Forwards Proposed Enforcement Action Against Util for Violations Involving Matl False Statements Re Tech SpecsML20140H873 |
Person / Time |
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Site: |
Grand Gulf, 05000000 |
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Issue date: |
03/22/1985 |
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From: |
Kammerer C NRC OFFICE OF CONGRESSIONAL AFFAIRS (OCA) |
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To: |
Cochran T, Dowdy W, Markey E, Simpson A, Stennis J, Udall M HOUSE OF REP., SENATE, SENATE, ENVIRONMENT & PUBLIC WORKS |
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Shared Package |
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ML20140C961 |
List: ... further results |
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References |
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FOIA-85-478 850822, EA-84-075, EA-84-75, NUDOCS 8510230175 |
Download: ML20140H873 (1) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended 1999-09-09
[Table view] Category:NRC TO U.S. CONGRESS
MONTHYEARML20248F0321989-09-14014 September 1989 Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl ML20247L2401989-09-13013 September 1989 Responds to Re K Barnes Concerns Regarding Safety at Plants.Advises That to Date,Releases from Plants Remain Well within Accepted Stds ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246B6591989-08-18018 August 1989 Forwards 40th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants from Apr-June 1989. Lilco Shareholders Voted to Accept Terms That Provide for Sale of Plant to State of Ny ML20247C0111989-05-12012 May 1989 Forwards NRC Quarterly Status Rept to Congress Covering First Quarter 1989.On 890303,NRC Dismissed Shoreham Intervenors from Licensing Proceeding for Misconduct During Proceeding.W/O Encl ML20247C3541989-03-17017 March 1989 Forwards Detailed Info Re Status of Implementation of TMI Action Plan Items at Listed Plants.Small Number of Action Items Still Need Resolution ML20236D4761989-03-0909 March 1989 Forwards NRC 38th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1988 ML20195G8521988-11-10010 November 1988 Forwards Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Jul-Sept 1988.Inability of Commission to Forecast Licensing Schedule for Shoreham & Seabrook Noted ML20245D6531988-09-14014 September 1988 Responds to Re Requested Response to Concerns of H Nickerson Long Work Hrs for Personnel at Various Central Illinois Nuclear Generating Plants.Related Info Encl ML20245D5811988-08-22022 August 1988 Forwards 36th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants Covering Apr-June 1988.Licensing Schedule Cannot Be Realistically Forecast Due to Unresolved Emergency Preparedness Issues ML20207G2211988-08-15015 August 1988 Responds to Requesting Response to P Birnie Re Event at LaSalle Involving Recirculation Pump. NRC Response to P Birnie Identical to Ltr Addressed to Recipient ML20195G6681988-06-10010 June 1988 Provides Info in Response to Rl Spaulding Re Problems Associated W/Full Power Operation Authorization & Plant Shutdown.Plants Must Demonstrate Satisfactory Solutions to Issues Before Restart or Full Power Operation ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20148E0961988-02-29029 February 1988 Forwards Quarterly Rept Covering Fourth Quarter of 1987,in Response to House Rept 97-850 ML20196G9691988-02-29029 February 1988 Forwards 34th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1987. Commission Unable to Forecast Licensing Schedule for Shoreham & Seabrook Because of Unresolved Issues ML20195J6611988-01-20020 January 1988 Responds to Concerns Raised in Re Stainless Steel Matl Designated as E-Brite 26-1.Actions Taken to Address Allegation That E-Brite 26-1 Unsuitable for Use in Nuclear Power Plants Listed ML20236K8761987-11-0303 November 1987 Responds to Sztaba Expressing Concerns Re Safe Operation of State of CT Nuclear Power Plants.Plants in State Not Rated Among Most Troublesome in Nation.Licensee Performance Monitored in Publicly Available SALP Repts ML20236G1831987-10-27027 October 1987 Responds to Re Proposed Rule 10CFR50 & Congressional Ltrs Received on Morning of 871022 Meeting. Commission Stands Behind Declaring Process for Proposed Rule Open ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20235J5351987-09-28028 September 