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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
[Table view] |
See also: IR 05000220/1992005
Text
ACCELERATED
DISTRIBUTION
DEMONSTRATION
SYSTEM REGULATORy
INFORMATION
DISTRIBUTION
SYSTEM (RIDS)DOCKET 0500022 0500041 NOTES: ACCESSION NBR:9203190321
DOC.DATE: 92/03/12 NOTARIZED:
NO FACIL:50-220
Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha AUTH.NAM" AUTHOR AFFILIATION
SYLVIA,B.R.
Niagara Mohawk Power Corp.RECIP.NAME
RECIPIENT AFFILIATION
Document Control Branch (Document Control Desk)" SUBJECT: Provides response to NRC violations
noted in Insp Repts 50-220/92-05
&50-410/92-05.Corrective
actions: accountability
meeting held w/personnel
directly involved to provide insight into reasons for event.DISTRIBUTION
CODE: IE01D COPIES RECEIVED:LTR
ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice
of Violation Response RECIPIENT ID CODE/NAME PDl-1 PD BRINKMANiD
INTERNAL: ACRS AEOD/DEIIB
DEDRO NRR MORISSEAUiD
NRR/DLPQ/LPEB10
NRR/DREP/PEPB9H
NRR/PMAS/ILRB12
OE DER EXTERNAL: EG&G/BRYCEgJ.H.
NSIC COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME BR INKMAN, D.AEOD AEOD/DSP/TPAB
NRR HARBUCKgC.
NRR/DLPQ/LHFBPT
NRR/DOEA/OEAB
NRR/DST/DIR
8E2 NUDOCS-ABSTRACT
OGC/HDS1 RGN1 FILE 01 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 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 25 ENCL 25
,~I
NIAGARA MOHAWK POWER CORPORATION/NINE
MILE POINT, P.O.BOX 63.LYCOMING, NY 13093/TELEPHONE
(315)349-2882 B.Ralph Sylvia Executive Vice President Nuclear March 12, 1992 NMP1L 0649 United States Nuclear Regulatory
Commission
Document Control Desk Washington, DC 20555 Nine Mile Point Unit 1 Docket No.50-220 DPR-Nine Mile Point.Unit 2 Docket No.50-410 NPF-Gentlemen:
SUBJECT: RESPONSE TO NOTICES OF VIOLATION-NRC COMBINED INSPECTION
REPORT NOS.50-220/92-05
AND 50-410/92-05
Attached is Niagara Mohawk Power Corporation's
response to the Notices of Violation contained in the subject Inspection
Report dated February 11, 1992, (Attachments
1 and 2).We share your concerns addressed in the Inspection
Report, and feel that our corrective
actions have appropriately
addressed the root cause and recurrence
of these violations.
If you have any questions concerning
this matter, please contact me.Very truly yours,/Yr~/jj"L.c.(~r)j:a+C~
B.Ralph Sylvia Executive Vice President-Nuclear BRS/RM/NS/lmc
ATTACHMENTS
xc: Mr.T.T.Martin, Regional Administrator, Region I Mr.W.L.Schmidt, Senior Resident Inspector Mr.R.A.Capra, Director, NRR Mr.D.S.Brinkman, Senior Project Manager, NRR Mr.J.E.Menning, Project Manager, NRR Mr.L.Nicholson, Chief, Reactor Projects, Section 1B Records Management
92031'70321
920312 PDR ADOCK 05000220 PDR
ATTACM4ENT
1 (Page 1 of 3)NIAGARA MOHAWK POWER CORPORATION
NINE MILE POINT UNIT 1 DOCKET NO.50-220 DPR-63 RESPONSE TO NOTICE OF VIOLATION AS CONTAIjMED
IN INSPECTION
REPORT 50-220/92-05
VIOLATION 5 22 2-05 10 CFR 50.36 (a)states in part that each license authorizing
operation of a production
or utilization
facility will include Technical Specifications.
