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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20199E4561997-11-13013 November 1997 Safety Evaluation Accepting Ampacity Derating Analysis in Response to NRC RAI Re GL-92-08, Thermo-Lag 330-1 Fire Barriers, for Plant ML20210Q9991997-08-28028 August 1997 Safety Evaluation Concluding That Since 25th Tendon Surveillance on Few Yrs Away,Adequacy of Remaining Prestressing Force Will Be Critical to Verify ML20149F9961997-07-18018 July 1997 Safety Evaluation Re Gpu Nuclear Operational Quality Assurance Plan,Rev 10 for Three Mile Island Nuclear Generating Station,Unit 1 & Oyster Creek Nuclear Generating Station ML20133E1681997-01-0707 January 1997 Safety Evaluation Re Third 10-yr Interval ISI Plan,Rev 1 to Relief Request R11 for Plant.Proposed Alternative to ASME Requirements Authorized ML20138H6671996-12-19019 December 1996 Safety Evaluation Accepting Util IPE Submittal in Response to GL 88-20 ML20134D7811996-10-24024 October 1996 Safety Evaluation Supporting Amend 51 to License DPR-73 ML20128L6741996-10-11011 October 1996 Safety Evaluation Accepting Third ten-year Interval for Pump & Valve Inservice Testing Program for Facility ML20128K1981996-10-0808 October 1996 Safety Evaluation Supporting Amend 50 to License DPR-73 ML20128L1601996-10-0303 October 1996 Safety Evaluation Accepting Third 10-yr Interval Inservice Insp Plan Request for Relief R15 ML20128F4791996-10-0101 October 1996 Safety Evaluation Accepting Rev to Inservice Testing Program Re Leakage Testing of Containment Isolation Valves ML20059D1771993-12-28028 December 1993 Safety Evaluation Supporting Amend 48 to License DPR-73 ML20062K1041993-12-0606 December 1993 Safety Evaluation Supporting Amend 47 to License DPR-73 ML20058F0311993-11-16016 November 1993 SE Informing That Changes to Pdms Requirements & Commitments List of 930115,does Not Constitute Unreviewed Safety Question,Nor Do They Involve Significant Hazard or an Environmental Impact ML20059K3001993-11-0808 November 1993 Safety Evaluation Supporting Amend 46 to License DPR-73 ML20057A3641993-09-0101 September 1993 SER Denying Licensee 930216 & 0416 Requests for Relief from Certain Requirements of ISI Program ML20056H2651993-08-24024 August 1993 SE Re Inservice Testing Program Requests for Relief ML20056F0171993-08-0505 August 1993 Safety Evaluation Accepting Proposed Changes to Pdms Requirements & Commitments List of 930115 ML20056E0911993-08-0404 August 1993 SE Re Util 930614 Response to Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs. Util Justification for Not Implementing Addl Short Term Actions Acceptable ML20128P7321993-02-19019 February 1993 Safety Evaluation Supporting Amend 171 to License DPR-50 ML20128P4651993-02-18018 February 1993 Safety Evaluation Accepting Util Justification for Cancelling Commitment on Five Plant Control Room Human Engineering Discrepancies Re Relocation of Shift Supervisor Ofc ML20128F1361993-02-0505 February 1993 Safety Evaluation Re Leak on Core Spray in-vessel Annulus Piping.Plant Can Be Safely Operated for One Fuel Cycle W/O Repairing Observed Leak at Listed 1/4-inch Fillet Weld ML20126M2861993-01-0505 January 1993 Safety Evaluation Granting Relief from ISI Post Repair Hydrostatic Schedule Requirements ML20125C3901992-12-0707 December 1992 Safety Evaluation Re Upper Reactor Bldg & Nonsafety Architectural Components Subjected to tornado-wind Loading ML20127P2251992-11-23023 November 1992 Safety Evaluation Accepting Response to SBO Rule ML20058G1331990-11-0606 November 1990 Safety Evaluation Supporting Amend 39 to License DPR-73 ML20058A7621990-10-18018 October 1990 SE Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01 ML20058P4681990-08-0909 August 1990 Safety Evaluation Accepting Changes to Table 4.3-3 of Recovery Operations Plan ML20247L0681989-09-11011 September 1989 Safety Evaluation Supporting Amend 35 to License DPR-73 ML20246M7561989-08-30030 August 1989 Safety Evaluation Accepting Util 890624 Response to Integrated Plant Safety Assessment Section 4.11, Seismic Design Consideration, Items 4.11(1), Piping Sys & 4.11(3), Electrical Equipment ML20247A7061989-07-17017 July 1989 Safety Evaluation Supporting Generic Ltr 83-28,Item 4.5.2 Re Periodic on-line Testing of Reactor Trip Sys ML20245J4411989-06-23023 June 1989 Safety Evaluation Supporting Util 850823 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability - On-Line Functional Testing of Reactor Trip Sys ML20245C1711989-06-15015 June 1989 Safety Evaluation Re Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20244C8501989-06-12012 June 1989 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re on-line Testing for Reactor Trip Sys ML20247E8141989-05-18018 May 1989 Safety Evaluation Accepting Proposed Changes to Recovery Operations Plan ML20247G4131989-05-15015 May 1989 Safety Evaluation Supporting Amend 34 to License DPR-73 ML20245J1201989-04-27027 April 1989 Safety Evaluation Supporting Amend 149 to License DPR-50 ML20245A6521989-04-12012 April 1989 Safety Evaluation Supporting Amend 33 to License DPR-73 1999-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear Station.