Letter Sequence Other |
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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
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
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
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
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
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
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
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
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
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
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
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
ML20028F4841983-01-25025 January 1983
Forwards Qualification Info for Replacement of Hydrogen Vent Valves,Per 811002 & 820212 Commitments
Project stage: Other
1980-03-18
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Portland Ceneral Electric Company May 21, 1979 BDW-490-79 Trojan Nuclear Plant P.(1 Box 435 Rairder, Oregon 97048 Mr. R. H. Engelken, Director Nuclear Regulatory Commission, Region V 1990 North California Blvd.
Walnut Creek, California 94596
Dear Sir:
Subject:
Immediate Report of Reportable Occurrence This letter is a follow-up to a telephone report made by Mr. W.
S. Orser, Engineering Supervisor, to Mr. Mike Malmros, NRC Inspector, on May 21, 1979, concerning a situation where we cannot assure that the containment ventila-tien system supply valves will remain leak tight following a postulated loss of coolant accident (LOCA) while ventilating the containment. 'This situation was discovered as the result of a study undertaken to respond to a letter from Mr. A Schwencer of the Nuclear Regulatory Commission to Mr. C. Goodwin, Jr. dated November 28, 1978. A preliminary analysis shows that the pressure transient following a LOCA may result in damage to the containment ventilation system supply ducting creating a potential for portions of the damaged duct to interfere with the closing of the contain-ment ventilation system supply isolation valves.
This occurrence will be reported to the Nuclear Regulatory Commission as a Licensee Event Report as requested by your office and in accordance with our Technical Specifications.
Si,ncerelyf7
)
w C
O ' B. D. Withers Plant Superintendent BDW JCP:ga c:
J. L. Williams C. Goodwin, Jr.
D. J. Broehl R. L. Sullivan S. R. Christensen S. L. Loy D. F. Kielblock L. Frank, Director DOE /EFSC L. W. Erickson Office of Management Information Shift Supervisors and Program Control Plant Review Board NRC Resident Inspector Nuclear Operations Board J. H. Braggs, Bechtel Trojan Operating Committee File 93.24a M
7905310 360
- M
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