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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] |
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CATEGORY j.
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9703190068 DOC.DATE: 97/03/12 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 5000400 AUTH. NAME AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION G Document Control Branch (Document Control Desk)
SUBJECT:
Transmits Rev 30 to Shearon Harris Nuclear Power Plant Emergency Plan (PLP-201).
DISTRIBUTION CODE: A045D TITLE: OR COPIES RECEIVED:LTR Submittal: Emergency Preparedness 4 ENCL SIZE:
Plans, Implement'g Procedures, C NOTES:Application for permit renewal filed. 05000400 E
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNA FILE CENTER 2 2 NRR/DRPM/PERB EB ACT 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
NOTE TO. ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8
Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant MAR 18 1997 SERIAL: HNP-97-065 10 CFR 50, Appendtx E United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 CHANGE TO EMERGENCY PLAN (REVISION 30)
Dear Sir or Madam:
In accordance with 10 CFR 50, Appendix E, Carolina Power k, Light Company hereby transmits one copy of Revision 30 to the Shearon Harris Nuclear Power Plant Emergency Plan (PLP-201).
This revision replaces all pages of the previous revision.
The changes incorporated by Revision 30 to the Emergency Plan include the following four (4) categories:
v c a Ti e ima ~te - An update of the 19S9 Evacuation Time Estimate for the 10-Mile EPZ was completed in January of 1997. The data gathered was used to update various graphs and tables listed in the Emergency Plan.
- 2. P Id III d-Th h ddd ddt dp II d IIIIII f various positions on the HNP Emergency Response Organization.
P I f .I -Th h d dd dl Ilf I . h f external support organizations, updated references or agreements, and so forth.
~le ~ica - These changes involve minor word changes that either correct previous typographical errors or slightly modify the wording without changing the intent.
A description of each change is included in the enclosure to this letter. The changes are listed by number in the order that the change occurs in the Emergency Plan. The enclosure provides a list of the changes grouped numerically into the four categories listed above.
Each of these changes has been evaluated by the plant staff as not decreasing the effectiveness of the Emergency Plan and have been implemented per 10 CFR 50.54(q).
9703i900b8 9703i2 IIIIIIIII3llllL'IIIIIIIIIIllil,llilIIIIIIIjilll h
F "4, l~>~
State Road 1134 New Hill NC Tel 919 362.2502 Fax 919 362-2095
Document Control Desk SERIAL: HNP-97-065 Questions regarding this matter may be referred to Ms. D. B. Alexander at (919) 362-3190.
Sincerely, MGW Enclosure c: Mr. J. B. Brady (NRC Senior Resident Inspector, HNP)
Mr. N. B. Le (NRR Project Manager, HNP)
Mr. L. A. Reyes (NRC Regional Administrator, Region II) two copies of Emergency Plan 2of3
F L RF T HNP- -0 MMARY F HAN F. PI P-201 R V.
Below is a list of the changes grouped numerically into the four (4) change categories:
vacuation Time imate date 6, 7, 8 P sition Related 19, 20, 21, 22, 23, 24, 25, 26, 27, 28, 29, 30, 31, 35, 38, 40, 41, 42 3,4,5,34,36,37,43,46,48
~lerica 1, 2, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 32, 33, 39, 44, 45, 47, 49 Liern ~Pa e ~an e
- 1. Page 2, Sect. 2.4.3.2 "Accident Assessment Team" was changed to "TSC Accident Assessment Team" for clarity due to the creation of the EOF Accident Assessment Team.
- 2. Page 3, Sect. 2.4.10.4.1 The EOF Accident Assessment Team was added.
- 3. Page 9, Items 1.1.l and References to EPPOS 2 and EPPOS 3 were added.
1.1.m Page 12, Sect. 1.10 Item "a" was added for accuracy.
- 5. Page 14, Fig. 1.5-2 A new map was added as an update.
Page 16, Table 1.8-1 This table was retitled and updated based on the updated Evacuation Time Estimate completed in January 1997.
Page 17, Fig. 1.8-1 This figure was updated based on the updated Evacuation Time Estimate completed in January 1997.
8., Page 20, Table 1.8-2 This table was updated based on the updated Evacuation Time Estimate completed in January 1997.
~
- 9. Page 21, Step 2.1.b "...he is freed of all other responsibilities and thus able to devote his entire effort to managing..." was changed to "...this individual is freed of all other responsibilities and thus able to focus on managing..." as a less gender- specific statement.
