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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
[Table view] |
See also: IR 05000400/1991027
Text
ACCELERATED
DISTRIBUTION
DEMONSTPWTION
SYSTEM REGULATORY
INFORMATION
DISTRIBUTION
SYSTEM (RIDS)ACCESSION'BR:9202270071
DOC.DATE: 92/02/24 NOTARIZED:
NO CIL:50-400
Shearon Harris Nuclear Power'Plant, Unit 1, Carolina UTH.NAME AUTHOR AFFILIATION
ICHEY,R.B.
Carolina Power&Light Co.RECIP.NAME
RECIPIENT AFFILIATION
Document Control Branch (Document Control Desk).SUBJECT: Responds to NRC 920124 ltr re violations
noted in insp rept 50-400/91-27.Corrective
actions:comparator
channel selector switch was returned to normal position.DZSTRZBUTZON
CODE: ZEOZD COPZES RECEZVED:LTR
i ENCL/SZSE: TITLE: General (50 Dkt)-Insp Rept/Notice
of Violation Response NOTES:Application
for permit renewal filed.DOCKET¹05000400 05000400 RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS AEOD/DEIIB
DEDRO NRR MORISSEAUiD
NRR/DLPQ/LPEB10
NRR/DREP/PEPB9H
NRR/PMAS/ILRB12
OE DI REGMX.LE-'=-" 02 EXTERNAL: EG&G/BRYCEgJ.H.
NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 RECIPIENT ID CODE/NAME MOZAFARI,B.
AEOD AEOD/DSP/TPAB
NRR HARBUCKgC.
NRR/DLPQ/LHFBPT
NRR/DOEA/OEAB
NRR/DST/DIR
SE2 NUDOCS-ABSTRACT
OGC/HDS1 RGN2 FILE 01 NRC PDR COPIES LTTR ENCL 1'1 l.1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1l.NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION
LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24
Carolina Power&Light Company P.O.8ox 165~New Hill, N.C.27562 R.8.RICHEY Vice President Harrts Nuclear Project FEB 2 4 f992 Letter Number: HO-920049 (0)Do'cument Control Desk United States Nuclear Regulatory
Commission
Washington, DC 20555 NRC-775 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO.50-400 LICENSE NO.NPF-63 REPLY TO A NOTICE OF VIOLATION Gentlemen:
In reference to your letter of January 24, 1992, referring to NRC Inspection
Report RII: 50-400/91-27, the attached is Carolina Power and Light Company's reply to the violations
identified
in Enclosure l.It is considered
that the corrective
actions taken/planned
are satisfactory
for resolution
of the violations.
'hank you for your consideration
in this matter.Very truly yours, A,4~R.B.Richey Vice President Harris Nuclear Project MGW:dmw Attachment
RGB'"=.~
cc: Mr.S.D.Ebneter (NRC-RII)Ms.B.L.Mozafari (NRC)Mr.J.E.Tedrow (NRC-SHNPP)MEM/H0-920049.0/1/OS1
9202270071
920224 PDR ADOCK 05000400 8 PDR yP
Attachment
To NRC-775 REPLY TO A NOTICE OF VIOLATION NRC INSPECTION
REPORT NO.50-400/91-27
VIOLATION 400 91-27-01 Re orted Violation:
Technical Specification
6.8.l.a requires that written procedures
be established
and implemented
covering procedures
outlined in Appendix A of Regulatory
Guide 1.33, Revision 2, February 1978.Regulatory
Guide 1.33, Appendix A, paragraph 5 requires procedures
for responding
to alarmed conditions.
