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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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I ISTRIBUTION e g< Docket 50-397)
PTRB'Readin(
Docket No. 50-397 HLThompson JJKramer LPCrocker FEB 0 4 682 DLziemann HBClayton ItEMORANDUM FOR: Robert L. Tedesco, Assistant Director LPhillips for Licensing ,
Division of Licensing , , , cy , , s
( . -g, i e FROM: Hugh L. Thompson, Jr., Acting Director os p; 2 *._*Q(.9 Division of Human Factors Safety [
SUBJECT:
SAFETY EVALUATION REPORT INPUT: $ Y-WASHINGTON PUBLIC POWER SUPPLY SYSTEM, UNIT 2 FE3;3 22s $
OPERATING AND MAINTENANCE PROCEDURES AND C
.dc:mEfic[@gta ANTICIPATED TRANSIENTS WITHOUT SCRAM h A /f I #-
Enclosed are our SER inputs for Section 13.5.2, Operating and Maintenance -
Procedures, which include consideration of the 1NI Task Action Plan (TAP)
Items I.C.1 - Short-Term Accident Analysis and Procedures Revision, I.C.7 -
NSSS Vendor Review of Procedures and I.C.8 - Pilot Monitoring of Selected Emergency Procedures for Near-Term Operating License Applicants and Section 15.8 - Anticipated Transients Without Scram (ATWS).
Emergency operating procedures based on the reanalysis of transients and accidents developed in response to TAP Item I.C.1, as clarified in NUREG-0737, will be developed by the applicant in lieu of interim procedures developed from the Short-Term Accident Analysis. Therefore, the program for Pilot Monitoring of Emergency Procedures for NT0L's as required by TAP Item I.C.8 will not be performed for WNP-2. This approach is acceptable to the Procedures and Test Review Branch (PTRB).
However, NRC approved Technical Guidelines must be available in time for the applicant to prepare and implement emergency operating procedures prior to fuel load. PTRB will r.eview the applicant's program prior to issuance of the operating license.
This review is being performed by Brent Clayton, Principal Operational A Safety Engineer (X24582), of the Procedures and Test Review Branch.
So '
oc g Original signed by o Hugh L. Thompson, Jr., Acting Director
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SAFETY EVALUATION REPORT INPUT WASHINGTON PUBLIC POWER SUPPLY SYSTEM, UNIT 2 OPERATING AND MAINTENANCE PROCEDURES AND ANTICIPATED TRANSIENTS WITHOUT SCRAM 13.5.2 OPERATING AND MAINTENANCE PROCEDURES A. General (h' A review has been conducted of the applicant's plan for development and implementation of operating and maintenance procedures. The review was conducted to determine the adequacy of the applicant's program for assuring that routine operatings off-normale and emergency activities are conducted in a safe manner. The following description and evaluation are based on information contained in the applicant's FSARi the applicant's response to NRC TMI Action Plan Items (NUREG-0660 and NUREG-0737), and supplemental information obtained during the review.
f In determining the acceptability of the applicant's programe the criteria of NUREG-0800, Standard Review Plane Section 13.5.3 were used. The review consisted of an evaluation of (1) the applicant's procedure classification system for procedures that are performed by licensed operators in the control room and the classification system for other
1 I operating and maintenance procedures; (2) the applicant's plan for completion of operating and maintenance procedures during the initial plant testing phase to allow for correction prior to fuel loading; (3) the applicant's program for compliance with the guidance contained in Regulatory Guide 1.33, Rev. 2, March 1978 regarding the minimum procedural requirements for safety related operations; (4) compliance with the guidance contained in ANSI N18.7-1976/ANS 3.2; and (5) the applicant's program for compliance with Task Action Plan (NUREG-0660)
Item I.C.1, " Guidance for the Evaluation and Development of Procedures for Transients and Accidents", for the development of Emergency Operating Procedure Guidelines.
- Additionally, the applicant's program for compliance with Item I.C.1 of NUREG-0737 for the development of Emergency Operating Procedures will be reviewed and reported in a supplement to this Safety Evaluation Report.
l B. Operating and Maintenance Procedure Program i
d The applicant has committed in FSAR Chapter 17e Quality of*h I Assurance, to a program in which all activities are to j
be conducted in accordance with detailed written and approved procedures meeting the requirements of Regulatory Guide 1.33r Rev. 2e March 1978, " Quality Assurance Program l Requirements (Operation)", and ANSI N18.7-1976/ANS 3.2.
l l
, i -
jhTheapplicant uses the following categories of procedures for those operations performed by licensed operators in the control room:
System Operations (Including Radioactive Waste Systems)
General Operation Abnormal Conditions (Including Annunciator Response) -
Emergencies Surveillance Other procedures include the following areas:
Fuel Handling and Refueling Activities Operatie41 and Engineering Tests Chemistry Health Physics Maintenance Nuclear Performance Evaluation Emergency Plan Implementation
,, Security Plan Implementation Our review disclosed that the applicant's program for use of operating and maintenance procedures meets the relevant requirements of 10 CFR 34, and is consistent with the guidance provided in Regulatory Guide 1.33 and ANSI N18.7-1976/ANS 3.2. Thereforer we conclude that the applicant's program is acceptable.
i C. Reanalysis of Transients and Accidents; Development of Emergency Operating Procedures
(' / In letters of September 13 and 27, October 10 and 30, and t
i November 9, 1979, the Office of Nuclear Reactor Regulation required licensees of operating plants, applicants for operating Licenses and licensees of plants under construction to perform analyses of transients and accidents, prepare emergency operating procedure guidelinese upgrade emergency operating procedurese and to conduct operator retraining.