- 10. Page 23. Step 2.3.d "While he may consult with others, the Site Emergency Coordinator may not delegate..." was changed to "The Site Emergency Coordinator may consult with others, but may not delegate..." as a less gender- specific statement.
1 of 5
I. RF T 06 ARYOF HAN xF I P - 0 FV.
Item Pa~e ~han~e
- 11. Page 25, Step 2.4.2.s "Ensure that he is..." was changed to "Ensure that you are..." as a less gender- specific statement.
- 12. Page 25, Step 2 4.3.f "Ensure fire brigade..." and "...fire area preplans." were changed to "Ensure Fire Brigade..." and "...Fire Area Preplans." as clerical changes.
- 13. Page 26, Step 2.4.3.1.a "Supervise the Accident Assessment Team..." was changed to "Supervise the TSC Accident Assessment Team..." as a title change.
"...personnel." was added to the end of the step as a grammatical change.
- 14. Page 26, Step 2.4.3.1.e "...from the Accident Assessment Team..." was changed to "...from the TSC Accident Assessment Team..."as a title change.
- 15. Page 26, Sect. 2.4.3.2 "The Accident Assessment Team reports..." was changed to "The'SC Accident Assessment Team reports..." as a title change.
- 16. Page 30, Sect. 2.4.6, "...performance of his responsibilities." was changed to 1st para "...performance of assigned responsibilities." as a less gender-specific statement.
- 17. Page 32, Sect. 2.4.7.1, "...the position of EC-CR." was changed to "...the position of 1st para Emergency Coordinator - Control Room (EC-CR)." for clarification
- 18. Page 32, Sect. 2.4.7.1, "Responsibilities of the Emergency Coordinator - Control Room..."
was changed to "Responsibilities of the EC-CR...".
'nd para
- 19. Page 32, Sect. 2.4.7.2 "...two Status Board Plotters..." was deleted from the list of personnel reporting to the Communication Director (and the Emergency Response Organization as a whole). The responsibilities of the Status Board Plotters have been absorbed by the Admin Team personnel in the TSC and EOF.
- 20. Page 33, Step 2.4.7.2.c "Ensure that the Status Board Plotters post..." was changed to "Ensure that the Admin Team posts..." due to the deletion of the Status Board Plotter position.
- 21. Page 33, Sect. 2.4.7.3, "...and two Status Board Plotters." was changed to "...and 1st para the News Coordinator." due to the deletion of the Status Board Plotter position from the ERO and the movement of the News Coordinator from the Joint Information Center to the EOF.
- 22. Page 33, Step 2.4.7.3.b "Ensure that Status Board Plotters post current plant and off-site information on status boards in the EOF..." was changed to 2of5
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- 23. Page 33, Sect. 2 4.7.3.1 The News Coordinator was moved here from Sect. 2.4.8.5. The relocation of the News Coordinator from the JIC to the EOF was made to place the News Coordinator closer to the information necessary to write a timely and accurate news release.
- 24. Page 35, Sect. 2.4.8.5 The News Coordinator was moved from this location to Sect.
2.4.7.3.1.
25.. Page 37, Sect. 2.4.10.2 A brief description of the Site Media Manager position was added here.
- 26. Page 39, Sect. 2.4.10.4, "...activities of the EOF Senior Reactor Operator..." was 1st para changed to "...activities of the EOF Accident Assessment Team, EOF,Senior Reactor Operator..." due to the addition of the EOF Accident Assessment Team.
- 27. Page 39, Step 2.4.10.4.e "Direct the activities of the EOF Accident Assessment Team." was added as a new Step.
- 28. Page 39, Step 2.4.10.4.g "Provide engineering support for the Technical Analysis Director in the TSC, as requested." was added as a new Step.
- 29. Page 39, Sect. 2.4.10 4.1 The EOF Accident Assessment Team was added here. The team was added to the EOF staff to provide the Technical Analysis Manager with a staff of engineers able to assist in any necessary engineering functions in support. of an emergency.
- 30. Page 43, Fig. 2.2-1 The Status Board Plotter positions that previously reported to the Communication Director were deleted from the Figure.
- 31. Page 44, Fig, 2.4-1 The Status Board Plotter positions that previously reported to the Communication Manager in the EOF were deleted from the Figure.
The News Coordinator, previously located in the JIC was moved to the EOF and now reports to the Communications Manager.
