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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January 14, 1980 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. A. Schwencer, Chief Operating Reactors Branch !/1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Your letter of November 19, 1979 provided the interim NRC position for Containment purge and vent valve operation pending resolution of isola-tion valve operability. We have completed a review of your letter and provide the following in response.
1.
Whenever Containment integrity is required, emphasis has been placed on operating the Containment in a passive mode as much as possible.
Purging and venting times are main-tained as low as achievable.
Purging and venting is per-formed only when there is an established need to improve working conditions to perform a safety-related surveil-lance or maintenance activity and to maintain Containment pressure within Technical Specification limits.
2.
The 54-in. Containment purge and vent isolation valves are maintained closed during Plant operation (Modes 1, 2, 3 and
- 4) as described in my letter to you dated November 19, 1979.
>A modification to the purge system (ie, installation of a mini purge system) is under development. Valves used in the mini purge system will be qualified in accordance with the guidelines provided in your September 27, 1979 letter.
Qualification of the existing 54-in. valves with regard to operability during and following a LOCA is not planned at this time; these valves will remain in the closed position during operation.
a.
With regard to the 8-in. Hydrogen Vent System 9
motor-operated isolation valves, the valve manu-1 facturer (BIF) has informed us that the valves S
do 90 012 0 0 M l~785 187
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h :~ l i~ d 3 5. K '^! E '."."~ C 1.T ',2..l Mr. A. Schwencer January 14, 1979 Page 2 can be safely closed under the most severe design basis accident flow condition loading without dam-aging critical valve parts from an open position of 50 degrees. Therefore, as an interim measure, PGE will limit the opening of the Hydrogen Vent System isolation valves to 50 degrees.
This will be fully implenented by February 1,1980.
On a long-term approach, we are pursuing complete quali-fication of the 8-in. Hydrogen Vent System isola-tion valves with BIF.
b.
In the Trojan plant design, a Containment Isolation Signal (CIS) will close the Hydrogen Vent System isolation valves. A review of all ESFAS circuits incorporating the manual override feature was con-ducted previously and the result was submitted to the NRC in a letter dated January 3, 1978.
It was concluded that there are no instances when overrid-ing of one ESFAS circuit will cause the bypass of any other ESFAS signal.
In addition, the high Con-tainment pressure signal will also close the valves and cannot be overriden.
Please note that Trojan Technical Specifcation 4.6.4.3 (Appendix A to FOL NPF-1) requires opening the 8-in. Hydrogen Vent System isolation valves for 15 min once every 31 days and verifying 140 cfm +10 percent every 18 months. Calculations have been performed to show that opening of these 8-in. valves no more than 50 degrees will have a negligible effect on the flow rate (140 cfm). However, the 18 month surveillance test will be performed during the forthcoming refueling outage to verify this flow rate.
Sincerely, E&W m.
k_ fLincolad
.a.
Vice President Enginee ring-Cons t ruc tion c:
Mr. Lynn Frank, Director State of Oregon Department of Energy 1785 188