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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999 Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20209B2951999-06-22022 June 1999 Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226 ML20196E9231999-06-21021 June 1999 Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor ML18040A3651999-06-0707 June 1999 Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission ML18040A3661999-06-0404 June 1999 Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr ML20195C9751999-06-0101 June 1999 Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods ML20195C9601999-05-28028 May 1999 Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr ML20207F1811999-05-24024 May 1999 Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns ML20195B1861999-05-21021 May 1999 Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl ML20207D1541999-05-21021 May 1999 Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld ML20207D5331999-05-21021 May 1999 Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790 ML20206S2621999-05-16016 May 1999 Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date ML20195D5911999-05-13013 May 1999 Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411 ML20206P1981999-05-11011 May 1999 Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2 ML20206R6941999-05-10010 May 1999 Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate ML20206N0291999-05-0707 May 1999 Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28 ML20206G8121999-04-30030 April 1999 Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083 ML20206F7731999-04-22022 April 1999 Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2 1999-09-07
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ACCELERATED DOCUMENT DISTRIBUTION SYSTEM
'i REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CCES)ION NBR:9309080163 DOC.DATE: 93/09/03 NOTARIZED: NO DOCKET CIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha 05000410 UTH.NAME AUTHOR AFFILIATION SYLVIA,B.R. Niagara Mohawk Power Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 930803 ltr re violations noted in insp rept 50-410/93-14.Corrective actions:util initiated plan for restructuring operating procedures by developing special operating procedures category. D DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 1 MENNINGiJ 1 1 D INTERNAL: ACRS 2 2 AEOD/DEIB 1 1 AEOD/DSP/ROAB 1 1 AEOD/DSP/TPAB 1 1 D AEOD/TTC 1 1 DEDRO 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PEPB 1 1 NRR/PMAS/ILPB1 1 1 NRR/PMAS/ILPB2 1 1 NUDOCS-ABSTRACT 1 1 OE D 1 1 OGC/HDS1 1 1 EG FILE 02 1 1 RES/HFB 1 1 GNl=F E 01 1 1 EXTERNAL EGGG/BRYCE g J H ~ 1 1 NRC PDR 1 1 NSIC 1 1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DI"SV, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24
7 NlASAPA V MOHAWK NIAGARAMOHAWKPOWER CORPORATION/NINE MILE POINT, P.O. BOX 63, LYCQMING, NY 13093/TELEPHONE (315) 349-2882 B. Ralph Sylvia Executive Vice President Nuclear September 3, 1993 NMP89316 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit 2 Docket No. 50-410 NPF-Gentlemen:
SUBJECT:
REPLY TO NOTICE OF VIOL4TION- NRC INSPECTION REPORT 50-410/93-14 Enclosed is Niagara Mohawk Power Corporation's reply to the Notice of Violation contained in the subject Inspection Report dated August 3, 1993. The discussion, as requested by the Inspection Report, of Niagara Mohawk's position with respect to compliance with ANSI/ANS 3.2-1982, Section
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5.3.9.1 is also enclosed. This letter also provides additional information, as requested, regarding the
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quality of the Nine Mile Point Unit 2 Operating Procedures.
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Viola o se We believe that the response to the Notice of Violation (Enclosure 1) appropriately addresses the causes of this violation and presents appropriate corrective actions which will prevent recurrence.
-Nor/na Pr c r F Enclosure 2 provides Niagara Mohawk's position with respect to the issue of off-normal procedure format. The Inspection Report indicated that our resolution of the issue regarding procedure format has not been timely. We acknowledge that, until this inspection, we misinterpreted the focus of this issue, believing the concern to be the quality of selected Operating Procedures, which we were addressing by upgrading the Electrical Operating Procedures and enhancing our procedure preparation processes. We discussed our position regarding this issue with the NRC Region Staff during the on-site inspections covered by this report.
Furthermore, as discussed in Enclosure 2, Niagara Mohawk has initiated a plan for a significant restructuring of Unit 2 Operating Procedures (OPs) by developing procedures in a new category, Special Operating Procedures (SOPs). The Unit 2 SOPs will incorporate, as appropriate, the attributes of symptoms, automatic actions, immediate and subsequent operator actions. In an August 6, 1993 letter to the Regional Administrator, Mr. T. Martin, we described this plan and provided our implementation schedule. As discussed in our letter, implementation of this plan will be complete by July 31, 1994 in accordance with a structured schedule which will allow adequate time for verification and training.