1987 Responds to Constituent Tf Gross Ltr Supporting Ucs 870210 10CFR2.206 Petition to Suspend OLs & CPs of Any Util Operating or Bldg Nuclear Power Reactors Designed by B&W,Per 870803 Request.Nrc Statements Re Plants Discussed ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20215K5981987-06-10010 June 1987 Responds to 870508 Request for Testimony at 870514 Hearing on External Influence on NRC Adjudicatory Procedures in Shoreham Proceeding.Index of Pertinent Documents Encl ML20215H9431987-06-0505 June 1987 Advises That Review of B&W Designed Nuclear Power Plants Will Not Satisfactorily Address Safety Issues Associated W/ B&W Design.Supports Efforts to Create Independent Safety Review Board ML20214J5261987-05-15015 May 1987 Responds to Recipient Expressing Support for NRC Shut Down of Peach Bottom Atomic Power Station & Concern Re Emergency Planning Issues at Seabrook.Commission Unable to Comment on Issues Before Commission or Adjudicatory Boards ML20214P8401987-05-15015 May 1987 Responds to Rj Mrazek Re Util Request to Operate Facility at 25% Power.Commission Will Not Make Decision on Merits of Request Until All Parties Have Opportunity to Have Views Considered ML20207A2061987-04-17017 April 1987 Responds to Request for Rept Re Legal & Institutional Aspects Under NRC Jurisdiction on Possible Conversion of Unit 1 to Defense Matls Production Reactor.Cp Still in Effect.Util Plans to Mothball Reactor by June 1988 ML20210N2161986-09-25025 September 1986 Discusses Governor Celeste Opposing Full Power Operations of Plants.Order Bars Commission from Voting Until Further Order by Us Court of Appeals.Served on 860930 NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs1986-09-10010 September 1986 Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls1986-08-26026 August 1986 Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls ML20209E6291986-08-26026 August 1986 Responds to 860731 Request to Be Kept Informed of Proceedings Re Facilities ML20206Q1321986-08-20020 August 1986 Submits Interim Response to Re Alleged Falsification of Welding Certificates for Welders at Plants Employed by Powerplant Specialists,Inc ML20204F9361986-07-30030 July 1986 Responds to from R Blank,Addressing Concerns Re Safety of Older Nuclear Plants,Per SO Conte 860701 Request ML20215L2051986-06-16016 June 1986 Responds to to NRC Requesting That FEMA Conduct Public Meeting Re FEMA Assessment of 861213 Emergency Planning Exercise.Commission Addressed Similar Response in 860606 Memorandum & Order NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco1986-04-23023 April 1986 Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress1986-04-23023 April 1986 Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress ML20137P5121986-01-24024 January 1986 Provides Info Concerning Financial Qualifications of Utils Re Safety of Plants.Nrc Regulation of Commercial Nuclear Power Based on Responsibility of Licensees for Safe Operation.Addl Views of Asselstine Encl ML20141K3511986-01-15015 January 1986 Responds to Re Jg Martinez 851115 Questions Concerning 851107 Failure of Diesel Engine & Speed Control. Staff Recommended That Enhanced Maint & Surveillance Program Needed to Assure Reliability of Delaval Diesel Engines ML20211G2531985-10-0101 October 1985 Informs That 841019 Rept of Ofc of Inspector & Auditor, Including Transmittal Memo & Encl to ,May Be Released Based on NRC & Justice Dept Conclusion of Investigation ML20132G6251985-09-19019 September 1985 Forwards Responses to Gao Rept, NRC Should Rept on Progress in Implementing Lessons Learned from TMI Accident ML20140H5551985-08-13013 August 1985 Forwards Press Release 85-108 Re Proposed Fine Concerning Util Alleged Violation of NRC Requirements Which Prohibit Discrimination Against Employee for Identifying Safety Concerns to Mgt ML20140H5741985-08-12012 August 1985 Forwards Press Release 85-106 Re Proposed Fine for Util Alleged Violation of NRC Requirements Concerning Employee Discrimination in Cleanup Program ML20140H5911985-07-23023 July 1985 Forwards Press Release 85-99 Re NRC Proposed Civil Penalty in Amount of $150,000 Against Util for Violation of Requirements Concerning Reactor Vessel Water Level Instruments ML20132B8341985-07-18018 July 1985 Forwards Quarterly Status Rept for Second Quarter CY85. Licensing Delay for Limerick 1 Projected to Be 5 Months. Delay Cannot Be