Letter Sequence Approval |
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Results
Other: 05000344/LER-1979-008, Forwards LER 79-008/01T-0, 05000344/LER-1979-008-01, /01T-0 on 790521:during Review of Containment Purge Sys Design,Containment Purge Supply Ducting Was Overpressurized.Caused by Faulty Design Which Does Not Allow for Effects of Dynamic Forces Following LOCA, ML19210D622, ML19259A762, ML19262B978, ML19263E231, ML19270H773, ML19282D346, ML19318A658, ML19320B144, ML19323D025, ML20028F484, ML20039F788, ML20244A570
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MONTHYEARML19289C2151978-11-28028 November 1978 Forwards List of Requests for Design Changes & Other Work Items Suppl Previous Lists.Items on This List Will Not Affect Load Carrying Capability of Any Major Shear Wall Project stage: Request ML19259A7621979-01-0303 January 1979 Forwards Data Re Containment Purging During Modes 1,2,3 & 4 Taking Into Account Operational Capabilities,Radiological Controls,Respiratory Requirements & Safety Considerations. Seeks Containment Purging of Up to 90 H Per Year Project stage: Other ML20244A5701979-03-30030 March 1979 States Inability to Respond to Positions 1.g to 5.b of Branch Technical Position Lsb 6-4 by 790401.Requests 60-day Extension to 790601,in Order to Provide Accurate Assessments of Containment Purging & Determine Proper Corrective Action Project stage: Other ML19282D3461979-05-21021 May 1979 Ro:Util Cannot Assure Containment Ventilation Sys Supply Valves Will Remain Leak Tight Following Postulated LOCA While Ventilating Containment.Analysis Shows Damage to Sys May Result Project stage: Other 05000344/LER-1979-008, Forwards LER 79-008/01T-01979-05-31031 May 1979 Forwards LER 79-008/01T-0 Project stage: Other 05000344/LER-1979-008-01, /01T-0 on 790521:during Review of Containment Purge Sys Design,Containment Purge Supply Ducting Was Overpressurized.Caused by Faulty Design Which Does Not Allow for Effects of Dynamic Forces Following LOCA1979-05-31031 May 1979 /01T-0 on 790521:during Review of Containment Purge Sys Design,Containment Purge Supply Ducting Was Overpressurized.Caused by Faulty Design Which Does Not Allow for Effects of Dynamic Forces Following LOCA Project stage: Other ML19263E2311979-05-31031 May 1979 Responds to NRC Re Containment Purging During Normal Plant Operation.Provides Addl Info on Isolation Valve Closure & Seismic Category I Hydrogen Vent Sys Project stage: Other ML19209C3961979-09-27027 September 1979 Forwards Request for Addl Info Re Plant Control Bldg Design Mods.Encl Questions Comprise NRC Positions Re Acceptable Util Response Project stage: Request ML19210D6221979-11-19019 November 1979 Responds to NRC Providing Guidelines for Qualification of Containment Purge & Vent Valves & Requesting Commitment to Implement Valve Qualification Program.Development of Purge Sys Mods Underway Project stage: Other ML19270H7731979-11-19019 November 1979 Forwards Interim Position on Containment Purging & Venting During Normal Operation,Pending Resolution of Isolation Valve Operability.Commitment to Comply W/Encl Position Should Be Submitted within 45 Days Project stage: Other ML19262B9781980-01-14014 January 1980 Responds to NRC 791119 Position Re Containment Purge & Vent Valve Operation.Purging & Venting Performed When Needed to Improve Working Conditions Project stage: Other ML19262C4321980-02-0505 February 1980 Forwards Response to NRC 791003 Generic Request for Info Re Auxiliary Feedwater Flow Requirements.Info Pertains to Design Bases for Auxiliary Feedwater Sys Project stage: Request ML19309E4571980-03-18018 March 1980 Forwards Request for Addl Info Re Containment Purge Generic Issues. Addl Info Needed to Continue Review of Project stage: RAI ML19309H4621980-05-0707 May 1980 Forwards License Change Application (Lca) 60,replacing Lca 51.Certificate of Svc Encl Project stage: Other ML19323D0251980-05-12012 May 1980 Notifies That Info Re Containment Purge Sys,Requested in NRC & 800507 Telcon,Will Be Submited by 800615, in Conjunction W/Ie Bulletin 80-06 Review Effort Project stage: Other ML19318A5841980-06-16016 June 