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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
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Text
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DISTRIBUTION:
m 2 81985 Central Files HFEB Files (2)
DHFS Files (2)
WRegan HFEB Members MEMORANDUM FOR: Thomas M. Novak, Assistant Director for Licensing Division of Licensing FROM: Don H. Beckham, Acting Deputy Director Division of Human Factors Safety
SUBJECT:
SAFETY EVALUATION REPORT FOR WASHINGTON NUCLEAR PRDJECT, GENERIC LETTER 83-28, ITEM 1.2 (POST-TRIP REVIEW - DATA AND INFORMATION CAPABILITY).
DOCKET NO.: 50-397.
By letter dated November 18, 1983, Washington Public Power Supply System responded to Generic Letter 83-28 with regard to required actions based on generic implications of Salem ATWS events. The enclosed SER and SALP were prepared by the Human Factors Engineering Branch based upon TER input from its contractor, Science Applications International Corporation (SAIC), after having reviewed the applicable portions of the licensee's response to Generic Letter 83-28 for the Washington Nuclear Project No. 2. The TER was discussed with the licensee by telephone calls made May 16, 1985.
Based on our review, we conclude that the licensee's post-trip review data and information capabilities for Washington Nuclear Project No. 2 are acceptable.
This review has been conducted by S. N. Saba (x24878) and SAIC. There are no known dissenting professional opinions on this matter.
/
Divis}ionofHumanFactorsSafetyDon }. Beckh
Enclosures:
- 1. Safety Evaluation
- 2. SALP Evaluation cc: A. Bournia R. Auluck A-J. Bradfute' 8506060296 850528 0 R. Liner, SAIC ADOCK 050003 Q pog y D. Gallagher, SAIC Nf g .
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ENCLOSURE 1 SAFETY EVALUATION REPORT FOR GENERIC LETTER 83-28, ITEM 1.2 - POST-TRIP REVIEW (DATA AND INFORMATION CAPABILITY)
WASHINGTON NUCLEAR PROJECT NO. 2 DOCKET N0.: 50-397 I. INTRODUCTION On February 25, 1983, both of the scram circuit breakers at Unit l'of the Salem Nuclear Power Plant failed to open upon an. automatic reactor trip signal from the reactor protection system. This incident occurred during the plant start-up and the reactor was tripped manually by the operator about 30 seconds after the initiation of the automatic trip signal. The failure of the circuit breakers has been determined to be related to the sticking of the ,
under voltage trip attachment. Prior to this incident, on February 22, 1983, at Unit 1 of the Salem Nuclear Power Plant, an automatic trip signal was generated based on steam generator low-low level during plant start-up. In this case, the reactor was tripped manually by the operator almost coincidentally with the automatic trip. Following these incidents, on February 28, 1983, the NRC Executive Director for Operations (EDO), directed the staff to investigate and report on the generic implications of these occurrences at Unit 1 of the Salem Nuclear Power Plant. The results of the staff's inquiry into the generic implications of the Salem unit incidents are reported in NUREG-1000, " Generic Implications of the ATWS Events at the Salem Nuclear Power Plant." As a result of this investigation, the Commission (NRC) requested (by Generic Letter 83-28 dated July 8, 1983) all licensees of operating reactors, applicants for an operating license, and holders of
construction permits to respond to certain generic concerns. These concerns are categorized into four areas: (1) Post-Trip Review, (2) Equipment Classification and Vendor Interface, (3) Post-Maintenance Testing, and (4) Reactor Trip System Reliability Improvements.
The first action item, Post-Trip Review, consists of Action Item 1.1,
" Program Description and Procedure" and Action Item 1.2, " Data and Information Capability." This safety evaluation report (SER) addresses Action Item 1.2 only.