Emergency operating procedures are required to be consistent with the actions necessary to cope with the transients and accidents analyzed. Analyses of transients and accidents were to be completed in early 1980 and implementation of procedures and retraining were to be completed three months after emergency operating procedure guidelines were established; howevere some difficulty in completing these requirements has been experienced. Clarification l of the scope of the task and appropriate schedule revisions f
were vecluded in Item I.C.1 of NUREG-0737.
In a submittal dated June 30, 1980s the BWR Owners' Group provided a draft of generic Emergency Operating Procedure 1
Guidelines for Boiling Water Reactors. The guidelines were developed to comply with Task- Action Plan Item I . C .1 (3 ) as clarified by NUREG-0737 and incorporated i
l
, 4 .
d
_5-i the requirements for short-term reanalysis of small break loss-of-coolant accidents and inadequate. core cooling (Task Action Plan Items I.C.1(1) and I . C .1 (2 ) ) . In a letter dated October 21, 1980s from D. G. Eisenhut to S. T. Rogers, the' staff indicated that the, generic guidelines prepared by General Electric and the BWR Owners' ,
Group were acceptable for t r.i a l implementation at,, Wash'ington Public Power Supply System' Unit 2.
Additional informationi requested by the staffe was submitted by the Owners' Group on January 31, 1981.
~Th'e staff will complete its' review of this additional information prior to making a' final conct'usion on the acceptability of the guidelines for, implementation on all Boiling Water Reactors.
$k#In Amendment No. 17 to the FSAR (dated July 1981), the applicant committed to implement a program of emergency operating procedures based on the General Electric Owners' Group Guidelines, when approved by the staffe in acterdance with the schedule of NUREG-0737.
In addition to the General Electric Owners' ' Group efforts, the staff has prepared draft guidelines._for long-term upgradihg of emergency operating procedures (NUREG-0799) in accordance with Task Action Plan Item I.C.9. These guidelinese as revised durino the resolution of public commentsi also should be used in the preparation of the e
fv '
Washington Public Power Supply System Unit 2 emergency operating procedures. Therefore, the staff does not plan to conduct a Pilot Monitoring Review of Selected Emergency Operating Procedures in accordance with TMI Task Action Plan Item I.C.8 for this plant. However, we will review the applicant's submittal for compliance with the final staff guidelines r e s u l't i n g from resolution of public comments on NUREG-0799. The final staff guidelines will include consideration of the General Electric Owners' Group technical guidelines. Our review of the emergency operating procedures submitted by the applicant will be completed prior to issuance of the operating license and will be addressed in a.
supplement to this Safety Evaluation Report.
- In accordance with NUREG-0737, Item I.C.7, NSSS vendor review of low power testingi power ascension and emergency operating procedures is necessary to further l verify adeouacy of the procedures. Amendment No. 17 l
l to t h e- F S A R stated that the NSSS Vendore General Electric Corporatione will review the low power testinge power ascension test and emergency operating procedures by July 1982. This is several months prior to the currently scheduled fuel load date. The staff will .
confirm that this review is completed prior to issuance of a full power license.
15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM
/ Anticipated Transients Without Scram (ATWS) are events in which the scram system (reactor trip system) is postulated to fail to operate as required. This subject has been under generic review by the Commission staff for several years.
f/ In December 1978, Volume 3 of NUREG-0460, " Anticipated Transient Without Scram for Light Water Reactors" was issued describing the proposed type of plant modifications we believe are necessary to reduce the risk from anticipated transients with failure to scram to an acceptable level. We issued requests for the industry to supply generic analyses to confirm the ATWS mitigation capability described in Volume 3 of NUREG-0460.
Subsequently, we recommended to the Commission that rulemaking be used to determine any future modifications necessary to resolve ATWS concerns as welL as the
~
required schedule for implementation of such modifications.
Washitston Public Power Supply System, Unit 2 is subject to the Commission's decision in this matter.
d It is our expectation that the necessary plant modi *ications will be implemented in one to four years following a -
Commission decision on ATWS. As a prudent courses to
'further reduce the risk from ATWS events during the interim 4
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- i 8-period before completing the plant modifications determined by the Commission to be necessary, we require that the following steps be taken
- 1. An emergency operating procedure should be developed for an ATWS eventi including consideration of scram indicators, rod position indicators, average power range flux monitorse reactor vessel level and pressure indicatorse relief valve and isolation valve indicatorsi and containment temperaturer pressure and radiation indicators. The emergency operating procedures should be sufficiently simple and unambiguous to permit prompt operator recognition of an ATWS event.
- 2. The emergency operating procedure should describe actions to be taken in the event of an ATWS including consideration of manually scramming the reactor by using the manual scram buttonse changing the operation mode switch to the shutdown positione
, t ripping- t he feeder breakers on the reactor protection sgstem power distribution busesi scramming individual control rods from the back of the control room panele tripping breakers from plant auxiliary power source feeding the reactor protection systems and valving l
out and bleeding off instrument air to scram solenoid l .
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_9-valves. These actions must be taken immediately after detection of an ATWS event. Actions should also include prompt initiation of the residual heat removal system in the suppression pool cooling mode to reduce the severity of the containment conditions; and actuation of'the standby liquid control system if a scram cannot be made to occur.
The GE Owners' Group is currently developing a set of Reactivity Control Guideliness which will incorporate i
the abose steps for mitigating ATWS events. The applicant's procedure for mitigating,ATWS will be reviewed under the emergency operating procedure program as described in Section 13.5.2. The results of the staff review will be reported in a supplement to this Safety Evaluation Report.
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