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| | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT | | | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:51362 |
| | | stage = Approval |
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| ==SUMMARY== | | ==SUMMARY== |
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| Portland General Electric Company (the licensee) was requested by Generic Letter 82-33 to provide a report to the NRC describing how the post-accident monitoring instrumentation meets the guidelines of Regulatory Guide 1.97 as applied to emer-gency response facilities. The licensee's response specific to Regulatory Guide 1.97 was provided by letter dated December 28, 1984. Additional information was provided by letter dated May 13, 1986. | | Portland General Electric Company (the licensee) was requested by Generic Letter 82-33 to provide a report to the NRC describing how the post-accident monitoring instrumentation meets the guidelines of Regulatory Guide 1.97 as applied to emer-gency response facilities. The licensee's response specific to Regulatory Guide 1.97 was provided by {{letter dated|date=December 28, 1984|text=letter dated December 28, 1984}}. Additional information was provided by {{letter dated|date=May 13, 1986|text=letter dated May 13, 1986}}. |
| A detailed review and technical evaluation of the licensee's submittals was per-formed by EG&G Idaho, Inc., under contract to the NRC, with general supervision | | A detailed review and technical evaluation of the licensee's submittals was per-formed by EG&G Idaho, Inc., under contract to the NRC, with general supervision |
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Latest revision as of 03:13, 6 December 2021
Letter Sequence Approval |
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MONTHYEARML20154A3351985-11-30030 November 1985 Conformance to Reg Guide 1.97,Trojan Nuclear Plant Project stage: Other ML20197J6791986-05-13013 May 1986 Responds to Items Identified in Eg&G Rept Reviewing Util 851228 Submittal on Meeting Requirements of Reg Guide 1.97, Per Generic Ltr 82-33 & Suppl 1 to NUREG-0737 Project stage: Meeting ML20206T1351986-07-31031 July 1986 Conformance to Reg Guide 1.97,Trojan Nuclear Plant Project stage: Other ML20203N6431986-09-29029 September 1986 Insp Rept 50-344/86-30 on 860825-29.Violation Noted:Failure to Ship Waste Package Per Certificate of Compliance & Failure to Maintain Survey Records Project stage: Request ML20206U0511986-09-29029 September 1986 Safety Evaluation Re Util 860513 Response to Reg Guide 1.97. Licensee Provided Acceptable Justification for Deviating from Guidance of Reg Guide for Each post-accident Monitoring Variable Except for Quench Tank Temp & Neutron Flux Project stage: Approval ML20206T9641986-09-29029 September 1986 Forwards Safety Evaluation Re Util 860513 Response to Eg&G Idaho,Inc Rept Re Conformance to Reg Guide 1.97,Rev 2. Response Acceptable Except for Quench Tank Temp & Neutron Flux Variables.Instrumentation Should Be Upgraded Project stage: Approval ML20211E0971986-10-17017 October 1986 Forwards Complete Conformance to Reg Guide 1.97,Trojan Nuclear Plant, Technical Evaluation Rept.Technical Evaluation Rept Forwarded w/860929 Ltr Incomplete Project stage: Other ML20212Q4321987-01-26026 January 1987 Discusses NRC & Safety Evaluation Re Compliance W/Reg Guide 1.97.Mod of Quench Tank Temp Instrumentation Will Be Completed by End of 1988 Refueling Outage Project stage: Other 1986-05-13
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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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SAFETY EVALUATION TROJAN NUCLEAR PLANT DOCKET NO. 50-344 CONFORMANCE TO REGULATORY GUIDE 1.97 INTRODUCTION AND
SUMMARY
Portland General Electric Company (the licensee) was requested by Generic Letter 82-33 to provide a report to the NRC describing how the post-accident monitoring instrumentation meets the guidelines of Regulatory Guide 1.97 as applied to emer-gency response facilities. The licensee's response specific to Regulatory Guide 1.97 was provided by letter dated December 28, 1984. Additional information was provided by letter dated May 13, 1986.