Quantified for Shoreham Due to Litigation. Full Power OL Issued for Palo Verde 1 on 850601 IR 05000409/20050311985-07-16016 July 1985 Forwards Notice of Violation Issued to Util Based on 850409-0531 Insp ML20140H6231985-07-15015 July 1985 Forwards Press Release 85-95 Re NRC Proposed Fine Against Util for Alleged Violations of Safety Requirements During Apr 1985 ML20141H1081985-07-0909 July 1985 Forwards Responses to 850610 Questions Re Diablo Canyon OL Proceeding.Responses Delayed Due to Press of Other Business ML20140H6461985-06-0404 June 1985 Forwards Press Release 85-80 Re NRC Proposed Civil Penalty in Amount of $500,000 Aginst Util for Alleged Matl False Statements Made to NRC Concerning Operator Qualifications & Training ML20140H6701985-06-0303 June 1985 Forwards Press Release 85-78 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Unplanned Occupational Radiation Exposures & Failure to Control Contractor Work Forces ML20140H7211985-05-24024 May 1985 Forwards Press Release 85-75 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Failure to Take Corrective Action When Warranted Concerning QA Program ML20140H7451985-05-17017 May 1985 Forwards Press Release 85-70 Re NRC Proposed Civil Penalty in Amount of $50,000 Against TVA for Alleged Violation of Security Requirements 1989-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20195G3811999-06-0909 June 1999 Ack Receipt of ,Which Transmitted Emergency Plan Procedure 10-S-01-1,Rev 103,under Provisions of 10CFR50, App E,Section V ML20195G2971999-06-0909 June 1999 Ack Receipt of Re Emergency Plan Procedure 10-S-01-1,rev 104.No Violations Identified & Changes Subject to Insp to Confirm Effectiveness ML20195G3511999-06-0909 June 1999 Ack Receipt of 980831 & 1022 Ltrs,Which Transmitted Changes to Grand Gulf Emergency Plan,Rev 36 & 37,under Provisions of 10CFR50,App E,Section V ML20207D3351999-05-27027 May 1999 Forwards Insp Rept 50-416/99-05 on 990321-0501.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A6961999-05-21021 May 1999 Forwards Insp Rept 50-416/99-06 on 990419-23.No Violations Noted.Determined That Fire Protection Program Was Implemented IAW Requirements of License & GL 86-10.One Unresolved Item Noted Re fire-induced Failures on Equipment ML20206U3851999-05-18018 May 1999 Forwards Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A7561999-05-17017 May 1999 Ack Receipt of Which Transmitted Exercise Scenario for Emergency Plan Exercise Scheduled for 990623. Some Parts of Exercise Scenario Package Not Submitted & Being Developed ML20206N3921999-05-11011 May 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20206K1261999-05-0707 May 1999 Informs That on 990407 NRC Administered Gfes of Written Operator Licensing Exam.Facility Did Not Participate in Exam.Copy of Master Exam with Answer Key Encl.Without Encl ML20206E0571999-04-29029 April 1999 Discusses EOI 960418 Request for License Amend for GGNS That Would Permit Addl Method of Fuel Movement & Loading in Core When Control Rods Removed.Determined That Insufficient Info Provided to Permit Completion of Review ML20206B0951999-04-23023 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/99-01 & NOV .Reply Found to Be Responsive to Concerns Raised in Nov.Implementation of C/As Will Be Reviewed in Future Insps ML20206B3601999-04-23023 April 1999 Forwards Insp Rept 50-416/99-04 on 990131-0320.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206E7661999-04-19019 April 1999 Submits Summary of 990415 Meeting Conducted in Port Gibson, Mi Re Results of Plant Performance Review Completed on 990211 & Transmitted on 990319.List of Attendees Encl ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls IR 05000416/19980131999-04-0606 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/98-13 .Discussions on 990330 Resulted in Addl C/A Commitments to Address Violation Re Onsite Investigation ML20205J1051999-03-29029 March 1999 Forwards Objectives for Plant,Unit 1 1999 FEMA Emergency Plan Exercise Scheduled for 990623 ML20205E8701999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990211 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Isolated Examples of Failure to Follow Procedures Noted ML20207L3621999-03-0303 March 1999 Advises That Effective 990217,NRC Project Mgt Responsibilities for Grand Gulf Nuclear Station Transferred to Sp Sekerak 1999-09-09
[Table view] |
Text
.