Alarm response procedure ARP-ALB-013, Main Control Board,-section
ALB-013-5-4, directs the operator to try and reset the power range lower detector high flux deviation or auto defeat alarm by momentarily
placing the comparator
channel lower section switch to the appropriate
position and then return it to the normal~position.Contrary to the above, on January 13, 1992, the comparator
channel lower section switch was not returned to the normal position following an attempt to reset the alarm but was instead found to be positioned
in the N-42 defeat position.This is a Severity Level IV violation (Supplement
I).Denial or Admission and Reason for the Violation:
The violation is admitted.On January 13, 1992, the Nuclear Instrumentation (NI)comparator
channel selector switch for power range lower detector flux deviation and auto-defeat
was found in the N-42 position.The last operation of this switch was logged on January 12, 1992 on the dayshift.The alarm was being received frequently
due to a downpower maneuver, detector calibration
cycle, and fuel cycle characteristics.
The log indicated"numerous" detector deviation or auto defeat alarms.No alarms wer'e received during the following nightshift.
This indicates a failure to return the switch to the normal position after proper alarm response on the dayshift on January 12, 1992.The switch position was not noted at the turnover for nightshift
or the following dayshift (1/13/92).
The cause of the violation is due to inappropriate
work practice, in that the switch was inadvertently
left in the N-42 position.Corrective
Ste s Taken and Results Achieved: Upon discovery of this error on January 13, 1992, the comparator
channel selector switch was returned to the normal position.Surveillance
test OST-1039, Calculation
of Quadrant Power Tilt Ratio (QPTR), Weekly Interval Mode 1, was performed on January 12, 1992 and January 13, 1992 which satisfies the requirement
to calculate QPTR every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the comparator
channel selector switch is not in the normal position.Therefore, adequate control of the QPTR was maintained
during this period.MEM/H0-910249.0/2/OS1
Attachment
To NRC-775 REPLY TO A NOTICE OF VIOLATION'RC INSPECTION
REPORT NO.50-400/91-27 (continued)
Corrective
Ste s Taken-To Avoid Further Violations:
This violation is being reviewed with the Operations
personnel on-shift at'the , time the switch was inadvertently
left in the N-42 position as well as the remaining active shift Operations
personnel.
Self-verification
of switch positioning
and thorough turnover walkdowns will be stressed.,Marking
'of the NI'ompaiator
channel selector switch to facilitate
easier verification
of switch position is being evaluated.
Date When Full Com liance Will Be Achieved: Full compliance
will be achieved on February 24, 1992.VIOLATION 400 91-27-03 Re orted Violation:
Technical Specification
6.5.4.1 requires that audits of unit activities
shall be performed by the Nuclear Assessment
Department.
These audits shall encompass:
The results of actions taken to correct deficiencies
occurring in unit equipment, structures, systems, o'r method of operation that affect nuclear safety, at least once per six months.The conformance
of unit operation to provisions
contained within the technical specifications
and applicable
license conditions, at least once per 12 months.t The training, qualifications, and performance, as a group,.of the entire unit staff, at least once per 12 months.The'mergency
plan and implementing
procedures, at least once per 12 months.Contrary to the above, as of January 15, 1992, audits of unit activities
were not performed in that: An audit was not performed't
least once per six months to evaluate the results of actions taken to correct deficiencies.
An audit was not performed at least once per 12 months to evaluate the conformance
of unit operation to provisions
contained within technical specifications
and applicable
license conditions.
An audit was not performed at least once per 12 months to evaluate the training, qualifications, and performance
as a group, of the entire unit staff.MEM/H0-910249.0/3/OS1
Attachment
To NRC;775 i.REPLY TO A NOTICE OF VIOLATION NRC INSPECTION
REPORT NO.50-400/91-27 (continued)
Re orted Violation: (continued)
An audit was not performed at least once per 12 months to evaluate the emergency plan and implementing
procedures.
This is a Severity Level IV violation (Supplement
I).Denial or Admission and Reason for the Violation:
The violation is admitted.Nuclear Assessment
Department (NAD)Guidelines
improperly
interpreted
the assessment
frequency interval requirements
contained in the Technical Specifications.
Specifically, the Guideline required that assessments
start within the frequency interval defined in the Technical Specifications, and also provided that an assessment
start date could be extended by up to 25%of the frequency interval.The expectation
was that the extension would not be routinely used but was available to help with manpower/resource
allocation.