The four engineering positions that compose the EOF Accident Assessment Team were added to the EOF Organization Chart.
The Company Spokesperson and Technical Spokesperson positions were designated as Key Positions.
- 32. Page 47, Item 3.3.2.a "...and his staff..." was changed to "...and assigned staff..." as a less gender-specific statement.
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- 33. Page 49, Item 3.5.2.a "...and his staff." was changed to "...and assigned staff." as a less gender-specific statement.
- 34. Page 49, Item 3.6.a "Located at the Civic Center..." was changed to "Located at the Center Plaza Building (11th floor)..."
~
"...media briefing room available for press conferences." was changed to "...media briefing room available for press conferences (located in the Civic Center, also in downtown Raleigh)."
These changes were made due to the relocation of the Joint Information Center.
- 35. Page 50, Step 3.6.h "...by the Corporate Communications Department in Raleigh." was changed to "...by the Site Media Manager." The Site Me'dia Manager is a member of the Harris Nuclear Plant Emergency Response Organization and has the responsibility for initial media interactions prior to JIC activation.
- 36. Page 52, Sect. 3.9.1 The first two "old" paragraphs were replaced with four "new" paragraphs that provide an updated description of the Emergency Response Facility Information System (ERFIS) and the Real Time Information Network (RTIN).
- 37. Page 56, Table 3.1-1 Row "Portable Communications Equipment"; Column "OSC": The
"(a)" was changed to a "" since the OSC emergency equipment kits contain hand held radios.
Footnote (b) was changed from "Stored at the Harris E8 E Center" to "Stored near the Harris E8E Center". The Environmental Monitoring Kits are now located in a locked room by the boat shed approximately 150 meters "downhill" from the Harris E8 EC.
- 38. Page 58, Step 4.2.b "The Emergency Communicator will use the Selective Signaling System phone..." was changed to "The Emergency Communicator will use the electronic Notification Form on RTIN or the Selective Signaling System phone..." due to the addition of a computerized notification form on the RTIN. Upon approval it can be faxed simultaneously to multiple locations.
- 39. Page 59, Step 4.3.g "He may activate the TSC before all his staff..." was changed to "The SEC-TSC may activate the TSC before all of the staff..." as a less gender- specific statement.
"...he must assume their duties..." was changed to "...the SEC-TSC must assume their duties..." as a less gender-specific statement.
- 40. Page 59, Step 4.4.1.a "...by the Accident Assessment Team." was changed to "...by the Accident Assessment Teams in the TSC and EOF." since there are now Accident Assessment Teams in each of these facilities.
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- 41. Page 59, Step 4.4.1.b "The Accident Assessment Team evaluates plant conditions from the Technical Support Center using ERFIS..." was changed to "The Accident Assessment Teams evaluate plant conditions using ERFIS..." since there are now Accident Assessment Teams in the TSC and EOF.
- 42. Page 59, Step 4.4.1.c "Core damage assessment methodology is applied by the Accident Assessment Team..." was changed to "Core damage assessment methodology is applied by the TSC Accident Assessment Team..."
since this team is the only one with a Core Performance Engineer.
- 43. Page 66, Sect. 4.6.3.6.4 "... Apex Volunteer Rescue Squad..." was changed to "...Apex Rescue Squad, Inc...." in the first two paragraphs of this Section as a title change.
- 44. Page 80, Sect. 5.1.1, "He is also responsible..." was changed to "The EP Coordinator is 1st para also responsible..." as a less gender-specific statement.
- 45. Page 86, Sect. 5.3.2, "...or his designee..." was changed to "...or assigned last para designee..." as a less gender-specific statement.
- 46. Page 86, Sect. 5.4.1, "...for the TSC, OSC and EOF..." was changed to "...for the TSC, 1st para OSC, EOF and JIC..." since the JIC now contains an inventoried emergency kit.
- 47. Page 90, Sect. 6.3.2, "...and his staff..." was changed to "...and staff..." as a less 2nd para gender-specific statement.
- 48. Pages 97and 98, Sect. 7.0 References to EPPOS Nos. 2 and 3, and the updated Evacuation Time Estimate analysis were added as Items 7, 8 and 17 respectively. The other references were renumbered accordingly.
- 49. Page 122, Sect. 3.1 '...he has the authority to utilize..." was changed to "...the Governor has the authority to utilize..." as a less gender-specific statement.
"His representatives coordinate..." was changed to "The Governor's representatives coordinate..." as a less gender-specific statement.
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