'i 8 UNI S g # g NUCLEAR REGULATORY COMMISSION
, j W ASHING TON, D. C. 20555
- 9. e gv.....f March 22,1985 s/* E .
in;,s. Iba.
The Honorable Alan Simpson, Chairman Subcomittee on Nuclear Regulation Comittee on Environment and Public Works United States Senate Washington, DC 20510
Dear Mr. Chairman:
Enclosed for your information is a copy of the proposed enforcement action to be taken by the Nuclear Regulatory Comission against _
Mississippi Power and Light for violations involving traterial false statements regarding technical specifications at the Grand Gulf ~
Nuclear Power Station.
Sincerely, r .
.qf.
.. c .c .*
Carlton Kamerer, Director Office of Congressional Affairs
Enclosure:
As stated cc: Sen. Gary Hart IDENTICAL LETTER SENT T0:
Rep. Morris K. Udall / cc: Rep. Manuel Lujan Sen. Thad Cochran Sen. John Stennis Rep. Wayne Dowdy (NOTE: Rep. E. Markey / cc: Rep. C. Moorhead notified under spearate letter this date.)
8510230175 851004 PDR FOIA JACOBS85-478 PDR
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UNITED STATES NUCLEAR REGULATORY COMMISSION 2 e wAsamorom, o. c. 2osss RAR 21 M
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Docket No. 50-416 4
EA 84-75
^
Mississippi Power and Light Company ATTN: William Cavanaugh, III President 4 P.O. Box 1640 I Jackson, MS 39205 i
- Gentlemen
- _
j The Comission has reviewed your submittals with regard to the technical ~
1 specifications for Grand Gulf Nuclear Station Unit 1. As you are aware, these submittals contained numerous errors regarding plant-specific design ~
features. The Comission has concluded that the submittals contained several material false statements which are described below.
1 On December 15, 1980, you submitted a markup of the Standard Technical Specifications for General Electric Boiling Water Reactors (NUREG-0123) which you stated reflected plant-specific design features. This statement was false because, as described in detail in Item A in the enclosed Notice of Violation (NOV), the technical specifications did not reflect plant-specific design j features described in the FSAR. This statement was material in that had the 4
NRC known of the errors in the technical specifications, it would not have t issued the license without requiring changes to the technical specifications.
The second violation involves a markup of the technical specifications submitted on June 26, 1981. This submittal contained the same errors as were contained in the December 15, 1980 submittal. Additional submittals and changes were t transmitted in letters' dated December 31, 1981, January 12, February 25, March 23, April 5, 6, 7, and 30 May 26, June 1, 9 (two letters), and 10, 1982.
On June 16, 1982, NRC issued a low power (5%) license to MP&L for Grand Gulf Unit I with appended technical specifications based upon the licensee's submittals.
The errors contained in the December 15, 1980 submittal were reflected in the technical specifications issued with the license. Each of these submittals was a separate opportunity to discover and correct the false submittal of December 15, 1980. Your failure to do so constitutes a material false statement by omission.
The statement was false because you failed to correct your initial false submittal and to ensure that the technical specifications ultimately issued with the license reflected plant-specific design features. The statement was material because the NRC would not have issued the license with erroneous technical specifications.
CERTIFIED MAIL ENCLO5ED RECEIPT RE0 VESTED g fh3Ny NO
(
4 Mississippi Power and Light Company l The third violation involves a letter to Harold Denton dated June 14, 1983, in which Mississippi Power and Light provided additional proposed changes to the Grand Gulf Technical Specifications which you stated were " intended, in general, to enhance clarity or provide consistency with the plant design and i,
operation." Certain statements in this letter were false because:
i
- a. With reference to Technical Specification 4.8.1.1.1.b, the submittal l stated, "There is no automatic transfer from the nomal to alternate circuit since this bus search and automatic transfer feature was deleted from the load I shedding and sequencing (LSS) panel by a pre-operating license design change.
Section 8.3 of the FSAR no longer contains a description of the bus search and automatic transfer feature of the LSS panel." However, the LSS panel still i performs a search and automatic transfer function even though it is prohibited
! from auto-transfer hookup to another off-site power source by other features.