1980 Forwards Response to NRC Re Implementation of Five Addl TMI-2 Related Action Items Project stage: Other ML19318A6581980-06-16016 June 1980 Forwards Addl Info Re Containment Purge Sys Requested by NRC .Provides Response to Questions & as-built Tabulation of Engineered Safety Features Equipment Required to Operate Automatically Following Accident Project stage: Other ML19320B1441980-07-0303 July 1980 Submits Clarification of 800616 Addl Info Re Containment Purge Sys,Submitted in Response to 800318 Request.High Radiation Signal Can Be Overridden Manually by Raising Setpoint or Holding Reset on Radiation Monitors Panel Project stage: Other 05000344/LER-1980-017, Forwards LER 80-017/03L-01980-09-0505 September 1980 Forwards LER 80-017/03L-0 Project stage: Request ML19351D3331980-09-24024 September 1980 Advises That Util Commitments Re NRC 791119 Interim Position on Containment Purging Venting Pending Resolution of Isolation Valve Operability Are Acceptable.Safety Evaluation & Tech Spec Changes Will Be Provided,If Required Project stage: Approval ML19337B2171980-09-29029 September 1980 Notifies of Delay in Implementation of TMI-2 Lessons Learned Items Scheduled for 810101 Until Resolution of Matl Delivery Problems.Summary of Util Commitments Per NUREG-0578 & Comments on NRC to Licensees & Applicants Encl Project stage: Other ML19339B0061980-10-23023 October 1980 Forwards Safety Evaluation Re Implementation of Recommendations for Auxiliary Feedwater Sys.Requests Response to Two Unresolved Items Identified in Rept within 45 Days Project stage: Approval ML19339B0091980-10-23023 October 1980 Safety Evaluation Re Implementation of Recommendations for Auxiliary Feedwater Sys Project stage: Approval ML19343B8041980-12-23023 December 1980 Responds to NRC Requesting Response to NUREG-0737 Re Implementation of TMI-2 Action Items.Util Intends to Meet Requirements & Schedules Except Where Stated.Hardware Availability Problems Could Cause Delays Project stage: Other ML19350A9121981-03-11011 March 1981 Responds to 810127 & 0310 Requests for Westinghouse Schematic Diagrams for Review of Engineered Safety Features for Nrc.W/O Encl Project stage: Other ML19350A9341981-03-12012 March 1981 Responds to NRC Re Containment Purging Issue. Valves Will Be Qualified,Per NRC 790927 Guidelines,To Justify Complete Permanent Opening for Containment Venting. Completion of Any Resulting Mods Expected by June 1982 Project stage: Other ML20003H9401981-05-0404 May 1981 Advises That Mods Needed Re TMI Action Item II.F.1.6, Containment Hydrogen Monitoring,To Achieve Acceptable Levels of Reliability Based on NUREG-0737 Criteria.Three solenoid- Operated Valves Will Be Added Inside Containment Project stage: Other ML20260H6311981-05-15015 May 1981 Schematic Diagram:Containment Sump Pumps Discharge Isolation Valve M04180, as-built.Sheet 2 Project stage: Other ML20260H6351981-05-15015 May 1981 Schematic Diagram:Containment Sump Pumps Discharge Isolation Valve CV4181, as-built.Sheet 1 Project stage: Other ML20009C9641981-07-17017 July 1981 Suppls 801223 Response to NUREG-0737,Item II.B.1 Re Reactor Coolant Vent Sys.Also Submits Info on Items II.D.1,II.E.1.2, II.E.4.2,II.K.3.5,II.K.3.25,II.F.1.5,II.F.2 & III.A.2 Project stage: Other ML20031D4001981-10-0202 October 1981 Responds to NRC 810728 Request for Valve Qualification Data & Tech Spec Changes Re Containment Purge & Vent Valves & Containment Pressure Setpoint.Qualification Data for 8-inch Valves Not Available.License Change Application Forthcoming Project stage: Request ML20260H6241981-10-14014 October 1981 Schematic Diagram:Containment Purge Isolation Movs, as-built Project stage: Other ML20031H1461981-10-21021 October 1981 Forwards Supplemental Info Re Implementation Status of TMI Action Items II.B.3,II.F.1.1,II.F.1.2,II.F.1.6,II.F.2, II.D.1.2,II.K.3.1,II.K.3.5 & III.A.2.Items Will Be Completed by 820801 Project stage: Supplement ML20038A6311981-11-0606 November 1981 Forwards Addl Info Requested in NRC Re Reactor Vessel Level Indication Sys Being Installed at Facility Project stage: Other ML20039C6481981-12-0202 December 1981 Draft