|
---|
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] |
Text
.g _4MAY-25-99 14ED 10 3 317
~ . - o, .
4 i
1 l May 24,1999. i Drl William Trdvers L !
. Executive Dhector of Operations i United States Nuclear Regulatory Commission
- Washington,DC 20555.
t
' Dear Mr. *Invers; As provided under 10 CFR 2.206, Citir. ens Awareness Network, Coalition on West Valley Nuclear Waste, Environmen-tal Advocates Greens of Orester Syracuse, Nuclear Information and Resource Service, Oswego Valley Peace and .l Justice, Siesta Club (froquois Group), 'tudent Environmental Action Coalition (SU/ SUN %E5P), Syracuse Anti- ,
. Nuclear EITort, Symcuse Peace Council, and Dd Steven Penn, Ph.D., pedtion the U.S. Nuclear Regulatory Commis.
! sion to suspend the operadng license of Niagara Mohawk Power Corporatiun (NMPC) for the Nine Mile Point Unit l One (NMP1) nuclear power generating station. The petition calls for suspension of the license until such time as '
' NMPC teleases the most recent inspectiota data on the plant's core shroud and an adequate public review of the plant's safety is accomphshed because of the following new and unreviewed information and safety concerns:
- 1) The public canact rely upon NMPC to accurately perfbra the data analysis necessary to calculate the extent and rate of cracking in the cure shuvud. As demonstrated in two leuers to the NRC by Dr. Steven Penn (December ,
,14,1998 and March 17,1999) the research studies commissioned by Niagara Mohawk to estimate crack growth tales ,
- (COR) in the core shroud were replete with procedural errors including selective omissiott of data and calibration
, inconsistencies in electropotentiokinetic reactivity (EPR) measurements used in calculations of the CGR. In many ;
- instances, the studies neglected proper error analysis, m@senting the accuracy with which the reported CGR was :
'known and against which new data must be checked. While we acknowledge that the issue of estimating the CGR is !
, - less relevant given the recent' direct measurements of the CGR, the public still has no assurance that the calculations
~
and research being performed by NMPC and its research contractors is being conducted in an accurate arid unbiased j
manner 1.ingering public doubt over the research practices of NMPC necessitates a public review of the inspection .
data to assess the true safety status of the core shroud. Further, the NRC has not' evaluated Dr. Penn's letters, and has .
stated it does not plan to review Dr. Penn's second letter until Fall 1999; NRC's refusal to assess these analyses poses ;
an 12.,&:.4 safety issue. The most recent inspection data must be properly analyzed and publicly reviewedprior to any potential restart in order to assess the current state of the core shroud material and the sgety concer?s of contin-urd operation ofNMPl.
' 2) NMPC and NRC bave reported in the May 1999 laspection that cap screws instaBed as a Inodification to the core shroud ir 1997 suffered intergranular stress corrosion cracklag (AGSCCh resulting in the fracture of at j
' least one of t", e cap screws. He cap screws were part of bow spring mechanisms designed to prevent tie rods from ;
. rubbing against the cote shroud. With the fallute of one of the tie rods between 1995 and 1997 due to improper i
- insta11abiand the inferior material chosen for the cap screws, NMPC's record on installing repairs to the core shroud, ,
and NRC's record on approving and overseeing them, indicate: (1) that NMPC's designs warrant in-depth review by j c the public: and (2) that the implementation of repairs requires closer scrutiny to assure safe operation of NMP1. The i fact that the material chosen by NMPC and approved by NRC for the cap screws was so susceptible to IGSCC, the same mechanism by which the core shroud is believed to be deterioriating, indicates a shocking lack of forethought on l
the part of the licansee and a dismaying inadequacy of oversight by the regulator. This new data concerning the cap
{
screws, widch has come to light since NRC approved the repair designfor V9 and V-10, raises sfety-signhicant ;
quesdons about the credibility ofNRC's approval of the vertical weld repair design, and necessitates afurtherpublic review of the design's adequacy in order to determine the level of sqfety before restart ofNMP1.
- 3) Data from the May 7999 laspection of the NMP1 core shroud is I.cw and NRC staff review will not occur I prior to restart of the reactor on the current refueling outage schedule. his data constitutes new information on a !