Plant Technical Specification
6.12 states in part that for High Radiation Areas, the area be conspicuously
posted and entrance be controlled
by requiring issuance of a Radiation Work Permit.Any individual
or group of individuals
permitted to enter the area shall be provided with or accompanied
by: a radiation monitoring
device which continuously
indicates radiation dose rates, or;a radiation monitoring
device which continuously
integrates
the radiation dose rate in the area and alarms when a preset integrated
dose is received, or;an individual
qualified in radiation protection,,with
a radiation dose rate monitoring
device.Contrary to the above, on December 16, 1991, three members of the licensee's
Operations
Department
entered the South Condenser Moisture Separator Room on the 277'levation
of the Turbine Building, a posted High Radiation Area, without being on a Radiation Work Permit, and without a dose rate meter, an alarming dosimeter, or accompanied
by a Radiation Protectio'n
technician
with a meter.This is a Severity Level IV violation (Supplement
IV).I.THE REASONS FOR THE I LATION Niagara Mohawk admits to the violation as stated.Operations
personnel are covered by an extended Radiation Work Permit (RWP)if they meet the qualifying
conditions
for such permit.However, one of the prerequisites
to the application
of an extended RWP, obtaining a radiation monitoring
device, was not met.The Station Shift Supervisor (SSS)failed to obtain a radiation monitoring
device or Radiation Protection (RP)support prior to entrance into a High Radiation Area.The root cause for this event is personnel error due to Operations
personnel not following station procedures, which are based upon the above cited Technical Specification.
Specifically, Generation
Administrative
Procedure GAP-RPP-08,"Control of Transient, High, and Locked High Radiation Areas," Section 3.2, was not followed.Operations
personnel did not have monitoring
capability
such as a radiation monitoring
device, an alarming dosimeter, or a person qualified in RP procedures
possessing
a radiation dose rate monitoring
device before entering the locked High Radiation Area.Also, better availability
of portable radiation monitoring
equipment assigned to Operations
in the control room through appropriate
controls would have allowed the proper entry into the locked High Radiation Area.The SSS attempted unsuccessfully
to get a portable radiation monitoring
device before entering the High Radiation Area.
ATTACHMENT
1 (Page 2 of 3)NIAGARA MOHAWK POWER CORPORATION
NINE MILE POINT UNIT 1 DOCKET NO.50-220 DPR-63'ESPONSE TO NOTICE OF VIOLATION AS CONTAINED IN INSPECTION
REPORT 50-220/92-05
I 2.C RRE T E STEP TAKEN AND THE ULTS ACHIE ED Radiological
Occurrence
Reports (ROR)for entering the locked High Radiation Area without a radiation monitoring
device (ROR¹1-91-00-57)
and breaking in the"break-to-enter" key box (ROR¹1-91-00-56)
were generated on December 16, 1991.Immediate c'orrective
actions taken for ROR¹1-91-00-57 were for Radiation Protection
to survey the South Condenser Moisture Separator Room area, document dosimetry readings from Operations
personnel, and verify that doses received were within Reg'ulatory
limits, Niagara Mohawk guidelines, and posted values at the gates.Each person who entered the area recorded an exposure of 10 mrem on an extended RWP log.The follow-up radiation survey identified
a general area radiation exposure rate, in the travel path Operations
took, of less than or equal to 450 mr/hr.Immediate corrective
actions taken for ROR¹1-91-00-56
were to contact Security I&C to replace the key box glass and have Radiation Protection
audit and account for the keys in the"break-to-enter" key box.An accountability
meeting was held with personnel directly involved to provide insight into the reasons for this event.The SSS was coached by Operations
management
regarding compliance
with applicable
procedures
and impact on Technical Specifications.
