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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to 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 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 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 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 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 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 ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20195F9971999-06-11011 June 1999 Discusses 990513 Fax Which Forwarded Copy of an Open Ltr to Central New York on Nine Mile One Nuclear Reactor, & Petition to NRC Re Nine Mile Point One Core Shroud Insp, Signed by 187 People ML20195G9661999-06-11011 June 1999 Ack Receipt of Petition Requesting Action Under 10CFR2.206 Sent to W Travers on 990524.Petition Requested That NRC Suspend Operating License Issued to NMP for Nine Mile Point Unit 1.Staff Reviewing Issues & Concerns Raised in Petition ML20207H1021999-06-10010 June 1999 Advises That Info Re Theoretical Basis for Shear & Torsional Spring Constants in Holtec Sf Rack, Submitted in & Affidavit ,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20207G5281999-06-0909 June 1999 Ack Receipt of Expressing Concern for Reactor Core Shroud for Plant,Unit 1.NRC Staff Requested to Conduct Insp of Reactor Shroud,Including Areas Outside Core Shroud Welds & Publicly Disclose Results 1 Wk Before Plant Restart ML20137S9381999-06-0909 June 1999 Ack Receipt of Petition Requesting Action Under 10CFR2.206 Sent to W Travers on 990405.Petition Requested That NRC Take EA Against Util & Senior Nuclear & Corporate Mgt ML20207G2171999-06-0707 June 1999 Forwards SE Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage for Plant,Unit 1 ML20207H3961999-06-0707 June 1999 Informs That NRC NRR Reorganized,Effective 990328. Organization Chart Encl ML20195D5001999-06-0404 June 1999 Discusses NMPC Request That GE-NE-523-B13-01869-113, Assessment of Crack Growth Rates Applicable to Nine Mile Point I Vertical Indications, Rev 0 Be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20207D3141999-05-28028 May 1999 Ack Receipt of 981203,990325 & 0415 Ltrs,Which Presented Several Concerns & Comments Re Operation of Nmp,Plant,Unit 1 During Last Operating Cycle ML20207E8131999-05-28028 May 1999 Responds to Re Concern for Core Shroud Insp Plan for Plant,Unit 1.Insp Results Cannot Be Made Available Before Plant Restarts ML20207A4881999-05-20020 May 1999 Discusses Expressing Concern Re Core Shroud at NMPNS Unit 1 & Indicating Desire to See Further Testing of Any Cracks & Release of Rept to Public Before Unit Restarted ML20207B0171999-05-18018 May 1999 Forwards Safety Evaluation Accepting Rept TR-107285, BWR Vessel & Internals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996 ML20206U5191999-05-17017 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Units 1 & 2 ML20206N6881999-05-12012 May 1999 Forwards Copy of NMP Ltr of 990430,responding to 990325 & 0415 Ltrs Re Core Shroud Evaluations for Plant Unit 1 ML20206M2041999-05-10010 May 1999 Requests Util Provide Written Comments to NRC Addressing Petitioners Expressed Concerns That Involve Licensee Activities.Petitioner Asserts That Util Actions Resulted in Placement of Confidential & Fraudulent Employee Evaluation ML20206K1681999-05-10010 May 1999 Forwards RAI Re 981116 Request for License Amend to Change TSs Re Implementation of Sys for Detection & Suppression of Coupled neutronic/thermal-hydraulic Instabilities in Reactor at Plant,Unit 1.Response Requested by 990621 ML20206L3981999-04-30030 April 1999 Responds to Requesting Addl Info to Either Respond to Apparent Violation,Or Prepare for Predecisional Enforcement Conference Re Apparent Violation of NRC Requirements Identified by OI in Rept 1-98-033 ML20205Q6471999-04-13013 April 1999 Discusses OI Report 1-1998-033.Purpose of Investigation Was to Determine Whether SRO Willfully Violated Conditions of SRO License by Assuming Assistant Station Shift Supervisor Position After Failing Requalification Scenario Evaluation ML20205N0591999-04-12012 April 1999 Forwards RAI Re Which Describes Proposed Core Shroud Repair for Core Shroud Vertical Welds at Plant,Unit 1.Response Requested by 990414 ML20205J3761999-04-0808 April 1999 Final Response to FOIA Request for Documents.App a Records Already Available in PDR IA-99-179, Final Response to FOIA Request for Documents.App a Records Already Available in PDR1999-04-0808 April 1999 Final Response to FOIA Request for Documents.App a Records Already Available in PDR ML20207L0111999-03-11011 March 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Nine Mile Point Nuclear Station,Units 1 & 2 ML20207L5711999-03-0404 March 1999 Informs That Info Submitted with 990203 Application Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR.790 & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20207K3701999-03-0303 March 1999 Forwards NRC PRB Meeting Summary Re Recipient Ltr of 981214, Expressing Concern for Degraded Core