! b. With reference to Technical Specification 6.5.2.2, the submittal stated l that the Manager of Systems Nuclear Operations, Middle South Services, will be '
l replaced by a qualified representative of System Nuclear Operations. However, s the organizational entity, Systems Nuclear Operations, did not exist.
The statements were material because an agency reviewer might have made the
- requested changes to the technical specifications had the reviewer not known 1
that the bases for the changes were wrong.
I The fourth violation involves a letter to the Nuclear Regulatory Comission staff dated June 23, 1983, in which Mississippi Power and Light provided additional proposed changes to the Grand Gulf Technical Specifications which MP&L stated were "interded, in general, to enhance clarity or provide consistency with the plant design and operation." A statement in this letter 1
was false because the submittal stated, with reference to Technical Specification Table 4.3.7.5-1, that a note requiring channel calibration does not apply to the instruments used at Grand Gulf and should be deleted. However, the footnote
! fully applied to the Grand Gulf instruments. The false statement was material j because the reviewer might have made the requested change to the technical ,
specifications based upon incorrect information.
The fifth violation involves a letter to Harold Denton dated August 5, 1984, in i which Mississippi Power and Light certified that the Grand Gulf Technical l Specifications transmitted to the NRC up to and including Amendment 13
! accurately reflected the plant, the FSAR and supporting documents, and the SER !
I in all material respects. The statement was false because the technical ;
specifications did not reflect existing plant-specific design features as [
evidenced by the fact that in a letter to the NRC dated August 14, 1984, MP&L j
requested additional changes to the Grand Gulf Technical Specifications to add ,
circuit breakers to the list of those circuit breakers performing primary l
! containment penetration conductor overcurrent protection functions for which [
surveillance was required. The false statement was material because the NRC :
believed the list of circuit breakers requiring surveillance was complete and !
might have issued the license with erroneous technical specifications, had the ;
j licensee not subsequently corrected the error. j l l l
1 t
Mississippi Power and Light ,
c Company j I
Two inspections of surveillance procedure compliance with technical specifications [
were conducted between license issuance and the comencement of initial criticality !
on August 18, 1982. Both of these inspections in the areas of operations and !
fire protection identified additional technical specification errors requiring ;
correction prior to initial criticality. The NRC was informed by MP&L management l
. at that time that the errors were isolated instances and had all been corrected i j prior to initial criticality, j l
!' During the period of September 27 to October 8, 1982, Region II inspectors l identified additional problems with technical specification surveillance ;
! requirements. As a result, an enforcement conference was held with MP&L ,
j in the Region II Office and a Confirmation of Action Letter was issued ;
by the Region II Regional Administrator confirming licensee comitments to i prepare and submit license amendment requests to the NRC. The amendments were i i to correct administrative and technical deficiencies in the facility technical i
! specifications, as well as to establish a formal Quality Assurance program to ' [
i assure compliance with the technical specifications, including the associated l surveillance requirements. Even after these efforts, submittals regarding i
l technical specifications still contained errors up to and including a submittal [
of August 5, 1984 l
! \'
The primary responsibility for ensuring that the license contains appropriate technical specifications clearly rests with the licensee. Your failure to j i fulfill your obligation to thoroughly know and understand the technical !
specifications which are a part of your license cannot be excused. The l material false statements listed in the Notice are indicative of.a failure ,
4 to exercise your responsibility to ensure the accuracy and completeness of [
j each and every submittal of information made or required to be made as part of l l the licensing process.
!l The violations have been categorized as Severity Level III violations in accordance f I with the General Statement of Policy and Procedure for NRC Enforcement Actions, la l
10 CFR Part 2 Appendix C. Each of the five material false statements constitutes j a separate violation of NRC requirements. To emphasize to you and to other !
licensees the importance of ensuring that technical specifications accurately l 4
reflect plant-specific design features, I have been authorized, after consultation with the Comission, to issue the enclosed Notice of Violation and Proposed
! Imposition of Civil Penalties in the amount of One Hundred and Twenty-five !
! ThousandDollars($125,000). I considered proposing a civil penalty of Two i Hundred and Fifty Thousand Dollars for these violations. However, in recognition !