The guideline also required that, if any extension was used, the subsequent
assessments
would be started on a frequency based on the original start date, thereby eliminating
the potential for cumulatively
extending an assessment
start date oyer several assessment
intervals.
This interpretation
of Technical-
Specification
requirements
contained in NAD Guidelines
was in error.A review of the NAD assessment
records indicates that the assessments
cited were conducted within the time limits of established
department
guidelines, but were completed outside the frequency interval requirements
of Technical Specifications.
Corrective
Ste s Taken and Results Achieved: A review of assessment
records for those assessments
required by Technical Specifications
was undertaken
to determine those assessments
which exceeded the standard frequency as defined by the Technical Specifications.
The assessments
which fell outside the standard frequency intervals have been completed and line management
briefed of the results.The final reports will be forwarded within 30 days of the briefings.
By memorandum
dated February 7, 1992, NAD initiated a new policy requiring that assessments
be completed, including briefing within the Technical Specification
required frequency interval, and that.no extension be applied.This memorandum
supersedes
the NAD guideline until the guideline is revised to reflect NAD's current policy.MEM/H0-910249.0/4/OS1
i
Attachment
To NRC-775 i REPLY TO A NOTICE OF VIOLATION NRC INSPECTION
REPORT NO.50-400/91-27 (continued)
Corrective
Ste s Taken To Prevent Further Violations:
The next assessment
in each area required by Technical Specifications
has been scheduled to be completed prior to one frequency interval from the previous assessment
start date.This will ensure that the next assessments
are within Technical Specification
time intervals.
Once established, assessment
frequency intervals will be determined
from the debriefing
date of the previous assessment.
In this manner, assessments
will be completed within Technical Specification
required times.Similar reviews and appropriate.
corrective
action have been taken with respect to Technical Specification
requirements
at all three s'es.Date When Full Com liance Will Be Achieved: Full compliance
will be achieved on March 13, 1992.Re orted Weakness: TS 6.5.4.4 requires that audit reports encompassed
by TS 6.5.4.1 shall be forwarded to various management
positions within 30 days after completion
of the audit.The Operations
audit required by TS 6.5.4.l.a was completed on December ll, 1991.The Operations
manager did not receive the Operations
audit until January 14, 1992, which exceeded the 30-day time requirement.
A previous failure to forward audit reports within 30 days was identified
as a violation (400/91-18-02).
The tardiness in forwarding, this Operations
audit indicates that this process is still not performed adequately, and the forwarding
process is considered
to be weak.~Res ense: As stated, the Operations
assessment
'was completed on December 11, 1991.With that completion
date, the assessment
report was required to be issued and forwarded on or before January 10, 1992.The report was approved and forwarded on January 9, 1992.CP&L uses internal mail routing for such documents and routinely completes distribution
within 2-3 days.We believe that signing the report for distribution
within 30 days of assessment
completion
with normal internal mail routing fully meets the 30-day requirement
for report issuance.Re orted Weakness: e 10 CFR 50 Appendix B, Part I, requires that organizations
performing
quality assurance functions shall report to a management
level such that organizational
freedom is provided.Audit.reports of site activities
are used as a quality assurance function to report to corporate management.
It was noted by the inspector that draft audit reports were being distributed
to the audited function manager prior to finalization
of the audit report and subsequent
distribution
to corporate management.
This indicates that a lack of organizational
freedom exists in the audit program and is, therefore, considered
to be a weakness.MEM/H0-910249.0/5/OS1
Attachment
To NRC-775 i REPLY TO A NOTICE OF VIOLATION NRC INSPECTION
REPORT NO.50-400/91-27 (continued)
R~es ense: Draft reports may be provided to the audited/assessed
function managers to facilitate
communications.
Since debriefs are handled orally, this provides line management
the first hard copy of the assessment
results.Their review is used to help ensure accuracy of the final assessment
report and clearer understanding
of the results.The content of final assessment
reports is independent
of line management
and remains the responsibility
of the Nuclear Assessment
Department.
MEM/H0-910249.0/6/OS1
i