Shroud & Vessel Internals at Nine Mile Point Unit 1 ML20203E7281999-02-11011 February 1999 Responds to to W Travers & Submitted Pursuant to 10CFR2.206,requesting That NRC Convene Public Hearing to Consider Revocation of Operating License for Nine Mile Point Nuclear Station,Unit 1.Petition Does Not Meet Criteria ML20203B4671999-02-0808 February 1999 Informs That Licensee 990111 Application & Affidavit Submitting HI-961584,HI-971667,HI-92801 & HI-89330 Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) ML20206R8331999-01-14014 January 1999 Advises That, Licensing Rept for Reracking Nine Mile,Unit 1 Spent Fuel Pool, Will Be Withheld from Public Disclosure, Per 10CFR2.790 ML20199E2701999-01-14014 January 1999 Ltr Contract:Mod 1 to Task Order 235, Review & Evaluation of Nine Mile 2 Nuclear Plant Application for Conversion to Improved TSs - Electrical Sys, Under Contract NRC-03-95-026 ML20206R6161999-01-12012 January 1999 Informs That on 981124 Licensee Submitted Revs to TSs Bases for Plant,Unit 1.Revs Update Listed Bases to Incorporate Design Changes Affecting Reactor Fuel,Reactor Vessel Water Level Instrumentation & Drywell Leak Detection Sys ML20199D2801999-01-12012 January 1999 Informs That on 981204,NMP Submitted Rev to TSs Bases for NMPNS Unit 1.Rev Update Bases for 3.6.2 & 4.6.2 Protective Instrumentation. Forwards Modified Pages for NMP Unit 1 TS Bases for Insertion Into TSs ML20206R0831999-01-0404 January 1999 Informs That Privacy Info Re Investigation Rept Entitled, Results of Independent Team Investigation of Concerns Involving Erosion & Corrosion of Flow Elements, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20198L1971998-12-24024 December 1998 Informs That Based Upon Conclusion That Current Design & Licensing Basis Does Not Credit Containment Overpressure to Ensure Adequate NPSH to Core Spray & Containment Spray Pumps,Nrc Considers GL 97-04 Closed Per 980807 RAI ML20198L3831998-12-23023 December 1998 Forwards Insp Repts 50-220/98-15 & 50-410/98-15 on 980927-1121.No Violations Noted.Notes Challenges Faced by Unit 2 Operators Due to Equipment Performance Problems 1999-09-30
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- .p* #6 'uq 9, UNITED bTATES
<$ NUCLEAR REGULATORY COMMISSION REGloN I
[ 475 ALLENDALE ROAD KING oF PRUSSIA, PENNSYLVANIA 194041415 0,% . . . e ,d'
January 22,1998 i
EA 97 530 Mr. B. Ralph Syhr Executive Vice Pr64ldent and Chief Nucleer Officer >
Niagara Mohawk Power Corporation Nuclear Learning Center 450 Lake Road Oswego, NY 13in8 SUBJECT: NOTICE OF VIOLATION AND PROPOSED IMFOSITION OF CIVIL PENALTY
- $55,000 (NRC Inspection Report Nos. 50-220/97-07;50-410/97-07)
Dear Mr. Sylvia:
This refers to the NRC inspection conducted between August 10 and October 4,1997, at the Nine Mile Point Nuclear Station, the findings of which were discussed during an exit meeting on October 17,1997. During the inspection, the NRC reviewed the circumstances associated with several apparent violations of transportation and radwaste program requirements which occurred at your facilities. The inspection report was sent to you on November 28,1997.
On December 19,1997, a predecisional enforcement conference was held with you and members of your staff to discuss the violations, ibelt causeu, and your corrective ections.
Based on the information developed during the inspection and the Information that you
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provided during the conference, four violations of NRC requirements are being cited and are described in the encloced Notice of Violation and Proposed imposition of Civil Penalty. The circumstances surrounding the .lolations are described in detail in the st,bject inspectior; report. The violations involve four shipments of radioactive materialin a manner contrary to NRC requirements. In the first case, the radiation levels (within an occupied portion of the transport vehicle) were in excess of limits upon arrival of the shipment at its destination. In the second case, the wrong material was shipped such that the radiation levels upon receipt -
were four times higher than expected. In the other two cases, material was shipped to locations different than intended or authorized. Numerous iristances of your staff being Inattentive to details, and not adequately independently verifying information, contributed to l i the three failures within a two month period. .1 With respect to the first violation, on July 24,1997, a package containing two metal samples j h from the Unit 1 core shroud, was sent to BWX Technologies, Inc., Lynchburg, Virginia, and
. . upon receipt of the package at BWX, the dose rate in the normally occupied section of the/) /
vehicle was 2.8 mrem /hr, which is in excess of the regulatory limit of 2 mrem /hr. As you noted at the conference, adequate radiological surveys were not conducted prior to the shipment, in that the technician only surveyed that forward portion of the sleeper cab and did not curvey the rear portion of the ccb which was closest to the source.