9309080163 930903 PDR ADOCK 050004io 8 PDR
Page 2 This Inspection Report noted that several events in the potential emergency category were not being addressed by our proposed SOPs. These events were not included in the SOP plan described in our
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August 6, 1993 letter. Niagara Mohawk has since decided to expand the scope of our SOP
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development effort to address the events listed in Regulatory Guide 1.33, Appendix A, Section 6, applicable to the Nine Mile Point Unit 2 design except for a very limited number of events which are more appropriately addressed by our symptom based Emergency Operating Procedures or our Emergency Plan Procedures. The events identified in the Inspection Report will be incorporated into the SOPs within the time frame identified in our August 6, 1993 letter. Niagara Mohawk will revise the USAR to clearly describe our procedure hierarchy and our commitments to ANSI/ANS-3.2 1982.
0 erato Pr e ure ua i The Inspection Report notes that there appears to be a persistent problem with the quality of Unit 2 Operating Procedures (OPs) and expresses concern that our upgrade program may not be effective in dealing with this problem. Our evaluation of the violation indicates a weakness in the implementation of our procedure preparation and review process. We will establish additional management controls as described in Enclosure 1 in order to improve the effectiveness of the Unit 2 Operating Procedure upgrade activities.
Over 2,900 site administrative and technical procedures have been upgraded, however, the majority of the Unit 2 OPs were not included. We are continuing with our longer term effort to upgrade the remaining OPs.
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Nine Mile Point Unit 2 experience indicates that continued attention to improvement of the OPs is
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appropriate. Niagara Mohawk believes, however, that the improvement in recent operating
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performance demonstrates the operators'bility to effectively use the currently existing procedures.
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$ ummaiy Niagara Mohawk believes that the SOP development plan discussed above and the corrective actions discussed in Enclosure 1 will significantly enhance the Unit 2 procedure program.
If you have any questions concerning these matters, please contact me, Very truly yours, B. Ralph Sylvia Exec. Vice President - Nuclear BRS/AFZ/Imc Enclosures XC: Mr. T. T. Martin, Regional Administrator, Region I Mr. W. L. Schmidt, Senior Resident Inspector Mr. R. A. Capra, Director, Project Directorate I-1 Mr. J. E. Menning, Project Manager, NRR Records Management
E~NCL CE NIAGARA MOHAWKPOWER CORPORATION NINE MILE POINT UNIT 2 DOCKET NO. 50-410 NPF49 "REPLY TO NOTICE OF VIOLATION,"AS CONTAINED IN INSPECTION REPORT 50410/93-14 VIOL4TION -410 3-14-01 10 CFR 50 Appendix B, Criterion VI, on document control requires in part that measures shall assure that documents, such as procedures, including changes, are reviewed for adequacy.
Contrary to the above, as of July 8, 1993, an operating procedure change was not reviewed for adequacy in that OP-71D would have permitted both logic trains of the Automatic Depressurization System to be made inoperable during restoration of one power supply train.
This is a Severity Level IV violation (Supplement 1).
- 1. THE REA I R THE VI L4TI N A limited revision to procedure N2-OP-72 (OP-72 ) was written in August 1992 to address a loss of power to loads supplied from 2VBA-UPS2B (UPS2B). This procedure was prepared to support a corrective maintenance activity performed in September 1992. The steps for restoring power to the UPS2B loads were extracted from procedure N2-PM-13, which had been previously demonstrated to be effective for de-energizing and restoring Division II power supplies.
While developing the limited revision to OP-72, the provisions for the use of the Automatic Depressurization System (ADS) inhibit switches was erroneously added as an alternative to opening breaker 2BYS*PNL201B-10. This error was not identified by the Qualified Technical Reviewer. Subsequently, procedure N2-OP-71D (OP-71D) was developed as part of the Electrical OP upgrade program. The section on restoring power to UPS2B loads was transferred from OP-72 to OP-71D when the upgraded Electrical OPs were implemented. OP-71D received a cross-disciplinary and technical review prior to the addition of the section on restoring power to UPS2B loads. The review by the Qualified Technical Reviewer, after incorporating this section from OP-72, did not identify the error.
The primary cause for the incorrect procedure has been determined to be inadequate managerial methods in that procedure program requirements and management expectations regarding procedure preparation and review activities were not well understood by the individuals involved.
In addition, management oversight was less than adequate in identifying that these expectations were not well understood.
Page 1 of 3
0 The procedure section addressing the restoration of UPS2B loads has never been used.
Furthermore, had this procedure been used, the internal inconsistency resulting from the erroneous step would in all likelihood have resulted in an operator decision to stop the procedure and to initiate action to resolve the discrepancy. Additionally, operation of the ADS inhibit switches would have initiated Control Room front panel annunciators, alerting the operating shift of the need to take action to restore ADS operability.
- 2. RRE TIVE ACTI N TAKEN AND THE RE LT A HIEVED An immediate Procedure Change Evaluation (PCE) was issued in response to the Inspector identified procedure deficiency. This PCE removed the option to use the ADS switches during the performance of this procedure.
Deviation Event Report (DER) ¹2-93-1611 was issued on July 8, 1993, to document the evaluation of the cause of this procedure deficiency and corrective actions.