< of the fact that the informality of the NRC's process for review of technical !
j specifications contributed to the problem, I have mitigated the penalty by 50%. j
! You are required to respond to the enclosed Notice ar.d you should follow the '
i instructions specified therein when preparing your response. The NRC will i closely monitor MP&L's corrective actions and failure to carry them out may i l
lead to further enforcement action. ;
- i As noted above, numerous inspections involving these matters have been conducted ;
by the NRC and also several management meetings and Enforcement Conferences have :
been held which concerned these issues. Written comitments have been made by i i
_ . . , . - . . - . - _ _ _ _ _ _ ~ _ _ , _ _ _ _ _ . _ _ _ . . - - _ _ . _ _ _ . _ - . _ . - - _ . . _ _ . _ _ . . - -__
Mississippi Power and Light Company ,,
MP&L as a result of these meetings and inspection reports. In your response to the enclosed Notice of Violation and Proposed Imposition of Civil Penalties, appropriate reference to these previous submittals (by page or paragraph number as appropriate) is acceptable.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosure will be placed in the NRC's Public Document Room.
The responses directed by this letter and accompanying Notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
Sincerely,j 7/
%5 r mes M. T or, Director ffice of nspection and Enforcement ,
Enclosure:
Notice of Violation and Proposed Imposition of Civil ' Penalties l
l
. _ _ - _ - . .- - -~ _ . . --
1 .
l NOTICE OF VIOLATION
' AND PROPOSED IMPOSITIOR UF CIVIL PENALTIES i:
I-i Mississippi Pcwer and Lig'ht Company Docket No. 50-416 Grand Gulf License No. NPF-13
- EA 84-75 As a result of review of your submittals for the period from December 15, 1980 to August 14, 1984, several material false statements were identified.
These false statements are representative of over four hundred errors discovered in the Grand Gulf Technical Specifications. The technical specifications did not reflect plant-specific design features despite the fact that the ifcensee had numerous opportunities over a four year period to ensure that they did.
t Some of the errors were significant enough to require correction by Order even for low power operation. The number of errors and the duration of the problem indicate that MP&L has failed to exercise its responsibility to ensure the -
completeness and accuracy of submittals to the NRC. In accordance with the General Statement of Policy and Procedure for NRC Enforcement Action, 10 CFR Part 2, Appendix C, 49 FR 8583 (March 8, 1984), and pursuant to Section 234 of the Atomic Energy Act of 1954, as amended 42 U.S.C. 2282, PL 96-295, and 10 CFR 2.205, the violations and associated civil penalties are described below:
i A. On December 15, 1980 a markup of the Standard Technical Specifications for J General Electric Boiling Water Reactors (NUREG-123), revision 2, August 1979 was submitted. The transmittal letter contained the statement that the markup reflected plant specific design features for Unit 1 of the l
Grand Gulf Nuclear Station.
i Contrary to Section 186 of the Atomic Energy Act of 1954, as amended, i this statement was a material false statement. The statement was
! false because, in the following respects, the technical specifications did not reflect existing plant specific design features.
- 1. In the markup, Technical Specification Table 3.3.5-1, Reactor Core
! Isolation Cooling System Actuation Instrumentation, pages 3/4 3-45 4 and 3/4 3-46, specified the minimum operable channels per trip system
> as "2" and referred to " Action 50." Action 50 stated "with the number of operable channels less than required by the M1aimum Operable Channels per Trip System requirement: ,
i
- a. For one trip system, place the inoperable channel in the tripped 1 condition within one hour or declare the RCIC system inoperable, f b. For both trip systems, declare the RCIC system inoperable.
I
- The initiation logic of RCIC at Grand Gulf Unit 1 is arranged as one l
trip system with four water level signals feeding a one-out-of-two-l twice logic. The technical specification requirement of 2 minimum
' operable channels per trip system would not result in RCIC initiation unless the correct two channels are operable. The minimum operable channels per trip system should have been four. Also, the Action
, n o v it eM -- (t 1 m ,7
Notice of Violation .
Statement was intended for a 2-trip system design instead of the one-trip system design at Grand Gulf.
- 2. In the markup, Technical Specification 3.9.1 ' stated:
"The reactor mode switch shall be OPERABLE and locked in the Shutdown or Refuel position. When the reactor mode switch is locked in the Refuel position:
- a. A control rod shall not be inserted or withdrawn unless the Refuel position one-rod-out interlock is OPERABLE.