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9901290128 990122 PDR ADOCK 03000220 0 PDR ,
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Niegera Mohawk Power Corporation 2 With respect to the second violation, on September 3,1997, a cask was shipped from Unit 4 2 to Molten Metti Technology, Oak Ridge, Tennessee, containing a !!ner that was different than the liner that wailntended ic,r shipmcnt, contrary to the sh!pping manifest. The violation was identified when, during unloading of the cask, Melten Metal Technology recognized that the radiation levels in the area of the liner were approximately four times higher than expected.
Subsequent investigation revealed that one of your radwaste operators inadvertently loaded the wrong liner into the shippir g catk prior to transport. Although each liner had a unique identification number, the radwaste operator did not check the nurober on the linor with the number on the shipment schedule. Rather, he used on!y the storage location number which was in error in addition, although a Unit 1 radiation protection (RP) technician conducted a radiation survey of the cask and sent the results to the Unit 2 RP technician prior to the shiprnent, the Un! 2 RP technician signed the associated shipping manifest authorizing the shipment without reviewing the radiation survey Such a review may have disclosed the higher than expected radiation levels.
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With respect to the third violation, on September 25,1997, a package containing a metel sample removed from a tube sheet in the Unit 1 emergency cooling (EC) condenser, was shipped to a BWX contracts officer in an administrative off!ce n:omplex in Lynchbutg, Virginia, rather than to the intended BWX laboratory. The office complex was not listed on tne material License Certificate for receipt of radiohetiva shipmants. A similar error, which conetitutes the fourth violation, had occurred in May 1995, when a sourco range detector was shipped to the General Electric (GE) f acility in San Jose, California, rather then to the intended GE f acility in Twlasburg, Ohio. The San Jose f acility similarly did not have a lk.anse to receive radioadive material. Although the manifests had been properly prapared in each case, your warehouse personnel nonetheless sent the package to the wrong address. On both occasions, inattention to detail and inadequate verification contributed to these violations.
The NRC recognliss that the actual sofety consequence of these violations was low in each &
case. However, these violations indicate a lack of edequate oversight of the radioactive materials handling and transportation program to t mure appropriate attentiun to detall by staf f
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in implememing the program. In addition, the f act that three of the violatione ccourred during a two-month period, between July 24,1997 and September 26,1997, indicates a poteme for greater safety significance. Therefore, the violations are of a significant regulatory concert)
and are baing classified in the aggregt.te as a Severity Level lli problem in accordance with the
" General Statement of Policy and Procedure icr NRC Enforcement Actions" (Enforcement Policy), NUREG-1600, s
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Niagare Mohawk Power Corporation 3 in accordance with the Enforcement Policy, a base civil penalty in the amount of 655,000 is considered for a Severity Level ill problem. Because your facility has been the subject of escalated enforcement actions within the last 2 years,' the NRC considered whether credit was warranted for / dent /f/catAon and Correct /ve Action in accordance with the civil penalty assessment process in Section VI.B.2 of the Enforcement Policy. No credit was warranted for identification of the problem because the events were identified in each case by the recipients of the packages, and in each case, you had an opportunity to identify these deficiencies sooner, For example, in th. eccc cf the shipment in which dose rates in the c,ccupied portions of the vehicle were found to have exceeded regulatory limits, an adequate survey prior to shipment may have identified the condition. In the case of the wrong liner of resins being dispatched from the site, review of the survey results by the Unit 2 RP technician would have identified the condition. Credit is warranted for your corrective actions which were considered prompt and comprehensive. Your immediate actions included disciplinary .
actions against responsible personnel, ceasing warehouse personnel responsibilities pertaining to shipment of radioactive . materials by transferring those responsibilities to RP, and modifications of radiation survey protocols with resnect to transport vehicles. Your long term corrective actions included planned focus on improving human performance and leadership of the radio)ctive materials har dling and transportation program.
Therefore, to emphasize the importance of appropriate attention to detailin the implemoritation and oversight of the radioactive transportation program, the need for identifying violations, and in recognition of your previous escalated enforcement action, I have been authorized, after consultstion with the Director, Office of Enforcement, to issue the enclosed Notice of Violation and Proposed imposition of Civil Penalty (Notice) in the base amount of $55,000 for the Severity Level 111 problem.