Also, to provide immediate access to a radiation monitoring
device for Operations
in the control room, a radiation monitoring
device station has been provided in that location.The Assistant SSS has single point accountability
for return and issue of radiation monitoring
devices as part of shift turnover.Additionally, a radiation monitoring
device has been located atop the emergency key box in the SSS office for the exclusive use of the SSS or designee during emergency entry into High Radiation Areas.These actions have alleviated
the radiation monitoring
device availability
problem that contributed
to the violation.
3.CORRE TIVE STEPS TO BE TAKEN TO AVOID FURTHER VIOLATIONS
A Lessons Learned Transmittal
has been generated for the Unit 1 event and has been distributed
to Nuclear Division senior management
personnel, Unit 1 and 2 Operations
and Unit 1 and 2 Radiation Protection.
This will allow Operations
and other branch departments
to understand
the significance
of this violation.
Operations
will also present shift training to Operations
crews to emphasize this event and the Lessons Learned, including the overriding
requirement
to comply with Technical Specification
requirements
and station procedures.
The shift training will also include instructions
that if radiation monitoring
devices become unavailable, Radiation Protection
will be notified and no entry made into a High Radiation Area until applicable
procedures
and requirements
have been fulfilled.
Radiation Protection
personnel will be involved with this shift training.
ATTACHMENT
1 (Page 3 of 3)NIAGARA MOHAWK POWER CORPORATION
NINE MILE POINT UNIT 1 DOCKET NO.50-220 DPR-63 RESPONSE TO NOTICE OF VIOLATION AS CONTAINED IN INSPECTION
REPORT 50-220/92-05
RRE T E STEPS T BE TAKEN TO A ID FURTHER I LATI (cont.)The Radiological
Occurrence
Report process will be replaced by the Deviation/Event
Report (DER)process to allow for a higher level and more immediate management
review.The DER procedure is being revised to provide a process which will allow dissemination
of events, such as the Unit 2 High Radiation Area entry, between both units in a more timely manner.This procedure revision will be completed by March 31, 1992, with training to be completed by April 30, 1992.4.DATE HE LL MPLIANCE WAS A HIEVED Full compliance
was achieved on December 16, 1991, when doses received by Operations
were determined
and found to be within regulatory
limits after surveys were performed by Radiation Protection.
ATTACHMENT
2.(Page 1 of 3)NIAGARA MOHAWK POWER CORPORATION
NINE MILE POINT UNIT 2 DOCKET NO.50-410.NPF-69 RESPONSE TO NOTICE OF VIOLATION AS CONTAINED IN INSPECTION
REPORT 50-410/92-05
VIOL ATIO 5 1-05 10,CFR 50.36 (a)states in part that each license authorizing
operation of a production
or utilization
facility will include Technical Specifications.
Plant Technical Specification
6.12 states in part that for High Radiation Areas, the area be conspicuously
posted and entrance be controlled
by.requiring issuance of a Radiation'ork
Permit.Any individual
or group of individuals
permitted to enter the area shall be provided with or accompanied
by: a radiation monitoring
device which continuously
indicates radiation dose rates, or;a radiation monitoring
device which continuously
integrates
the radiation dose rate in the area and alarms when a preset integrated
dose is received, or;an individual
qualified in radiation protection, with a radiation dose rate monitoring
device.Contrary to the above, on October 23, 1991, five members of the licensee's
Operations
Department.entered the Northeast and Northwest Condenser Area on the 277'levation
of the Turbine Building, a posted High Radiation Area, without being on a Radiation Work Permit, and without a dose rate meter, an alarming dosimeter, or accompanied
by a radiation"protection
technician
with a meter.This is a Severity Level IV violation (Supplement
IV).1.THE REASONS FOR THE VIOLATION Five Operations
personnel entered the Northeast and Northwest Condenser area on the 277'levation
of the Turbine Building on October 23, 1991, in response to a loss of condenser vacuum condition.
This area is a locked High Radiation Area and entry is controlled
by procedure S-RAP-RPP-0801,"High Radiation Area Monitoring
and Control" (formerly S-RPIP-3.8).
