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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20058K1391993-12-0606 December 1993 Safety Evaluation Supporting Amend 193 to License NPF-1 ML20057D9951993-09-30030 September 1993 Safety Evaluation Accepting Licensee Request for Exemption from Certain 10CFR50 Requirements for Emergency Planning for Plant ML20057D0791993-09-22022 September 1993 Safety Evaluation Supporting Amend 192 to License NPF-1 ML20127P5801993-01-26026 January 1993 Safety Evaluation Supporting Amend 189 to License NPF-1 ML20125B8071992-12-0404 December 1992 Safety Evaluation Supporting Amend 188 to License NPF-1 ML20127L4221992-11-19019 November 1992 SE Accepting IST Program Requests for Relief for Pumps & Valves ML20059D1031990-08-30030 August 1990 SER Accepting Util 880311,0401 & 1223 & 900319 & 0622 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20059C7981990-08-27027 August 1990 Safety Evaluation Supporting Amend 162 to License NPF-1 ML20058L5641990-08-0202 August 1990 Safety Evaluation Concluding That Operable Instrumented Ammonia Detection Capability Unncessary for Protection of Control Room Personnel in Event of Spill of Anhydrous Ammonia in Vicinity of Plant ML20055C7531990-06-18018 June 1990 Safety Evaluation Supporting Amend 161 to License NPF-1 ML20245H4141989-08-10010 August 1989 Safety Evaluation Approving on-line Functional Testing of Reactor Trip Sys,Per Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20245E8091989-06-20020 June 1989 Safety Evaluation Supporting Amend 154 to License NPF-1 ML20247M9331989-05-24024 May 1989 Safety Evaluation Supporting Amend 153 to License NPF-1 ML20247H9571989-05-15015 May 1989 Safety Evaluation Supporting Amend 152 to License NPF-1 ML20247F1911989-03-17017 March 1989 Safety Evaluation Supporting Amend 151 to License NPF-1 ML20235T5351989-02-28028 February 1989 Safety Evaluation Supporting Amend 150 to License NPF-1 ML20151T4191988-08-0505 August 1988 Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures as Design Basis for Facility ML20151X8581988-08-0303 August 1988 Safety Evaluation Supporting Amend 149 to License NPF-1 ML20151H3041988-07-14014 July 1988 Safety Evaluation Supporting Amend 148 to License NPF-1 ML20151L4391988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20151E4551988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20196G0421988-06-23023 June 1988 Safety Evaluation Supporting Amend 145 to License NPF-1 ML20196C1571988-06-22022 June 1988 Safety Evaluation Supporting Amend 144 to License NPF-1 ML20196F9471988-06-16016 June 1988 Safety Evaluation Supporting Amend 143 to License NPF-1 ML20154D4931988-05-11011 May 1988 Safety Evaluation Supporting Amend 142 to License NPF-1 ML20154A1151988-05-0303 May 1988 Safety Evaluation Supporting Amend 141 to License NPF-1 ML20148S6491988-04-11011 April 1988 Safety Evaluation Supporting Amend 140 to License NPF-1 ML20151B3821988-03-31031 March 1988 Safety Evaluation Supporting Amend 139 to License NPF-1 ML20236X5311987-12-0101 December 1987 Safety Evaluation Supporting Amend 137 to License NPF-1 ML20236S4021987-11-12012 November 1987 Safety Evaluation Supporting Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Fire Protection of Safe Shutdown Capability Requirements ML20236M8711987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Accumulator Fill Line Failures ML20236M8551987-11-11011 November 1987 SER Supporting Util Repairs Proposal Re Main Feedwater Line Restraint Failure ML20236M9931987-11-0909 November 1987 Safety Evaluation Supporting Amend 136 to License NPF-1 ML20236A9151987-10-13013 October 1987 Safety Evaluation Concluding That Corrective Actions for Design Deficiencies in Main Steam Line Pipe Supports Adequate & Acceptable & That Commencement of Heatup & Return to Power Safe ML20235V6121987-10-0202 October 1987 Safety Evaluation Supporting Amend 135 to License NPF-1 ML20238B0181987-09-0101 September 1987 Safety Evaluation Supporting Amend 134 to License NPF-1 ML20237G8351987-08-25025 August 1987 Safety Evaluation Re Util 870723 Request for Relief from 4 H Test Pressure Hold Time Requirement of Section XI of ASME Code,1974 Edition Through