- b. CORE ALTERATIONS shall not be performed using equipment associated with a Refuel position interlock unless the following associated Refuel position interlocks are OPERABLE for such equipment: _
- 1. All rods in. ~
2 .- Refuel platform position.
- 3. Refuel platform hoists fuel-loaded.
- 4. Fuel grapple position.
- 5. Source range monitor countrate."
However, Grand Gulf does not have a fuel grapple position interlock.
- 3. In the markup, Technical Specification 4.5.lb ECCS surveillance requirements for operability stated the required flow and discharge pressure to be:
- a. LPCS pump develops a flow of at least 7115 gpm against a test line pressure greater than or equal to 128 psid.
- b. LPCI pump develops a flow of at least 7450 gpm against a test line pressure greater than or equal to 111 psid.
- c. HPCS pump develops a flow of at least 7115 gpm against a test line pressure greater than or equal to 200 psid.
These technical specification discharge line pressure requirements for operability were subsequently changed to read respectively 290 psid, 125 psid, and 445 psid. The original discharge pressure requirements for operability were not consistent with the assumptions in the safety analysis.
4 In the markup, Technical Specification 4.8.1.1.1, Electrical Power Systems Surveillance Requirements, stated:
! "Each of the above required independent circuits between the offsite transmission network and the onsite Class IE l
distribution system shall be:
- b. Demonstrated OPERABLE at least once per 18 months during l
Notice of Violation shutdown by transferring manually and automatically, unit power supply from the nonnal circuit to the alternate circuit."
Grand Gulf Station did not have the automatic transfer feature for offsite to onsite AC power sources.
The false statement was material because if the NRC had known of the errors in the technical specifications, the NRC would not have issued the license with erroneous technical specifications.
This is a Severity Level III violation (Supplement VII). Civil Penalty - $25,000.
B. On June 26, 1981 a second markup of the Standard Technical Specifications for General Electric Boiling Water Reactors (NUREG-123), revision 2, August 1979 was submitted. This submittal contained the same errors as were contained in the December 15, 1980 submittal. Additional submittals and changes were transmitted in letters dated December 31, 1981, January 12,-
February 25, March 23, April 5, 6, 7, and 30, May 26, June 1, 9 (two letters) and 10, 1982. On June 16, 1982 NRC issted a low power (5%) license to MP&L for Grand Gulf Unit I with appended technical specifications based upon the licensee's submittals. The errors contained in Item A were reflected in the technical specifications issued with the license.
Each of these submittals was a separate opportunity to discover and correct the false submittal of December 15, 1980. The licensee's failure to do so constitutes a material false statement by omission.
The statement was false because the licensee failed to correct its initial false submittal and to ensure that the technical specifications ultimately issued with its license reflected plant-specific design features. The statement was material because the NRC would not have issued the license with erroneous technical specifications.
This.is a Severity Level III violation (Supplement VII). Civil Penalty - $25,000.
C. In a letter to Harold Denton dated June 14, 1983, Mississippi Power and Light provided additional proposed changes to the Grand Gulf Technical Specifications which MP&L stated were " intended, in general, to enhance clarity or provide consistency with the plant design and operation."
Contrary to section 186 of the Atomic Energy Act, this letter contained material false statements. The statements were false as shown below:
- 1. With reference to Technical Specification 4.8.1.1.1.b, the submittal stated, "There is no automatic transfer from the normal to alternate circuit since this bus search and automatic transfer feature was deleted from the load shedding and sequencing (LSS) panel by a pre-operating license design change. Section 8.3 of the FSAR no longer contains a description of the bus search and automatic transfer feature of the LSS panel."
I
Notice of Violation ,
However, the LSS panel still performs a search and automatic transfer function even though it is prohibited from auto-transfer hookup to another off-site power source by other features.
, 2. With reference to Technical Specification 6.5.2.2, the submittal stated that the Manager of Systems Nuclear Operations, Middle South Services, will be replaced by a qualified representative of System Nuclear Operations.
~
However, the organizational entity, Systems Nuclear Operations, did not exist.
The statements were material because an agency reviewer would not have made the requested changes to the technical specifications had the reviewer known that the bases for the changes were wrong.
This is a Severity Level III violation (Supplement VII). Civil '
Penalty - $25,000.
