 1) Fire Endurance Test No. 14980-97261 dated November 7, 1994
- 2) Fire Endurance Test No. 14980-97668 dated May 18, 1995
- 3) Fire Endurance Test No. 14980-98207 dated May 23, 1995
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