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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 ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively 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 ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively 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 ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively 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 ML20205Q5761988-10-31031 October 1988 SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & Security ML20205Q5721988-10-31031 October 1988 SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & Security ML20205M5731988-10-26026 October 1988 Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20155G4801988-09-28028 September 1988 Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively 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 ML20151E4551988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20151L4391988-07-11011 July 1988 Safety Evaluation Supporting Amend 147 to License NPF-1 ML20195G5531988-06-24024 June 1988 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC 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 ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program 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 ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 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 ML20248K6931997-12-31031 December 1997 Pacificorp 1997 Annual Rept. Financial Statements & Suppl Data for Years Ended Dec 1996 & 97 Also Encl ML20248K6891997-12-31031 December 1997 Enron 1997 Annual Rept ML20203J3821997-12-31031 December 1997 Annual Rept of Trojan Nuclear Plant for 1997 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 ML20137K5811997-03-31031 March 1997 SAR for Rv Package ML20140D9451997-03-31031 March 1997 Tnp First Quarter 1997 Decommissioning Status Rept 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 ML20135C3521996-12-31031 December 1996 Annual Rept of Trojan Nuclear Plant for 1996 ML20217M2551996-12-31031 December 1996 1996 Enron Annual Rept ML20217M2471996-12-31031 December 1996 Pacific Power & Light Co (Pacifcorp) 1996 Annual Rept ML20217M2381996-12-31031 December 1996 Portland General Corp 1996 Annual Rept ML20132G2831996-12-19019 December 1996 Rev 2 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan ML20132B8491996-12-12012 December 1996 Rev 20 to PGE-8010, Trojan Nuclear Plant Nuclear QA Program ML20132H0011996-12-12012 December 1996 Rev 20 to PGE-8010, Portland General Electric Nuclear QA Program for Trojan Nuclear Plant 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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f-ENCLOSURE 1 SAFETY EVALUATION TROJAN NUCLEAR PLANT GENERIC LtIIER 83-28, ITEM 4.5.2 REACTOR TRIP SYSTEF RELIABILITY, ON-LINE TESTING INTRODUCTION AND SUMMADY Generic Letter 83-28 was issued by NRC on July 8,1983, indicating actions to be taken by applicants and licensees based on the generic implications of the Salem ATWS events. Item 4.5 states a staff position which requires on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers, for all plants.
Item 4.5.2 reouires applicants and licensees with plants not currently designed to permit this periodic on-line testing to justify not making modificaticns to permit such testing. By letter dated November 4, 1983, the licensee, Portland General Electric Company, responded to the staff position e regarding Item d.5.2 of Generic Letter 83-28. Our review of this response ct finds it to be acceptable.
EVALUATION The licensee states that the Trojan plant, after implementation of the reactor trip breaker shunt trip modification, will be designed to allow on-line testing of the undervoltage and shunt trip attachments. Although the licensee does not specifically refer to the on-line testability of the entire reactor trip system, staff knows that the remainder of the reactor trip system has on-line testing capability because the Trojan Technical Specifications require such testing.
CONCLUSION The staff finds that the Trojan Nuclear Plant is designed to permit on-line functional testing of the reactor trip system, including independent testing of the diverse trip features of the reactor trip breakers. Thus, the licensee meets the staff position of Item 4.5.2 of Generic Letter 83-28.
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