A detailed review and technical evaluation of the licensee's submittals was per-formed by EG&G Idaho, Inc., under contract to the NRC, with general supervision
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by the NRC staff. This work was reported by EG&G in the Technical Evaluation Report (TER), "Conformance to Regulatory Guide 1.97, Trojan Nuclear Plant," dated July 1986 (attached). We have reviewed this report and concur with the conclusion that the licensee either confonns to, or is justified in deviating from, the guidance of Regulatory Guide 1.97 for each post-accident monitoring variable except for the variables quench tank temperature and neutron flux.
EVALUATION CRITERIA Subsequent to the issuance of the generic letter, the NRC held regional meetirgs in February and March 1983 to answer licensee and applicant questions and concerns regarding the NRC policy on Regulatory Guide 1.97. At these meetings, it was noted that the NRC review would only address exceptions taken to the guidance 8610070287 86092 PDR ADOCK0500bR P
\ ! of Regulatory Guide 1.97. Furthermore, where licensees or applicants explicitly state that instrument systems conform to the provisions of the regulatory guide,
- it was noted that no further staff review would be necessary. Therefore, the review performed and reported by EG&G only addresses exceptions to the guidance of Regulatory Guide 1.97. This Safety Evaluation addresses the licensee's submittals based on the review policy described in the NRC regional meetings l
and the conclusions of the review as reported by EG&G.
EVALUATION We have reviewed the evaluation performed by our consultant contained in the enclosed TER and concur with its bases and findings. The licensee either conforms to, or has provided an acceptable justification for deviating from the guidance of Regulatory Guide 1.97 for each post-accident monitoring variable except for the (a) quench tank temperature and (b) neutron flux.
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(a) Regulatory Guide 1.97 recommends a temperature range of 50 to 750*F for this variable. The licensee has provided instrumentation with a range of 0 to 300'F. The licensee states that this instrumentation is used to maintain the tank temperature below 200'F during normal operation and that a temperature near 300*F would indicate an abnormal condition. The staff concludes that the instrumentation range for this variable should be adequate to remain on scale during all accident and post accident conditions. Therefore, the licensee should provide 1
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a range that will a; a minimum read the saturation temperature corresponding to the rupture disk relief pressure (338 F).
- b. Regulatory Guide 1.97 recommends Category 1 instrumentation for this variable. Category I requirements include full redundancy to satisfy the single failure criteria. The licensee has committed to add a single Category I neutron flux channel, however, this will still not satisfy the single failure criteria. The licensee states that automatic post-accident boron injection flow rates and concentrations are designed to provide adequate shutdown margin for accidents without measuring the boron concentration. Baron injection of 2000 ppm from the refueling water storage tank and accumulators can be verified with Category 1 and 2 instrumentation. Any boron dilution would be detected by periodic sampling using the Post-Accident Sampling System. The plant also has existing neutron flux monitors which are not environmentally qualified for post accident monitoring, they are only qualified to perform their immediate safety function of reactor protection.
The staff concludes that the above instrumentation and sampling means are not satisfactory substitutes for a redundant qualified neutron flux monitoring channel. The use of the Post-Accident Sampling Sys-tem is much slower than a neutron flux monitoring channel, and the existing flux monitor systems are not environmentally qualified for post accident. The licensee should provide instrumentation for this variable that will comply with the Regulatory Guide 1.97 recommendations.
CONCLUSION Based on the staff's review of the enclosed Technical Evaluation Report, and the licensee's submittals, we conclude that the Trojan Nuclear Plant design is acceptable with respect to conformance to Regulatory Guide 1.97, Revision 2, except for the variables pertaining to the (a) quench tank temperature and (b) neutron flux. It is the staff's position that the licensee install and have operational, instru-mentation that meets the recommendations of Regulatory Guide 1.97, Revision 2, for these variables. This instrumentation should be operational at the first scheduled I
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l outage _of sufficient duration, but no later than startup following the second refueling outage after receipt of this report.
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