The Operations
personnel who entered the area are qualified as self monitors, and as such were authorized
to enter under an Extended Radiation Work Permit (RWP)as provided for in Administrative
Procedure AP-3.3.2,"Radiation
Work Permit." One member of the team entering this area was carrying a radiation monitoring
device as required by Technical Specifications
and Radiation Protection
procedures.
The condenser bay entry was monitored via a remote camera monitor by a Radiation Protection
Supervisor
in the area.The operator carrying the radiation monitoring
device became involved in responding
to the loss of vacuum and failed to devote the proper attention to performing
radiation surveys.The Radiation Protection
Supervisor
determined
that an adequate radiation survey was not performed by the operator carrying the radiation monitoring
device, nor did he inform the other operators" of radiation levels.The reason for the inadequate
survey has been determined
to be a personnel error due to a failure to follow procedures.
Upon exiting the High Radiation Area, personnel completed the required log entries for the Extended RWP.
ATTACHMENT
2 (Page 2 of 3)NIAGARA MOHAWK POWER CORPORATION'INE
MILE POINT UNIT 2 DOCKET NO.50-410 NPF-69 RESPONSE TO NOTICE OF VIOLATION AS CONTAINED IN INSPECTION
REPORT 50-410/92-05
2.RRE T E TEPS TAKE D THE RES LT A HIE ED The immediate corrective
actions were to have Radiation Protection
personnel verify radiation levels in the area and verify that doses received were within Regulatory
limits, Niagara Mohawk guidelines
and values posted at the gates.All personnel entering the area recorded an exposure of less than or equal to 5 mrem on an extended RWP log.The Plant Manager, Operations
Manager, and Radiation Protection
Manager, were all notified of the event.A Radiological
Occurrence
Report'(ROR)
was written to track and document the event and any corrective
actions generated.
An accountability
meeting was held with all personnel directly involved, to provide insight into the~~~~reasons for the event.Participants
discussed the procedural
requirements
for and the importance
of personnel radiation monitoring
in High Radiation Areas.In addition, they discussed the need for Operations
and Radiation Protection
to work as a team to promote safer plant operations.
Further, the control of keys that allow entry into locked High Radiation Areas (XH Keys)has been shifted from the Station Shift Supervisor (SSS)to the Radiation, Protection
office.This will facilitate
Operations
personnel coordination
with Radiation-Protection
technicians
during response to plant transients.
An emergency XH Key has been staged in the SSS office along with an emergency use only radiation monitoring
device.These may be used if a condition were to develop where immediate access to a High Radiation Area is required.3.CORRE TIVE STEPS TO BE TAKEN TO AVOID THER VIOLATI NS The Operations
Manager will discuss with Operations
personnel the Radiation Protection
requirements
for operators to enter a High Radiation Area, stressing that during an emergency, the preferred response is to involve Radiation Protection
personnel if available.
He will also stress that when utilizing the self-monitoring
technique, personnel will determine radiation levels in all accessed areas, and ensure all other personriel
in the area are made aware of these radiation levels.Operations
Training will be integrating
Radiation Protection
interfaces
into appropriate
training and evaluated simulator scenarios.
This will promote teamwork that allows operators to focus on~~~~~~responding
to plant transients
and Radiation Protection
technicians
to supply the appropriate
radiological
monitoring.
This interface, once internalized, will be a practiced emergency response and an evaluated portion of the simulator scenario.
ETTA HMBNT 2 (Page 3 of 3)NIAGARA MOHAWK POWER CORPORATION
NINE MILE POINT UNIT 2 DOCKET NO.50-410 NPF-69 RESPONSE TO NOTICE OF VIOLATION AS CONTAINED IN INSPECTION
REPORT 50-410/92-05.
4.DATE WHE FULL COMPLIANCE
AS ACHIEVED Full compliance
was achieved on October 23, 1991, when doses received by Operations
were" determined
to be within Regulatory
limits after surveys performed by Radiation Protection.