Summer 1975 Addenda ML20237G8421987-08-24024 August 1987 Safety Evaluation Re Ultrasonic Insp of RCS hot-leg Elbow (Loop B).Ultrasonic Exam Performed Acceptable W/Exception of Ultrasonic Beam Spread Correction Procedures Used to Estimate Indication Size.Continued Operation Permissible ML20236P6731987-08-0707 August 1987 Safety Evaluation Supporting Amend 133 to License NPF-1 ML20236H5581987-07-30030 July 1987 Safety Evaluation Supporting Amend 132 to License NPF-1 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20210F8701999-07-22022 July 1999 Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar ML20209C6531999-07-0606 July 1999 Rev 8 to Defueled SAR, for Trojan Nuclear Plant ML20206H4501999-05-0505 May 1999 Safety Evaluation Supporting Amend 201 to License NPF-1 ML20206C9351999-04-23023 April 1999 Safety Evaluation Supporting Amend 199 to License NPF-1 ML20206C9751999-04-23023 April 1999 Safety Evaluation Supporting Amend 200 to License NPF-1 ML20207G9881999-03-0303 March 1999 Rev 6 to Trojan Nuclear Plant Decommissioning Plan ML20207J0781999-02-28028 February 1999 Update to Trojan ISFSI Sar ML20202G4511999-02-0202 February 1999 Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar ML20207C6981998-12-31031 December 1998 1998 Annual Rept for Trojan Nuclear Plant. with ML20195J2501998-11-17017 November 1998 Rev 7 to Trojan Nuclear Plant Defueled Sar ML20155E0561998-10-29029 October 1998 SER Approving Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20155E0411998-10-27027 October 1998 Amend 7 to Quality-Related List Classification Criteria for Tnp ML20154R4121998-10-0202 October 1998 Requests Commission Approval,By Negative Consent,For Staff to Grant Two Specific Exemptions from Package Test Requirement Specified in 10CFR71 for Trojan Reactor Vessel Package & to Authorize one-time Transport for Disposal ML20237B6121998-08-13013 August 1998 Revised Trojan Reactor Vessel Package Sar ML20151W5471998-08-13013 August 1998 Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant ML20236Y2691998-08-0808 August 1998 Revised Trojan Rv Package Sar ML20249B4081998-06-17017 June 1998 Rev 6 to Trojan Nuclear Plant Defueled Sar ML20203E6291998-02-28028 February 1998 Trojan Nuclear Plant Decommissioning Plan ML20198T1741998-01-0404 January 1998 Rev 5 to Trojan Nuclear Plant Decommissioning Plan ML20248K6891997-12-31031 December 1997 Enron 1997 Annual Rept ML20203J3821997-12-31031 December 1997 Annual Rept of Trojan Nuclear Plant for 1997 ML20248K6931997-12-31031 December 1997 Pacificorp 1997 Annual Rept. Financial Statements & Suppl Data for Years Ended Dec 1996 & 97 Also Encl ML20203B0341997-11-26026 November 1997 Rev 5 to Trojan Nuclear Plant Defueled Sar ML20199F8141997-10-21021 October 1997 Requests Approval of Staff Approach for Resolving Issues Re Waste Classification of Plant Rv ML20216F4291997-07-25025 July 1997 Requests Commission Approval of Staff Approach for Reviewing Request from Poge for one-time Shipment of Decommissioned Rv,Including Irradiated Internals to Disposal Site at Hanford Nuclear Reservation in Richland,Wa ML20141F2311997-06-24024 June 1997 Rev 3 to PGE-1061, Tnp Decommissioning Plan ML20148K3541997-06-0909 June 1997 Safety Evaluation Supporting Amend 198 to License NPF-1 ML20148E8631997-05-31031 May 1997 Amend 6 to PGE-1052, Quality-Related List Classification Criteria for Trojan Nuclear Plant ML20148D2681997-05-23023 May 1997 Safety Evaluation Supporting Amend 197 to License NPF-1 ML20141H3181997-05-19019 May 1997 Safety Evaluation Supporting Amend 196 to License NPF-1 ML20140D9451997-03-31031 March 1997 Tnp First Quarter 1997 Decommissioning Status Rept ML20137K5811997-03-31031 March 1997 SAR for Rv Package ML20136D5591997-03-0606 March 1997 Safety Evaluation Approving Merger Between Util & Enron Corp ML20134B6231997-01-15015 January 1997 Draft Rev 3 of Proposed Change to Trojan Decommissioning Plan ML20217M2381996-12-31031 December 1996 Portland General Corp 1996 Annual Rept ML20217M2471996-12-31031 December 1996 Pacific Power & Light Co (Pacifcorp) 1996 Annual Rept ML20217M2551996-12-31031 December 1996 1996 Enron Annual Rept ML20135C3521996-12-31031 December 1996 Annual Rept of