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| | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT | | | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:08291, TAC:42594, TAC:44892, TAC:8291 |
| | | stage = Approval |
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| I. INTRODUCTION | | 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 i | | . 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 i |
| in ECCS performance. By letter dated November 28, 1978, the Commission | | in ECCS performance. By {{letter dated|date=November 28, 1978|text=letter dated November 28, 1978}}, the Commission |
| ) | | ) |
| (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: | | (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: |
Letter Sequence Approval |
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MONTHYEARML20244A5701979-03-30030 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 ML20260H6351981-05-15015 May 1981 Schematic Diagram:Containment Sump Pumps Discharge Isolation Valve CV4181, as-built.Sheet 1 Project stage: Other ML20260H6311981-05-15015 May 1981 Schematic Diagram:Containment Sump Pumps Discharge Isolation Valve M04180, as-built.Sheet 2 Project stage: Other ML20260H6241981-10-14014 October 1981 Schematic Diagram:Containment Purge Isolation Movs, as-built Project stage: 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 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 ML20260H6501982-02-24024 February 1982 Schematic Diagram:Sample & Containment Isolation Valves Project stage: Other ML20197G4831984-06-0101 June 1984 Forwards Safety Evaluation Supporting Containment Hydrogen Vent Sys Isolation Valves.Generic Evaluation of Radiological Consequences of Accidents While Purging & Venting at Power Also Encl Project stage: Approval 1981-12-04
[Table View] |
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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
[Table view] |
Text
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i SAFETY EVALUATION REPORT FOR CONTAINMENT PURGING AND VENTING DURING y
^
' 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 i
in ECCS performance. By letter dated November 28, 1978, the Commission
)
(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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M 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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- 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?
[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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a T'.5 ref ge and vent systems at the' Trojan plant konsist of. a" 54-inch purge
, ,+-f. srstem f or purging .the containment atmosphere to allow personnel access, y, q s1d a 8-inch vent system for maintaining the ebntainment pressure within a
,, %, ' i t I I' fphreribed range during normal operation and for oost-accident a'tmosphere
,~ ,
clesnup. In addition, two 4000 s,fm iodir e , filtration units are provided-
, d f insicie the containment to aic in ruoving airborne radioactivity- that may
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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 .'(u in
, stating that the 54-inch containment purge-system isolation' valves would be
, i ,
a,aintained in the closed position (uring operation .(Modes.1, 2, 3' and 4).
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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:
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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
/ 1 the contai e'nt, and increase personnet exposures.
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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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- l IIn addition, as.a result-of numerous. reports on the unsatisfactory l
.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 v in accordance- ,
I 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- 1 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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