Override & Reset of Control Circuitry in Ventilation/ Purge Isolation & Other ESF Sys Project stage: Draft Other ML20236A0681981-12-0404 December 1981 Safety Evaluation Re Containment Purging & Venting During Normal Operation of Plant.Purge/Vent Sys Design & Operating Practices for Facility Acceptable Subj to Implementation of Recommended Actions Project stage: Approval ML20039F7881981-12-18018 December 1981 Requests Review & Comments Re Encl Technical Evaluation Rept Concerning Containment Venting & Purging.Response Requested within 60 Days of Receipt of Ltr Project stage: Other ML20039D4801981-12-28028 December 1981 Forwards Supplemental Info to Util Re Implementation of NUREG-0737 Items Requiring Licensee Action by 820101 Project stage: Supplement ML20260H6371981-12-30030 December 1981 Schematic Diagram:Sample & Containment Isolation Valves, as-built Project stage: Other ML20260H6291981-12-30030 December 1981 Schematic Diagram:Containment Purge Isolation Cvs, as-built Project stage: Other ML20260H6451982-01-0606 January 1982 Schematic Diagram:Sample Isolation Valves Project stage: Other ML20260H6421982-01-0606 January 1982 Schematic Diagram:Rcdt Sample Isolation Valve Project stage: Other ML20040E9801982-01-29029 January 1982 Provides Addl Clarification of TMI Action Items II.F.1.1 & II.F.1.2 Re Capability of Radioactive Gaseous Waste Sys & Isokinetic Sampling,Per NRC .Diagram of Waste Gas Sys Recycle Vent Encl Project stage: Other ML20040H3281982-02-12012 February 1982 Forwards Response to NRC 811204 Request for Info Re Operation & Testing of Containment Purge & Hydrogen Vent Valves Project stage: Request ML20260H6501982-02-24024 February 1982 Schematic Diagram:Sample & Containment Isolation Valves Project stage: Other ML20049J6151982-03-0404 March 1982 Advises That TMI Action Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures & Challenges, Resolved Based on 801223 & 810102 Responses Project stage: Other ML20042B0051982-03-12012 March 1982 Forwards Response to NRC Re Acceptability of Facility Esf.Eight Nonproprietary & Three Proprietary Oversize Drawings Encl.Aperture Cards in Pdr.Proprietary Drawings Withheld (Ref 10CFR2.790) Project stage: Other ML20052D1261982-04-28028 April 1982 Forwards Supplemental Info Re Implementation Schedules for Outlined NUREG-0737 TMI Action Items in Response to Generic Ltr 82-05.Schedules for Items II.B.3 & II.F.1 Will Be Extended Due to Vendor Delays Project stage: Supplement ML20052F5451982-05-0707 May 1982 Responds to 820224 Request for Addl Info on NUREG-0737, Item II.B.1 Re RCS Vent.Design Parameters & Max Rate of Reactor Coolant Through Reactor Vessel Head Vent Sys Flow Restriction Orifices Provided Project stage: Request ML20051M2851982-05-10010 May 1982 Forwards Addl Info Re NUREG-0737 Action Items I.A.2.1, Upgraded Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage,Per NRC 820318 Request Project stage: Other 1981-10-02
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i SAFETY EVALUATION REPORT FOR CONTAINMENT PURGING AND VENTING DURING y
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' NORMAL OPERATION OF THE TROJAN NUCLEAR PLANT (Docket No. 50-344)'
I.
INTRODUCTION A number of events have occurred over the past several' years which directly relate to the practice of containment purging and venting 'during norma'l plant operation. These. events have raised concerns relative to potential failures affecting the purge penetrations which could lead to degradation in containmen.t integrity, and, for PWRs, a degradation in ECCS performance. By letter dated November 28, 1978, the Commission i
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(NRC) requested all Licensees of operating reactor's to respond to certain generic concerns about containment purging or venting during normal plant operation. The generic concerns were twofold:
(1)
Events had occurred where licensees ' overrode-or bypassed
- 1 the safety actuation isolation signals to the containment isolation valves..These events were determined to be abnormal occurences and were characterized in our report to Congress in January 1979.
