Letter Sequence Approval |
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MONTHYEARML20136H4031985-11-18018 November 1985 Notifies That Amend 2 to Dcrdr Summary Rept Will Be Submitted by 851231,per ,To Allow Review of Incomplete Elements Previously Identified in SER Project stage: Other ML20136E9941985-12-31031 December 1985 Forwards Amend 2 to PGE-1041, Dcrdr Summary Rept for Trojan Nuclear Plant, Providing Info Re Incomplete Elements Identified in 850724 SER.Cross-ref Between Request for Addl Info & PGE-1041 Pages Encl Project stage: Request ML20199F5881986-03-0707 March 1986 Suppl to Technical Evaluation Rept of Dcrdr of Trojan Nuclear Plant Project stage: Other ML20203M7651986-04-17017 April 1986 Supplemental Safety Evaluation Re Amend 2 to Dcrdr Summary Rept.Rept Did Not Discuss Participation of Human Factors Consultant in Activities Required to Complete Dcrdr Project stage: Approval ML20203D5621986-06-17017 June 1986 Vol 2 of Amend 3 to PGE-1041, Dcrdr Summary Rept for Trojan Nuclear Plant Project stage: Other ML20206Q3901986-06-24024 June 1986 Forwards Response to Request for Info in 860417 Supplemental Safety Evaluation on Dcrdr (NUREG-0737,Item I.D.1).Revised Pages to Amend 3 to Vol 2 of PGE-1041, Dcrdr Summary Rept Also Encl Project stage: Supplement ML20203D5491986-07-16016 July 1986 Forwards Vol 2 of Amend 3 to PGE-1041, Dcrdr Summary Rept for Trojan Nuclear Plant Project stage: Other ML20212H4481987-03-0202 March 1987 Provides Listing & Revised Schedule Dates for Completing Human Engineering Discrepancy Corrective Action Project stage: Other ML20236D8581987-07-27027 July 1987 Forwards Response to NRC Request for Addl Info on Dcrdr. Human Engineering Discrepancy 250 Cancelled & Removed from PGE-1041 by Amend 1 Project stage: Request 1986-06-17
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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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Text
e e SUPPLEMENTAL SAFETY EVALUATION TROJAN NUCLEAR PLANT DETAILED CONTROL ROOM DESIGN REVIEW BACKGROUND By letter dated July 28, 1983, Portland General Electric Company (PGE) sub-mitted its Program Plan for a Detailed Control Room Design Review (DCRDR) of the Trojan Nuclear Plant. NRC staff comments on that plan were forwarded to PGE on November 17, 1983. Results of the Program Plan review indicated the need for an in-progress audit. The staff conducted that audit on ,
December 12-16, 1983, and the audit report was forwarded to PGE on February 29, 1984.
~.
PGE submitted a Summary Report for the Trojan DCRDR on December 31, 1984.
Review of the Summary Report indicated the need for a pre-implementation audit which was conducted on February 25-March 1, 1985. The NRC concluded from the pre-implementation audit that only one element (verification) of the DCRDR was complete and recommended that PGE submit a supplement to the Summary Report and to address the results of activities rea'uired to complete the remaining eight l l
elements of the DCRDR.
A revision to the Summary Report was submitted by PGE on April 17,1985, and Amendment 2 to the Summary Report was submitted on December 31, 1985 in l
l response to the NRC's request. l 1
8605010682 PDR 860417 ADOCK 05000344 PDR ,
EVALUATION The current staff evaluation of the Trojan DCRDR is provided below. This
- evaluation is based on information available to date and is arranged in order of the DCRDR elements identified in Supplement I to NUREG-0737. The staff was assisted in its evaluation by Science Applications International Corporation (SAIC). Acopy.oftheSAICSupplemen(it6theTechn'icalEvaluationReport t (STER) is attached. The staff concurs with the evaluations and conclusions in the STER.
Establishment of a qualified multidisciplinary review team.
Amendment 2 of the Summary Report did not discuss the participation of a Human Factors consultant in the activities required to complete the DCRDR and that PGE would maintain multidisciplinary participatioh'throughout the remainder of the DCRDR. In order to satisfy this requirement, PGE should provide a description of the participation of the human factors specialist in the activities outlined in the attached STER (Pages 4-5). !
Function and task analyses to identify control room tasks and information and control reouirements 4
The function and task analyses as described in Amendment 2 of the Summary l
Report is acceptable and meets the requirements of Supplement 1 to NUREG-0737. l l
l 2
Comparison of display and control requirements with a control room inventory Informationprovided1nAmendment2oftheSummaryReportindicatek_thatPGE met the requirement of Supplement 1 to NUREG-0737.
A control room survey to identify deviations from accepted human factors principles PGE's centrol room survey is incomplete as PGE did not describe the participa-tion of the human factors, specialist in the annunciator study. In addition PGE should provide the resolution of the annunciator study. The annunciator study will complete the control room survey if annunciator conventions based on accepted human factors principles are developed and consistently applied.
Assessment of human engineering discrepancies N
PGE indicated during the pre-implementation audit that all HEDs (including those identified during Phase 1) were assessed. Assessment was en the basis of:
- 1) Potential for operator error, and
- 2) Plant safety impact.
The assessment process used by PGE is acceptable and meets the requirement of Supplement 1 to NUREG-0737.
l 3
e a l
Selection of design improvements ,
The organization and process for selecting design improvements satisfies the !
l requirement. However PGE should provide responses to the comments and concerns 1
)
discussed for the HEDs in Appendices A, B, C and D of the STER.
Verification that selected improvements will provide the necessary correction and verification that improvements will not introduce new HEDs The NRC's concerns as stated in the SER for verifying HED correction still exist. PGE's description of the verification process in Amendment 2 does not contain an explicit response to the concerns of the NRC. This is still an open item.
's Coordination of control room imorovements with changes from other programs I such as the safety parameter display system (SPDS), operator training, Reg.
Guide 1.97 instrumentation, and upgraded emergency operatino procedures PGE has only resolved the concern regarding the SPDS operator interface, therefore, the requirement is unsatisfied and PGE should provide more informa-tion on operator training for changes in the control room.
4