Letter Sequence Approval |
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MONTHYEARML20134D4391985-08-12012 August 1985 Discusses Auxiliary Feedwater Sys.Administrative Limit of Greater than or Equal to 60% Established for Water Level in Condensate Storage Tank.Review of History of Sys Will Be Performed Project stage: Other ML20132B3331985-09-13013 September 1985 Requests Tech Spec Changes to Eliminate Inconsistency in Tech Spec 3.7.1.4 Requirement for Condensate Storage Tank Min Level of 47% Water & 60% Water Level Determined to Be Necessary After 850720 Auxiliary Feedwater Pump Trip Project stage: Other ML20137Y1861985-10-0808 October 1985 Forwards AEOD/E514, Engineering Evaluation for Core Damage Precursor Event at Trojan. Most Serious of Five Events Occurred on 840920.Events Indicate Lack of Attention to Detail & Lack of Good Maint Practices Project stage: Other ML20137Y1981985-10-31031 October 1985 Engineering Evaluation for Core Damage Precursor Event at Trojan Project stage: Other ML20137H5371985-11-25025 November 1985 Forwards Review of Auxiliary Feedwater Sys for Reliability Improvements. List of Sys Mods & Schedule for Completion of Mods Encl.License Change Application Will Be Submitted to Add safety-related Surveillance Requirements Project stage: Other ML20137H5981985-11-30030 November 1985 Review of Auxiliary Feedwater Sys for Reliability Improvements Project stage: Other ML20203N8451986-04-29029 April 1986 Forwards Description of Effects of Planned Auxiliary Feedwater Sys Mods on Long-Term Recommendations GL-2 & GL-4, SRP Section 10.4.9 & Fsar.Sys Mods Scheduled for 1986 Refueling Outage Which Started on 860416 Project stage: Other ML20203L3241986-08-21021 August 1986 Discusses Status of Action Items Re Auxiliary Feedwater Sys Mods,Per Util .All Items Scheduled for Implementation by Startup of 1986 Outage Complete,Except as Listed Project stage: Other ML20213F3971986-11-10010 November 1986 Safety Evaluation Supporting Util Responses Re Effects of Proposed Mods to Improve long-term Reliability of Auxiliary Feedwater Sys Per Recommentations GL-2 & GL-3 Project stage: Approval ML20213F3821986-11-10010 November 1986 Forwards Safety Evaluation Supporting Util Responses in 851125 Rept on Auxiliary Feedwater Sys Design.Mods Consistent W/Recommendations GL-2 & GL-3 & Acceptable Project stage: Approval ML20214N9701986-11-24024 November 1986 Informs That Due to Problems W/Mechanical Overspeed Trip, 860821 Mod to Remove Electrical Overspeed Trip Reevaluated. Problems Identified During Setpoint Verification Testing. Electrical Overspeed Trip Will Remain Operational Project stage: Other 1985-08-12
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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 AUXILIARY FEEDWATER SYSTEM NRC RECOMMENDATIONS GL-2 AND GL-4
. INTRODUCTION
- By letter dated October 23, 1980, the staff forwarded its Safety Evaluation (SE) 1 of Portland General Electric's (PGE's) responses regarding requirements of the Auxiliary Feedwater (AFW) systems, which were identified in our letter to PGE dated October 3, 1979 and in NUREG-0611, " Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants." Among the responses evaluatcd were those related to long-Term Recommendations GL-2 and GL-4. Our SE concluded that PGE's responses to GL-2 and GL-4 were acceptable.
By letter dated November 25, 1985, PGE provided a detailed report of the Trojan AFW System design which included a discussion of proposed modifications that were intended to enhance system reliability. Responding to a staff request, PGE letter dated April 29, 1986 and an October 7, 1986 teleconference provided additional information regarding the affects of the system modifications as they related to GL-2 and GL-4.
DISCUSSION AND EVALUATION Long Term Recommendation GL-2 States:
" Licensees with plants in which all (primary and alternate) water supplies to the AFW systems pass through valves in a single flow path should install redundant parallel flow paths (piping and valves).
Licensees with plants in which the primary AFW system water supply passes through valves in a single flow path, but the alternate AFW system water supplies connect to the AFW system pump suction piping downstream of the above valve (s), should install redundant valves parallel to the above valve (s) or provide automatic opening of the valve (s) from the alternate water supply upon low pump suction pressure.
The licensee should propose Technical Specifications to incorporate appropriate periodic inspections to verify the valve position."
Our October 23, 1980 SE concluded that PGE's response to GL-2 was an acceptable alternative to the prescribed requirements. The staff determined that the in-sta11ation of low suction pressure alarms and safety-grade automatic trip of the AFW pumps on low suction pressure, the installation of control room position indication for the single locked-open primary AFW supply line suction valve, and the use of a new electric motor-driven AFW pump utilizing a separate flow path from the condensate storage tank (CST) to the pump suction, would collectively, be an acceptable alternate means of assuring AFW pump protection in the event of an inadvertantly closed valve on the primary AFW supply from the CST.
8611140188 861110 PDR ADOCK 05000344 P PDR
J PGE's November 25, 1985 letter proposes the replacement of the common suction valve with a flexible coupling. The flexible coupling and all non-Category I piping have been reanalyzed by the licensee and meets seismic Category I design requirements. In addition, an October 7, 1986 telephone conference confirmed that this " upgraded" piping has been analyzed for and meets Seismic Category II/I considerations and criteria, and will be incorporated into the ISI program. Also, a debris screen will be added to the CST outlet nozzle to prevent blockage. PGE also proposed to replace the safety related low suction pressure trip of the AFW pumps with a safety related low CST level trip. However, low AFW pump suction pressure would still be alarmed in the control room.
Based on the above, we conclude that the proposed modifications continue to provide an acceptable means of assuring AFW pump protection.
Long Term Recommendation GL-4 States:
" Licensees having plants with unprotected normal AFW system water supplies should evaluate the design of their AFW systems to determine if automatic protection of the pumps is necessary following a seismic event or a tornado.
The time available before pump danage, the alarms and indications available to the control room operator, and the time necessary for assessing the problem and taking action should be considered in determining whether operator action can be relied on to prevent pump damage. Consideration should be given to providing pump protection by means such as automatic switchover of the pump suctions to the alternate safetygrade source of water, automatic pump trips on low suction pressure, or upgrading the normal source of water to meet seismic Category I and tornado protection requirements."
Our October 23, 1980 SE concluded that PGE's response to GL-4 was acceptable since the concern raised in this recommendation was similar to that of Recommendation GL-2, namely, providing automatic protection for the AFW pumps in the event of loss of normal suction supply for what ever reason.
Other currently proposed modifications to the AFW system as stated in PGE's November 25, 1985 letter, in addition to those which were described under GL-2, include the installation of a tornado missile barrier around the above-grade suction piping near the CST, the addition of stiffeners to the CST wall in the vicinity of the suction nozzle, and judf rious placement of CST level transmitters and cabling. These modifications are intended to provide additional protection and availability of the AFW pump's normal water supply (i.e., the CST) and other components from damage during a seismic event or tornado.
Based on the above, we conclude that the proposed modifications continue to provide an acceptable means of assuring AFW pump protection.
CONCLUSION Based on our evaluation, the licensee's responses regarding the proposed modifi-cations are consistent with the recommendation of GL-2 and GL-4, and are therefore, '
acceptable. !
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Principle Contributor:
T. Chan )
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