Three other apparent violations set forth in the inspection report, are not being cited, consistent with Section IV of the Policy, because they are of minor significance.
Those apperent violation involve (1) Improperly maintained process control plans involving such issues as references to outdated Titis 49 requirements and training procedures; (2) the f ailure to identify and correct the out of date references in the Process Control Program with respect to the Title 49 requirements; and (3) although your QA department identified during an audit the deficiency in the process control plan with respect to the references to outdated training proceduros, this audit finding was closed prior to the deficiency being corrected.
With respect to the two remaining apparent violations described in the inspection report, the violations involved (1) transporting radioar,tive materialin sh pping containers owned by SEG, Inc., without complying with all quality assuranco requirements as defined by 10 CFR 71, Subpart H; and (2) failure to verify that any vendors you utilized to process waste had a quality assurance program that met NRC requirements per the Unit 1 Process Control Program. .
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At the conference, you disagreed with both of these apparent violations. With respect to the 1 For example, on November 5.1997, a Notice of Violation and Proposed imposition of Chil Penalty in the amount of $50,000 was issued for violations of the maintenance rule (Reference: EA 97-001). In addition, on April 19.1997. a Notice of Violation and Proposed imposition of Civil Penalty in the ancunt of $200,000 was issued for several violations (Reference: EAs 96 474; 96-475: 90494;96-541).
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Niagara Mohawk Power Corporation 4 first issue, you contended that the QA requ'rements only applied to the shipper who was separately licensed. After further review of this matter and consultation of this matter with the Office of Spent Fuel Projects, the NRC maintains that you are responsible for adhering to the QA requirements, unless certain exemptions contained in 10 CFR 71.10 are met. The ,
Statements of Consideration for this rule provide clarification on the rule's intent: "While information mt., be submitted by any interested person to the Commission in support of an application for package approval, it is the licensee who delivers a packege of radioactive material to a carrier who must assure himself and the Commission that the quality assurance -
program, on which approval of the package design is based, has been followed." (42 FR 39364, published 8/4/77). However, in this case, a stated exemption in 10 CFR 71.10 (b)(2)
was met in that the dose rates from the unshielded packages did not exceed 1 rem /hr at 3 meters. Therefore, the apparent violation is withdrawn. With respect to the second issue, you contended at the enforcement conference that this Unit 1 Process Control Program requirement had only been intended fenendors providing processing services on the promises of the Nine Mile Point Nuclear Station. The NRC is still reviewing this item and resolution will be handled by separate correspondence at a later date.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy cf this letter,its enclosure, and your response will be placed in the NRC Public Document Room (PDR).
Sincerely, i
Hu rt . Miller -/*
Regional Administrator
- Docket Nos. 50 220 and 50-410 License Nos. DPR 63 and NPF 89 Enclosure: Notice of Violation and Proposed imposition of Civil Penalty
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Niagam. Mehawk Power Corporation 5 cc w/ encl:
R. Abbott, Vice President & General Manager - Nuclear C. Terry, Vl:.e President- Safety Assessment and Suppert J. Conway, Vice President - L'aciear Engineering K. Dahlberg, Vice President - Nuclear Operations
, D. Wolniak, Manager, Lict.ising 3 J. Warden, New York Consumer Protection Branch
% G. Wilson, Senior Anorney M. Wetterhahn, Winston and Strawn J. Rettberg, New York C ate Electric and Gas Corporation N Eddy, Electric Diviolon, Department of Public Service, State of New York
)onaldssr., Esquire, Assistant Attorney General, New York Department of Law g J. Vinqu.c l'ATS, Inc.
, F. \'alentino, Wealdent, New York State Energy Research and Development Authority
], J. Spath, Program Director, New York Stats Energy Research and Development Authority
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. . b Niagara Mohawk Power Corporation QlSIRIBUTION:
PUBLIC SECY CA LCallan, EDO AThadani. DEDE i JLieberman, OE HMillcr, RI
} ? Davis, OGC SCollins, NRR
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fiZimmerman, NRR Enforcement Coordinators RI, Ril, Rlli, RIV
} BBeecher, GPA/PA GCaputo, 01 DBangart, OEP HBell, OlG' ' '
TMartin, AEOD OE:FA (2 copies) (Also by E-Mali)
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NUDOCS DScrenci, PAO-RI NSheehan, PAO-RI
.($ Nuclear Safety information Center (NSIC)
y Resident inspector - Nine Mile
LTremper, OC CChappell, NMSS l
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18000R
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