Trojan Nuclear Plant for 1996 ML20132G2831996-12-19019 December 1996 Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan ML20132H0011996-12-12012 December 1996 Rev 20 to PGE-8010, Portland General Electric Nuclear QA Program for Trojan Nuclear Plant ML20132B8491996-12-12012 December 1996 Rev 20 to PGE-8010, Trojan Nuclear Plant Nuclear QA Program ML20135B5241996-11-27027 November 1996 Rev 4 to Trojan Nuclear Plant Defueled Sar ML20135B5341996-11-25025 November 1996 Trojan ISFSI Safety Analysis Rept ML20134M3381996-11-20020 November 1996 SER Approving Physical Security Plan for Proposed Trojan ISFSI ML20134K6621996-11-11011 November 1996 Decommissioning Plan,Tnp ML20134F1211996-10-31031 October 1996 Safety Evaluation Supporting Amend 195 to License NPF-1 ML20134F4661996-10-30030 October 1996 Final Survey Rept for ISFSI Site for Trojan Nuclear Plant ML20134P4321996-09-30030 September 1996 Tnp Quarter Decommisioning Status Rept,Third Quarter 1996 ML20137K5321996-09-0505 September 1996 Rev 0 to H Analysis of Residue Protocol ML20137K5091996-06-28028 June 1996 Summary Rept Poge Tnp SFP Project 1999-07-06
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, a 4 tog g *, UNITED STATES j
2 NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20666 4001 4
9 . . . . . ,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 195 TO POSSESSION-0NLY LICENSE NO. NPF-1 PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER AND ELECTRIC BOARD PACIFIC POWER AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET NO. 50-344
1.0 INTRODUCTION
By letter dated November 2,1995, Portland General Electric Company (PGE or the licensee) submitted a request for changes to the Facility Operating ,
License No. NPF-1 for the Trojan Nuclear Plant (Trojan). The changes '
requested revise Section 5.0, Administrative Controls, of the Trojan Nuclear Plant Permanently Defueled Technical Specifications (PDTS), Appendix A, to reflect changes in the organization of Portland General Electric (PGE) Company as they apply to the oversight and management of the Trojan Nuclear Plant.
2.0 BACKGROUND
The Trojan possession-only license allows the licensee to possess and maintain but not operate the facility. On March 31, 1995, the NRC issued Amendment No.
194 to License No. NPF-1 replacing the Appendix A Technical Specifications for the Trojan Plant with a new set of Permanently Defueled Technical Specifications. Trojan is permanently defueled and cannot be operated or have fuel placed in the reactor under the terms of its license.
3.0 DISCUSSION AND EVALUATION PGE submitted letters to the NRC dated September 29, 1994, January 19, 1995, and October 10, 1995, notifying the NRC staff of changes in its organizational
- structure as it applies to oversight and management of the Trojan Plant. The i proposed amendment included in the letter of November 2,1995, revises Section l 5.0, Administrative Controls, of the permanently Defueled Technical Specifications to reflect the organizational changes.
9611040289 961031 PDR P
ADOCK 05000344 PDR .
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- Sections 5.1.1 and 5.2.1.b of the Defueled Technical Specifications identifies l the General Manager, Trojan Plant as having overall responsibility for the '
facility. Section 5.2.1.c identifies the Vice President and Chief Nuclear ,
- Officer as having the corporate responsibility for overall nuclear safety. !
! The General Manager, Trojan Plant organizational 1y reports to the Vice President and Chief Nuclear Officer. The Vice President and Chief Nuclear i Officer reports to the PGE Chief Executive Officer on Trojan Nuclear Plant ^
i activities.
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i The November 2, 1995, amendment request renames the General Manager, Trojan i Plant to the Trojan Site Executive and Plant General Manager. This individual l l would report to the Senior Vice President, Power Supply at the corporate level. The Vice President and Chief Nuclear Officer at the corporate level
- would be eliminated. The Senior Vice President, Power Supply, will continue
. to report to the PGE Chief Executive Officer on Trojan Nuclear Plant activities.