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating Station.With ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20198D2091998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Oyster Creek Nuclear Generating Station.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195C4271998-11-0606 November 1998 Safety Evaluation Supporting Proposed Ocnpp Mod to Install Core Support Plate Wedges to Structurally Replace Lateral Resistance Provided by Rim Hold Down Bolts for One Operating Cycle ML20155J3021998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Oyster Creek Nuclear Generating Station.With ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20154R4981998-10-20020 October 1998 Core Spray Sys Insp Program - 17R ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L3051998-10-14014 October 1998 Safety Evaluation Accepting Licensee Request to Defer Insp of 79 Welds from One Fuel Cycle at 17R Outage ML20154Q3371998-09-30030 September 1998 Rev 8 to Oyster Creek Cycle 17,COLR ML20154L5571998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Oyster Creek Nuclear Generating Station.With ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 1999-09-30
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pued p '4 UNITED STATES g g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l l GPU NUCLEAR OPERATIONAL QUALITY ASSURANCE PLAN
! REVISION 10 l THREE MILE ISLAND NUCLEAR GENERATING STATION. UNIT 1 DOCKET NO. 50-289 ,
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1 AND OYSTER CREEK NUCLEAR GENERATING STATION l DOCKET NO. 50-219 l ,
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1.0 INTRODUCTION
By letter dated April 25,1997, and supplemented by letters dated June 18 and July 10,1997, GPU Nuclear submitted Revision 10 of the Operational Quality Assurance Plan. The proposal, submitted on behalf of Three Mile island Nuclear Generating Station, Unit 1 (TMI-1), and Oyster Creek Nuclear Generating Station (OCNGS), identifies organizational changes in the licensee's management. A major element of the reorganization is the proposed merging of the Nuclear Safety Assessment Department (NSA) and the Licensing and Regulatory Affairs Department (L&RA) under a single director. The new department would retain the name Nuclear Safety Assessment and assimilate the responsibilities of the L&RA. L&RA is responsible for, among other things, the management of the nuclear safety review process (10 CFR 50.59). Three management positions in the current NSA l
organization would be eliminated; a new position, General Office Review Board (GORB)
Consultant would be created and the site licensing function would report to the newly created position Manager-Nuclear Safety and Licensing. This safety evaluation contains a brief description of the staff's analysis of the proposed changes.
2.0 EVALUATION The following are the applicable review criteria and regulatory requirements used to evaluate the proposed organizational changes.
2.1 Standard Review Plan (SRP) Chaoters 17.1 and 17.2 Section ll.1 of SRP Chapter 17.2," Quality Assurance During the Operations Phase," refers, with some exceptions, to the acceptance criteria of SRP Chapter 17.1, Section ll.1, for the organizational elements of a quality assurance (QA) program, included in the acceptance criteria are provisions applicable to the quality organization management in the areas of 97 7220go2 g 9 P
b (a) independence from cost and schedule pressures, (b) communication channels with senior management positions to resolve quality problems, (c) duties and responsibilities unrelated to QA that would prevent full attention to QA matters, and (d) relative position in the organizational hierarchy.
2.2 SRP Chapter 13.4 Section ll delineates acceptance criteria for reporting relationships for the independent review function and the independent safety engineering group (ISEG). ISEG should report to a technically oriented management position that is not in the management chain for power production.