(2)
Recent Licensing reviews have required tests or analyses.to show that containment purge or vent valves would shut without degrading containment integr'ity' during the dynamic loads of a design basis loss of coolant accident kDBA-LOCA).
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Pd.The NRC position of the Novembdr 1978 ~ Letter requested Licensees to cease.
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purging ' for venting) of containme'nt or, Limit purging (or venting) to an.
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{j absolute. minimum.. Licensees who elected 'to purge (or; vent) the. containment.
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'. Aere requested to.' demonstrate thac'ty containment purge (or! vent), system?
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[O ' design met the criteria outlined.in :the MC Standard Review Plan '(SRP)' 6.2.4,
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. h '/ Revision 1, andthe associated Br:anch Technical Position (BTP); CS8'6-$
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T'.5 ref ge and vent systems at the' Trojan plant konsist of. a" 54-inch purge a
, f. srstem f or purging.the containment atmosphere to allow personnel access, y,
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s1d a 8-inch vent system for maintaining the ebntainment pressure within a
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I' fphreribed range during normal operation and for oost-accident a'tmosphere I
In addition, two 4000 s,fm iodir e, filtration units are provided-
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insicie the containment to aic in ruoving airborne radioactivity-that may it1
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r be released f rom the reactor coolant system;during normal operation.
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f The Licensee i:esponded to the NRC positio,n letter of November 1978 by 4
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, stating that the 54-inch containment purge-system isolation' valves would be n
, i a,aintained in the closed position (uring operation.(Modes.1, 2, 3' and 4).
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s The 8-inch vent system isolation valves wiLL be used for purging the containmerw atmosphere. to attd6 perso el access and to maintain.the containment pressure > within a prescribed range during normal operation..The:
7 Vice isee ind4 hated that an inab'itity to purge would. Lead to. significant -
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incre$ des in pLbnt unavailability, increase tha airborne activity levels in
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The closure time for the 6-inch vent system isolation valves,, including instrumentation-delays, wiLL not exceed 5 seconds. Therefore, containment purging concurrent with a LOCA wiLL not result in a decrease in the containment pressure to the extent that ECCS performance would be adversely -
affected.
A debris screen will be provided inboard of each ~of the inside containment isolation valves. This wiLL provide added assurance that the vent system isolstion valves will not be prevented from ' closing, should they be in the open position at the onset of a LOCA.
l III CONCLUSIONS f.
We have reviewed the Trojan plant purge and vent systems against the provisions of BTP CSB 6-4, Revision 1, " Containment Purging During Power Operation." Although the Licensee provided information to justify purging /
venting without limitation through the 8". hydrogen vent'aystem during power
[
~operation, purging / venting should be limited, because the plant is inherently safer with closed purge / vent valves than with open lines which require valve.
action to provide containment integrity.
We, therefore, have concluded that the licensee should limit usage of the vent sys' tem for safety purposes.
Also, we have concluded that the licensee should propose a change to.their Technical Specifications which would require that the 54-inch purge isolation valves 4
be maintained in the Locked closed position during plant operating Modes 1 J
through 4.
Maintaining these valves closed wiLL preclude the release of radioactivity to the environment via the containthent purge system, should a LOCA occur.,
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IIn addition, as.a result-of numerous. reports on the unsatisfactory
.a performance of resilient. seats in butterfly-type _. isolation. valves:due.to' seal deterioration, periodic leakage integrity tests of butterfly. isolation' 4
valves-in purge / vent systems. are necessary. - Th'erefore, tha licensee s'hould' also propose a Technical Specification for testing these ' alves in accordance-v with the.following testing frequencies:.
, ?)
i a)
"The leakage jntegrity' test's: of the 54-inch isolation valves in the J
j containment purge ines shaLL be conducted at - Least once every 'six 1
months."
b)
"The Leakage integrity tests of the 8-inch isolation valves in the.
vent Lines shaLL be conducted at least once every three months."
1 The purpose of the. Leakage integrity' tests of the isolation valves in the l
i containment purge and vent lines is to identify excessive degradation of.
1 the resilient seats for these vales. Therefore,- they need not be conducted -
l with the precision required for the Type C isolation valve tests in 10 CFR Part 50, Appendix J.
These tests would be performed in addition to the-q 4
quantitative Type C tests required by Appendix J and would not relieve the.
licensee of the responsibility,to. conform to the requirements of Appendix J.
i j
Subject to successful implementation of the above re' commended actions,' we find the purge / vent system design and operating practices for the Trojan plant to be acceptable.
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