! D. In a letter-to the Nuclear Regulatory Consnission staff dated June -
23, 1983, Mississippi Power and Light provided additional proposed i changes to the Grand Gulf Technical Specifications which MP&L stated l were " intended, in general, to enhance clarity or provide consistency with the plant design and operation."
i Contrary to Section 186 of the Atomic Energy Act, this letter contained a material false statement. The statement was false as shown below:
$ The submittal stated, with reference to Technical Specification Table 4.3.7.5-1, that a note requiring channel calibration does not apply to the instruments used at Grand Gulf and should be deleted.
] However, the footnote fully applied to the Grand Gulf instruments.
The false statement was material because the reviewer might have made the requested change to the technical specifications based
, upon incorrect information.
i This is a Severity level III violation (Supplement VII). Civil Penalty - $25,000.
E. In a letter to Harold Denton dated August 5, 1984 Mississippi Power and Light certified that the Grand Gulf Technical Specifications
- transmitted to the NRC up to and including Amendment 13 accurately reflected the plant, the FSAR and supporting documents and the SER in all material respects.
I i
Contrary to Section 186 of the Atomic Energy Act of 1954, as amended, this statement was a material false statement. The statement was false because the technical specifications did not reflect existing plant-specific design features as shown below. In a letter to the NRC dated August 14, 1 1984, MP&L requested additional changes to the Grand Gulf Technical
( Specifications to add circuit breakers to the list of those circuit breakers l
Notice of Violation performing primary containment penetration conductor overcurrent protection functions for which surveillance was required. The false statement was material because the NRC believed the list of circuit breakers requiring surveillance was complete and might have issued the license with erroneous ,
technical specifications, had the licensee not subsequently corrected the error.
This is a Severity Level III violation (Supplement VII). Civil Penalty -
$25,000.
Pursuant to the provisions of 10 CFR 2.201, Mississippi Power and Light Company is hereby required to suNnit to the Director, Office of Inspection and Enforce-ment, USNRC, Washington, D.C. 20555, with a copy to the Regional Administrator, Region II, within 30 days of the date of this Notice, a written statement or explanation, including for each alleged violation: (1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) the corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieved. Consideration may be given to -
extending the response time for good cause shown. Under the authority of Section 182 of the Act, 42 U.S.C. 2232, the response shall be submitted under oath or affirmation.
Within the same time as provided for the response required above under 10 CFR ,
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2.201, Mississippi Power and Light Company may pay the civil penalties in the amount of One Hundred and Twenty-five Thousand Dollars ($125,000) for the violations, or may protest imposition of the civil penalties in whole or in part by a written answer. Should Mississippi Power and Light Company fail to answer within the time specified, the Director,.0ffice of Inspection and Enforcement, will issue an order imposing the civil penalties in the amount proposed above. Should Mississippi Power and Light Company elect to file an answer in accordance with 10 CFR 2.205 prutesting the civil penalties, such answer may: (1) deny the violations listed in this Noti;e in whole or in part; (2) demonstrate extenuating circumstances; (3) show error in this Notice; or (4) show other reasons why the penalties should not be imposed. In addition to protesting the civil penalties in whole or in part, such answer may request remission or mitigation of the penalties. In requesting mitigation of the proposed penalties, the five factors addressed in Section IV(B) of 10 CFR Part 2 Appendix C should be addressed. Any written answer in accordance with 10 CFR 2.205 should be set forth separately from the statement or explanation in reply pursuant to 10 CFR 2.201, but may incorporate by specific reference (e.g., citing page and paragraph numbers) to avoid repetition. Mississippi Power and Light Company's attention is directed to the other provisions of 10 CFR 2.205 regarding the procedure for imposing a civil penalty.
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Notice of Violation .
Upon failure to pay the penalties due, which have been subsequently determined in accordance with the applicable provisions of 10 CFR 2.205, this matter may be referred to the Attorney General, and the penalties, unless cc,npromised, remitted, or mitigated may be collec'ted by civil action pursuant to Section 234c of the Act, 42 U.S.C. 2282.
FOR THE NUCLEAR REGULATORY COMMISSION j
mes M. Tay1 r, Director W
Office of Inspection and Enforcement Dated at Bethesda, Maryland this.2/May of March 1985.
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