2.3 Aooendix B to 10 CFR Part 50 Criterion I, Organization, of Appendix B to 10 CFR Part 50, discusses requirements for organizational independence and the fact that personnel performing QA responsibilities have sufficient authority to identify and report quality problems. Because of the many variables involved, such as the number of personnel and the type of activity being performed, the organizational structure for executing the QA program may take various forms provided that the persons and organizations assigned the QA functions have the required authority and organizational freedom. Criterion I was written in a manner that would not dictate any particular organizational structure to assure independence, but rather that it would be flexible enough to accommodate the various organizational configurations that may be necessary to l properly execute specific activities performed by a licensee. The acceptability of any given i organizational structure remains predicated upon the effective implementation of the overall QA program by the licensee.
l The proposed changes in the licensee's Operational Quality Assurance (OQA) Plan and the associated staff evaluations are discussed below.
2.4 Realionment of Licensina and Reaulatory Affairs The responsibilities of the Director-NSA position would be amended to retain the requisite organizational independence based on the following considerations:
- 1. The Director-NSA would be responsible to assess, audit, and monitor the conduct of GPU Nuclear activities to assure that they provide the required degree of safety and reliability and are carried out consistent with all applicable laws, regulations, regulatory commitments, licenses, corporate policies and other requirements.
- 2. The Manager-Assessment will be res >c 1sible for providing recommendations on solutions to quality problems and peri it ning monitoring, assessments, and audits for the areas of licensing and the Indepet unt On-site Safety Review Group (IOSRG).
- 3. The Director-NSA would not be responsible for any activities unrelated to responsibilities described in the OQA Plan that would prevent the required attention to
. I QA matters. Further, the responsibility for the implementation of the QA plan wiil take precedence over the other duties of the Director-NSA.
- 4. The Director-NSA would have explicitly defined accessibility to the President (for selected activities), to the Director-Nuclear Safety & Technical Services and, to appropriate nuclear station directors for any significant quality-related problem or deficiency.
- 5. For onsite independent review issues involving the licensing and lOSRG areas, the i Manager-Assessment has the authority to directly report to and communicate with the Director-Nuclear Safety & Technical Services.
- 6. In the event of a conflict between the Manager-Assessment and any other non-QA activity reporting to the Director-NSA, the Director-NSA will delegate his authority to resolve the conflict to the Manager-Assessment. The Manager-Assessment has the authority to report directly to the Director-Nuclear Safety & Technical Services.
The staff considers the above provisions are acceptable to ensure that sufficient independence is maintained within the NSA management structure related to the assumption i of the Licensing and Regulatory Affairs Department responsibilities by the Director-NSA.
In regard to organizational structure, the stature of the Director-NSA will not change.
However, under certain situations the responsibility for carrying out provisions of the OQA Plan will be delegated to the Manager-Assessment in those cases, the Manager-Assessment is provided with the authority to report to a more senior manager to resolve the quality issues. The staff considers these provisions acceptable. ,
2.5 Qualification Reauirements for Certain NSA Manaaers Revision 10 of the OQA Plan eliminates the qualification requirements (academic degree in l engineering or physical science and 5 years of experience) for NSA managers who do not report directly to the Director-NSA as described in Section 1.9 of the OQA Plan. In the proposed organizational structure, all NSA management positions will report directly to the Director-NSA. The attemate qualification provision is therefore no longer applicable. The more conservative education and experience requirements (degree in engineering or physical science and 10 years of experience) for managers that directly report to the Director-NSA will remain in effect. The staff finds this change acceptable as NSA managers will satisfy l appropriate education and experience provisions. l 2.6 General Office Review Board (GORB) l The licensee has created a position of GORB consultant to assist the Director-NSA in his GORB responsibilities. The Director-NSA will remain the GORB Chairman and will continue to propose recommendations to the President-GPU Nuclear. The staff finds the addition of a GORB consultant acceptable.
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2.7 Independent On-site Safety Review Group (IOSRG)
The licensee has proposed to amend the organizational structure so that the IOSRG reports through the Manager-Nuclear Safety and Licensing rather than the Manager-NSA. This alignment meets the pertinent acceptance criteria of the SRP. The staff finds the revised reporting relationship of the ISORG acceptable.
3.0 CONCLUSION
In accordance with the SRP review criteria in Chapters 17.1,17.2, and 13.4, the staff has 1 determined that the proposed organizational structure is acceptable. While the OQA Plan !
Revision 10 change constitutes a reduction of the commitments in the QA program description previously approved by the NRC, we conclude that the revised program continues to satisfy the requirements of Appendix B to 10 CFR Part 50. -
Principal Contributor: A. Keim Date: July 18,1997 I
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