significant safety issue, and permitting restart of the reactor before the data is reviewed and a safety evaluation issued ,
I L eanstitutes an unteviewed safety issue. This inspection was initially scheduled for a mid-cycle outage afler 10,600 i 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of operadng cycle 13 (approximately November 1998). He mid-cycle outage was required by NRC prior to '
restart in 1997 because of the unprecedeated extent of deterioration of the core shroud.- Analysis of the inspection ;
data 3 and a safety evaluation were necessary to determine (1) the extent of crackmg,(2) to assess the safety consequences ; oI continued opersion of NMP1 with a severely cracked core shroud, and (3) to begin collecting emptrical data on IGSCC i and core shroud deterioration as part of an industry directive to monitor the age-related degradation of boiling water 3
- j reactor internals.1 M0 990524- R However,NRC postponed intreim at NMPC's requ L'r PT2 i
.f d skD EDO --G19990268 j
MAY-25-95,g D_03* 8 PM P.02
,,,, y V@T l
- 11 cracks would not apptoach the next safety-significant threshold until the end of the operating cycle. The NRC staff's I
letter tu NMPC approvi-g postponement of the mid-cycle inspection states: "This approval of NMPC's request . l does not affect the NRC staff's earlier letter and SE dated May 8,1997." The approval of postponement only deferred !
the necessary review of the status and level of safety of the core sl roud. Therefore, a review of the most recent l
inspection data to assess the current extent of cracking in the core shroud and a safety evaluation based on that ;
assessment are necessary before the reactor is allowed to restart, as would have been the case during the tntd-cycle ,
i inspection. $ubsequent NRC approval of an unprecedented and unproven repair designfor vertical welds tssued prior to the inspection and review of the May 1999 data, does not preempt the previously determined need to assess the ccrual extent of cracking in the vertical welds and the structuralintegrtry of the core shroud.
- 4) NMPC has informed NRC that a public review of the core shroud inspection data during this refueling ,
outage would place an " undue regulatory burden *' on NMPC management and posalbly compromise safety at NMP1. NMPC management acknowledged that they have insufficient resources to respond to the regulatory process l and the pubhc on issues relevant to safe 0peration of NMPl. This fact in itself constitutes new information and an !
unreviewed safety issue relating to the core shroud inspection and implementation of the proposed core shmud repair.
NMPC's record during the last 2 operating cycles and during this refueling outage do not warrant that level of trust.
Moreover, there is precedent for increased concern about NMPC's ability to self. assess its safety performance at NMPl. In a civil penaky issued agilnst NMPC on November 6,1997. NRC cited "significant regulatory concern" with Nh@C for violations at NMPl: the panel investigating the violations discovered, among other things, *inad- ,
equate management oversight" and " fall [ure] to monitor the effcetiveness of maintenance activitics for safety-signin- )
cant plant equipment in order to minimize the likelihood of failure and of events caused by the lack of effective i maintenance." These are issues directly pertinent to the failure of the tie rod installation (1995), faulty stesign of the bow spring modification (1997), flawed smdies on core shroud boat samples (1998), postponement of mid-cylcio inspection (1998), and miscalibration of instruments for vertical weld inspection (May 1999). Further; the core Shroud ;
r1 NMP1 is known to be "the worst case of cracking in the nuclear industry" (Union of Concerned Scientists). 'Ihe ;
question of" undue regulatory burden"is not relevant with a precedent-setting case of reactor degradation, but rather e requires the strictest regulatory oversight and a full public review. Finally, if the licensee cannot guarantee that l compliance with regulatory requirements can be met while protecting the public heahh and safety, this constitutes a :
viointion of NMPC's operating license. Therefore. NRC should suspend NMPC's operating ItcenseforNMP1 untt!
there has been a public review of the May 1999 inspection data and the proposed repair to V-9 and V-10 and the safety l of continued operation of the reactor can be determined. Postponing restart ofNMP1 would eliminate the issue of
" regulatory burden" for NMPC management and ensure that the safety signylcant work being conducted during this ~;
refketing outage is properly reviewed.
Therefore, for all of the above stated contenttons, the Petitioners call upon the NRC to suspend NMPC's operating license for NMP1 by postponing the scheduled restart date until such time as a public meeting can be held in Oswego , l County to review the most recent core shroud inspeedon data and the nroposed repair design to core shroud welds V-9 and V 10. !
Sincerely, Tim Judson Syracuse Peace Council 924 Durnet Ave.
Syracuse,NY 13203 Deborah Katz Executive Dimetor Citizens Awareness Network PO Box ft3 Shelbume Falls. MA 01379 Kyle Rabin Envirunmental Advocates 353 Ilamilton Street Albany. NY 12210 l
l
f;, .,
't1;tV-25-99 WED C3310 PM p,es
- l. i
[.
Howar(Hawkins Orcens of Greater Syracum -
PaulOunter Director, Reecent Watchdog Project . .
Nuclear Information & Resout cc Scryicc 142416th Street NW, M04 l
j Washin5 ton,DC 20036 j
. lleidi Siegfried -
Oswego %11cy Peace & Justice Martha Loew
~'
President
- Sierra Club, Iroquels Omup -
David Radley Student Environmental Action Coalition Wendy Harris -
Simon Morrin .
Syracuse Anti-Nuclear Esort
Syracuse, NY 13203 Dr. Steven Penn, Ph.D.
Department of Physics i i
Syracus UniYClaity l
(-
l l
l i
l 6-B