II. REVIEW GUIDELINES The following review guidelines were developed after initial evaluation of the various utility responses to Item 1.2 of Generic Letter 83-28 and incurporate the best features of these submittals. As such, these review l
l guidelines in effect represent a " good practices" approach to post-trip review. We h w e reviewed the licensee's response to Item 1.2 against these guidelines:
A. The equipment that provides the digital sequence of events (SOE) record and the analog time history records of an unscheduled shutdown should provide a reliabic source of the necessary information to be used in the post-trip review. Each plart variable which is necessary to determine the cause and progression of the events following a plant trip should be monitored by at least one recorder (such as a sequence-of-events recorder or a plant process computer) for digital parameters; and strip J
s charts, a plant process computer or analog recorder for analog (tine history) variables. Performance characteristics guidelines for SOE and time history recorders are as follows:
Each sequence of events recorder should be capable of detecting and recording the sequence Of events with a sufficient time discrimination capability to ensure that the tirne responses associated with'each monitored safety-related system can be ascertained, and that a determination can be made as to whether the time response is within acceptable limits based on FSAR Chapter 15 Accident Analyses. The recommended guidelines for the SOE time discrimination is approximately 100 millisecorids. If current SOE recorders do not have this time discrimination capability the licensee should show that the current time discrimination capability is sufficient for an adequate reconstruction of the course of the reactor trip and post-trip events. As a minimum this should include the ability to i
adequately reconstruct the transient and accident scenarios presented in Chapter 15 of the plant FSAR.
Each anelog time history data recorder should have a sample interval small enough so that the incident can be accurately reconstructed following a reactor trip. As a minimum, the i ,
licensee should be able to reconstruct the course of the transient and accident sequences evaluated in the accident analysis of l
l
I
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Chapter 15 of the plant FSAR. The recommended guideline for the sample interval is 10 seconds. If the time history equipment does not meet this guideline, the licensee should show that the time history capability is sufficient to accurately reconstruct the transient and accident sequences presented in Chapter 15 of the FSAR. To support the post-trip analysis of the cause of the trip and the proper functioning of involved safety related equipment, each analog time history data recorder should.be capable of updating and retaining information from approximately five minutes prior to the trip until at least ten minutes after the trip.
All equipment used to record secuence of events and time history information should be powered from a reliable and non-interruptible power source. The power source used need not be safety related.
B. The sequence of events and time history recording equipment should monitor sufficient digital and analog parameters, respectively, to assure that the course of the reactor trip and post-trip events can be reconstructed. The parameters monitored should provide sufficient information to determine the root cause of the unscheduled shutdown, the progression of the reactor trip, and the response of the plant parameters and protection and safety systems to the unscheduled shutdowns. Specifically, all input parameters associated with reactor trips, safety injections and other safety-related systems as well as output parameters sufficient to record the proper functioning of these
~
systems should be recorded for use in the post-trip review. The parameters deemed necessary, as a minimum, to perform a post-trip review that would determine if the plant remained within its safety limit design envelope are presented in Table 1. They were selected on the basis of staff engineering judgment following a complete evaluation of utility submittals. If the licensee's SOE recorders and time history recorders do not monitor all of the parameters suggested in these tables the licensee should show that the existing set of monitored parameters are sufficient to establish that the plant remained within the design envelope for the accident conditions analyzed in Chapter 15 of the plant FSAR.
C. The information gathered by the sequence of events and time history recorders shou'Id be stored in a manner that will allow for data retrieval and analysis. Tne data may be retained in either hardcopy, (e.g., computer printout, strip chart record), or in an accessible memory (e.g., nagnetic disc or tape). This information should be presented in a readatle and meaningful format, taking into consideration good human factors practices such as those outlined in NUREG-0700.
D. Retention cf data from all unscheduled shutdowns provides a valuable reference source for the determination of the acceptability of the plant vital parameter and equipment response to subsecuent unscheduled shutdowns. Information gathered during the post-trip review is to be
e retained for the life of the plant for post-trip review comparisons of subsequent events.