A sample of previously revised Operations Department procedures is being reviewed for technical accuracy. The results of that review will be presented to the Site Operations Review Committee (SORC) for consideration in determining whether additional corrective actions are warranted. A sample of one procedure per Qualified Technical Reviewer will be reviewed in the initial sample.
At this time eight upgraded Operations Department procedures have been reviewed with no errors in technical content identified. These reviews did identify some editorial errors.
- 3. RRE TIVE ACTION T BE TAKEN TO AV ID FURTHER VIOLATI N Niagara Mohawk will continue upgrading our Unit 2 OPs on a prioritized basis. Senior Operations Department Supervision (General Supervisor level or higher) will review selected revised procedures prior to publication with the procedure author and Qualified Technical Reviewer to ensure the procedure preparation and review activities were performed in full compliance with program requirements and management expectations.
Operations Line Management will reinforce, with procedure authors and Qualified Technical Reviewers, the expectations and requirements for proper procedure preparation and Technical Review activities.
The Operations Branch Manager will meet with all Operations Department personnel to reinforce Nuclear Division Standards of Performance and expectations regarding the emphasis on safety and quality of work having priority above schedule adherence as well as reinforcing management expectations on procedure preparation and review activities.
Training to emphasize the roles and responsibilities of Technical Reviewers will be included in the Technical Staff and Reactor Operator continued training programs.
Augmented Quality Assurance surveillance activities will be utilized to monitor the effectiveness of future Operations Department procedure revision activities. These surveillance activity results will be fed back to Operations Department Management to gauge the effectiveness of the corrective actions taken.
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- 4. DATE WHEN FULL C MPLIANCE WAS ACHIEVED Full compliance was achieved on July 8, 1993, when an immediate PCE was issued to remove the option to use the ADS switch during the performance of this procedure.
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ENCLOSURE 2 NIAGARA MOHAWKPOWER CORPORATION NINE MILE POINT UNIT 2 DOCKET NO. 50-410 NPF49 NIA ARA MOHAWKPOSITION ON F RMAT OF FF-NORMAL PR CEDUR
~fN DUC N Based upon the comments in Inspection Report 93-14, it appears that Niagara Mohawk and the NRC Staff have different positions regarding the required format for "off-normal" procedures.
This Enclosure discusses Niagara Mohawk's position on this issue.
~C*N A Niagara Mohawk believes that the current Unit 2 procedure program is in compliance with ANS 3.2-1982. In Section 13.5 of the USAR, Niagara Mohawk commits to follow Section 5.3 of ANS 3.2-1982. In subsequent subsections, however, we note that our EOPs will follow Rev. 4 of the BWROG format for symptom based EOPs. This position is consistent with footnote 13 to Section 5.3.9.1 of ANS 3.2.
ANS 3.2 Section 5.3.9.2, which requires procedures to respond to potential emergencies, does not specify a particular format. At the time the Unit 2 OPs were initially prepared, they followed the general format, style and content then being used by the existing Unit 1 procedures.
Furthermore, Niagara Mohawk specifically decided to incorporate off-normal actions within the OPs to minimize the number of procedures that operators would need to reference. The potential emergencies discussed in Section 5.3.9.2 and Appendix A10 of ANS 3.2 are covered by the off-normal section of our OPs or by other approved site procedures.
Subsequent experience, however, has demonstrated the desirability of having stand alone procedures for responding to selected operating events. As discussed below, we have developed a comprehensive plan to develop these stand alone procedures and provided this information to the NRC in our August 6, 1993, letter to the Region I Administrator.
FF-N RMAL PR ED RE PLAN A D TAT Niagara Mohawk's plan is to develop a new set of Unit 2 procedures called Special Operating Procedures, SOPs, which will cover events of potential emergency. As these SOPs are prepared, the appropriate off-normal sections of our current OPs will be modified.
We are developing a writer's guide for SOPs and the Operations Staff is developing the format best suited for SOPs. In some cases, this may result in the use of flow-chart type procedures, Page 1 of 2
similar to the EOPs. Regardless of the format, the attributes of symptoms, automatic actions, immediate and subsequent operator actions, will be incorporated in the individual procedures.
Incorporating these attributes may not necessarily involve specific procedure sections with the above headings. For example, automatic actions may be incorporated as a verification step at the appropriate time within the immediate or subsequent operator action sections. The USAR will be revised to reflect the revised procedure program.
$ UMMARY Niagara Mohawk believes that the existing Unit 2 procedure program is in compliance with the licensing basis, however, Niagara Mohawk will revise the USAR to more clearly and specifically describe our procedure program and commitment to ANS 3.2. We have also concluded that a set of Special Operating Procedures would be an enhancement to our program and have developed a plan to implement that approach.
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