! The Trojan Site Executive and plant General Manager will have overall
! responsibility for the facility, and will have control over those facility activities necessary for operation and maintenance of structures, systems and j components necessary for the safe storage of irradiated fuel. The Trojan Site Executive and Plant General Manager will also have corporate responsibility for overall nuclear safety. The Trojan Site Executive and Plant General ,
- Manager will be located at the Trojan Site. ;
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Currently the General Manager, Nuclear Oversight; General Manager 1 Engineering / Decommissioning; General Manager, Plant Support and Technical Functions; Manager, Maintenance; Manager, Operations; and Manager, Personnel / Radiation Protection at the Trojan site report to the General Manager, Trojan Plant. The proposed change would have these Trojan line managers and associated organizations reporting to the same individual with the new title Trojan Site Executive and Plant General Manager.
The licensee's proposal eliminates the position Vice President and Chief Nuclear Officer at the corporate level and has the Trojan Site Executive and
-Plant General Manager reporting to another existing corporate executive, the Senior Vice President, Power Supply. The corporate level vice president no longer is required to have any nuclear related qualifications. A number of site related activities that were previously reported to the corporate level Vice President and Chief Nuclear Officer would now be reported to the Plant i General Manager. These activities include the advice of the Independent Review and Audit Committee (IRAC) on matters relating to safe storage of irradiated fuel, the designation of the chairman, the members, and alternates that compose the IRAC, results of reviews as defined in Section 5.5.2.2, Review Responsibilities, and audits defined in Section 5.5.2.3, Audit Responsibilities. The licensee has retained.the requirement in Section 5.5.2.1.5, Functions, to notify the cognizant individual at the corporate level, in this case the Senior Vice President, Power Supply, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any safety significant disagreement between the IRAC and the Plant General Manager.
4 3-The regulations (10 CFR 50.40(b), and 10 CFR 50 Appendix B.I.) require that the applicant be technically qualified to engage in licensed activities, and that the authorities and duties of persons performing activities affecting structures, systems, or components important to safety be clearly established ,
and delineated. Standard Review Plan (SRP), 13.1.1., Management and Technical '
- Support Organization, NUREG-0800, dated July 1981, provides guidance in the NRC staff review of the licensee's corporate organizations. The licensee's i corporate organization should provide sufficient support to ensure safe dismantlement of the facility.
The changing of the title of the Trojan Site Executive and Plant General Manager to the Trojan Site Executive and Plant General Manager is an
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administrative change and the staff finds it acceptable. The NRC staff also i finds the elimination of the corporate levei position of Vice President and '
Chief Nuclear Officer and the reporting of the senior manager at the site to the corporate level Vice President, Power Generation acceptable. The
- significant reduction in risk to the public and onsite workforce since the
- Trojan Plant ceased operation and the unique nature of the decommissioning of the facility no longer requires specialized expertise at the corporate level.
Many of the independent functions that were performed at the corporate level can now safely be reviewed at the Trojan site. The retention of the notification requirement of the cognizant corporate level Senior Vice President in the case of a safety significant disagreement between the IRAC and the Plant General Manager provides an additional level of independent j
review and audit on safety significant matters at the site.
, The staff has determined that the proposed changes in the Trojan organizational structure does not adversely affect the licensee's ability to safely decommission the facility, that organizational duties and responsibilities continue to be clearly delineated, and that the licensee continues to meet the intent of guidance provided in SRP 13.1.1 at the corporate level. Therefore, the staff finds the licensee's proposal acceptable and in compliance with 10 CFR 50.40(b) and 10 CFR 50 Appendix 8.I.
and consistent with the guidance in SRP 13.1.1.
4.0 STATE CONSULTATION
In accordance with the Commission regulations, the appropriate member of the Oregon Department of Enerc/ was notified of the proposed issuance of this i amendment. The State official had no comment.
- 5. ENVIRONMENTAL CONSIDERATION The amendment is administrative in nature. The commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR 58404) dated November 27, 1994. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance t
of this amendment.
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- 6. CONCLUSION-The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes, (2) the change will be in compliance with the Commission regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. i Principal Contributor: Michael T. Masnik Date: October 31, 1996 l
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