III. EVALUATION AND CONCLUSION By letter dated November 18, 1983, Washington Public Power Supply System provided information regarding its post-trip review program data and information capabilities for Washington Nuclear Proiect No. 2 We have evaluated the licensee's submittal against the review guidelines described in Section II. Licensee deviations from the Guidelines of Section II were reviewed with the licensee by telephone on May 16, 1985. A brief description of the licensee's responses and the staff's evaluation of the response against each of the review. guidelines is provided belo.w:
A. The licensee has described the performance characteristics of the equipment used to record the sequence of events and time history data needed for pust-trip review. Based on our review, we find that the sequence of events recorder characteristics will conform to the guidelines described in Section II A, and are acceptable. Based on our telephone conversation on May 16, 1985, the staff was able to discuss and resolve the licensee deviations from guidelines regarding time history recorder characteristics as follows:
The licensee has a new computer system which provides the desired pre and post trip durations. Accordingly the time history recorder characteristics conform to the guidelines and are acceptable.
B. The licensee has established and identified the parcmeters to be monitored and recorded for post-trip review. Based on our telephone conversation on May 16, 1985, the staff was also able to discuss and resolve the licensee deviations from the guidelines described in Section II B as follows:
The licensee has a new computer which will monitor all parameters. Based on our review, we find that the parameters selected by the licensee include all of those identified in Table 1, conform to the guidelines described in Section II B, and are therefore acceptable.
C. The licensee has described the means for storage and retrieval of the information gathered by the sequence of events and time history recorders, and for the presentation of this information for post-trip review and analysis. Based on our review, we find that this information will be presented in a readable and meaningful format, and that the storage, retrieval and presentation conform to the guidelines of Section II C.
D. The licensee's submittal indicates that the data and information used during post-trip reviews will be retained in an accessible manner for the life of the plant. Based on our review, we find that the licensee's program for data retention conforms to the guidelines of Section II D, and is acceptable, m
Based on our review, we conclude that the licensee's post-trip review data and information capabilities for the Washington Nuclear Project No. 2 are acceptable.
TABLE 1 BWR PARAMETER LIST SOE Time History Recorder Recorder Parameter / Signal x Reactor Trip x Safety Injection x ,
Containment Isolation x Turbine Trip x Control Rod Position x(1) x Neutron Flux, Power x(1) Main Steam Radiation (2) Centainmer.t (Dry Well) Radiation x (1) x Drywell Pressure (Containment Pressure)
(2) Suppression Pool Tenperature x(1) x Primary Systen Pressure x (1) x Primary System Level x MSIV Position x(1) Turbine Stop Valve / Control Valve Position
, x Turbine Bypass Valve Position x Feedwater flow l
I x Steam Flow i
(3) Recirculation; Flow. Pump Status l x (1) Scram Discharge Level i
x(1) Condenser Vacuum 1
l t
- k. _
SOE Time History Recorder Recorder Parameter / Signal x AC and DC System Status (Bus Voltage)
(3) (4) Safety Injection; Flow. Pump / Valve Status x Diesel Generator Status (on/0ff, Start /Stop)
(1): Trip parameters (2): Parameter may be recorded by either an SOE or time history recorder.
(3): Acceptable recorder options are: (a) system flow recorded on an SOE recorder, (b) system flow recorded on a time history recorder, or i (c) equipment status recorded on an SOE recorder.
(4): Includes recording of parameters for all applicable systems from the following: HPCI, LPCI, LPCS, IC, RCIC.
l l
l 1
i
ENCLOSUPE 2 SALP EVALUATION WASHINGTON NUCLEAR PROJECT NO. 2 DOCKET NO.: 50-397 CENERIC LETTER 83-28, ITEM 1,2, POST-TRIP REVIEW A. Functional Arees: Licensing Activities - Generic Letter 83-28.
Item 1.2, Post-Trip Review Data and Information Capability
- 1. Management involvement in assuring quality.
Based on our review of the licensee's response to Generic .
. Letter 83-28, we find that the licensee has an effective capability for the collection, storage and retrieval of data needed to assess unscheduled reactor trips.
Rating: Category 2.
- 2. Approach to resolution of technical issues from a safety standpoint.
Rating: N/A
- 3. Responsive to NRC initiatives.
Based on our review, we find that the licensee is responsive to NRC initiatives.
Rating: Category 2,
- 4. Staffing Rating: N/A
- 5. Reporting and analysis of reportable events Rating: N/A
- 6. Training and qualification effectiveness Rating: N/A
- 7. Overall Rating for Licensing Activity Functional Areas:
Category 2