Letter Sequence Other |
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Results
Other: 05000344/LER-1980-022, Forwards LER 80-022/01T-0, ML14107A285, ML19344E780, ML19347B832, ML20003E295, ML20009D463, ML20009D465, ML20028F068, ML20030D185, ML20040G122, ML20041A225, ML20126L218, ML20197J754, ML20199B423, ML20210V194, ML20235Z766, ML20235Z787
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MONTHYEARML14107A2851980-05-23023 May 1980
Memorandum & Order on Ucs 771104 Petition for Remedial Relief Re Fire Protection of Electrical Cables & Environ Qualification of Electrical Components.Reaffirms Commission 780413 Decision Re Possible Shutdown of Operating Reactors
Project stage: Other
ML19344E7801980-09-0505 September 1980
Forwards, Environ Qualification of Electrical Equipment, Master List, Revision K Per 800114 IE Bulletin 79-01B Requirements & 800829 Order for License Mod.Encl Available in Central Files Only
Project stage: Other
ML19347B8321980-09-29029 September 1980
Forwards Suppl 2 to IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. No Written Response Required
Project stage: Other
05000344/LER-1980-022, Forwards LER 80-022/01T-01980-10-31031 October 1980
Forwards LER 80-022/01T-0
Project stage: Other
05000344/LER-1980-022-01, /01T-0:on 801028,review of IE Bulletin 79-01B Resulted in Discovery of safety-related Equipment Not Meeting Environ Qualification.Caused by Change in Criteria for Environ Qualification of safety-related Equipment1980-10-31031 October 1980
/01T-0:on 801028,review of IE Bulletin 79-01B Resulted in Discovery of safety-related Equipment Not Meeting Environ Qualification.Caused by Change in Criteria for Environ Qualification of safety-related Equipment
Project stage: Meeting
ML20126L2181980-11-0707 November 1980
Environ Qualification of Safety-Related Electrical Equipment to Harsh Environs,Ie Bulletin 79-01B, Technical Evaluation Rept
Project stage: Other
ML19345B8121980-11-25025 November 1980
Responds to NRC 801001 Request for Info Re Environ Equipment Qualification Tests.Pressure Transmitter Tests Conducted by Util Transmitter Qualification Group, & Safety Valve Flow Monitoring Tested by Technology for Energy Corp
Project stage: Request
ML19341D0021981-01-31031 January 1981
Degraded Grid Protection for Class IE Power Sys,Trojan Nuclear Plant, Technical Evaluation Rept
Project stage: Request
ML20003E2951981-03-26026 March 1981
Forwards Preliminary Results of NRC Review Re Environ Qualification of safety-related Electrical Equipment.Result of Review Identified Number of Potential Deficiencies. Response Required within 10 Days of Receipt of Ltr
Project stage: Other
ML20126L2081981-05-27027 May 1981
Forwards Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Evaluation Based on Util 800307,0425,0519,0905 & 810113 Submittals
Project stage: Approval
ML20126L2121981-05-27027 May 1981
Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Equipment,Required to Mitigate LOCA Following Accident in Harsh Environ,Found Acceptable Except as Noted in Section 3
Project stage: Approval
ML20009D4651981-07-13013 July 1981
Directors Decision Under 10CFR2.206,denying Coalition for Safe Power 790517 Request for Plant Shutdown
Project stage: Other
ML20009D4631981-07-13013 July 1981
Forwards Directors Decision Under 10CFR2.206,denying 790517 Request for Plant Shutdown & Public Hearing Re Fire Protection & Environ Qualification of Electrical Equipment Issues
Project stage: Other
ML20009D4681981-07-13013 July 1981
Notice of Issuance of Directors Decision Under 10CFR2.206, Denying Coalition for Safe Power 790517 Request for Plant Shutdown
Project stage: Approval
ML20030D1851981-08-26026 August 1981
Forwards Detailed Response to NRC 810527 Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Addresses Outstanding Info in Section 3.0 & Provides Resolutions to Deficiencies in Section 4.0
Project stage: Other
ML20140B6461981-09-0909 September 1981
Reiterates 810722 Request for Documents Re Show Cause Petition on Environ Qualification of safety-related Equipment at Facility
Project stage: Request
ML20040G1221982-02-0303 February 1982
Forwards Info Requested by NRC for Equipment Environ Qualification Review.W/O Encl
Project stage: Other
ML20041A2251982-02-12012 February 1982
Advises That Addl Info Re Environ Qualification of safety-related Electrical Equipment Has Been Forwarded to Franklin Research Ctr,In Response to NRC 820112 Request
Project stage: Other
ML20041C0401982-02-17017 February 1982
Advises of Preliminary Review of Util Submittals Re Environ Qualification of TMI Action Plan Electrical Equipment. Response Should Be Sent to Franklin Research Ctr within 30 Days of Ltr Date
Project stage: Approval
ML20050A4721982-03-29029 March 1982
Forwards Editorial Changes to 810826 Response to NRC Request for Info Re Radiation Qualification Envelopes
Project stage: Request
ML20028F0681983-01-21021 January 1983
Forwards Response to NRC 821217 SER Re Environ Qualification of safety-related Equipment.Continued Safe Operation Reaffirmed & Discrepancies Noted in Section 5 of Technical Evaluation Rept Resolved
Project stage: Other
ML20197J7541986-05-0606 May 1986
Part 21 Rept 86-01 Re Limitorque Valve operator-motor Lead Insulation Exhibiting Brittlement.Motor Leads for Motor Actuators Will Be Replaced W/Properly Insulated Wire by 860801
Project stage: Other
ML20199B4231986-06-0606 June 1986
Interim Part 21 Rept Re Defects Discovered in Limitorque Auxiliary Feedwater Flow Control Valve Motor Lead Insulation.Initially Reported on 860506.Replacements Will Not Be Available Until After 1986 Refueling Outage
Project stage: Other
ML20210A6251986-09-11011 September 1986
Discusses Potential Generic Question Re Failure Potential for safety-related Valves,Per 860827 Meeting W/Util to Discuss QA Audit of Limitorque Procurement of Peerless Motors.Part 21 Related
Project stage: Meeting
ML20210V1941986-09-25025 September 1986
Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation
Project stage: Other
ML20235Z7871986-10-15015 October 1986
Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty
Project stage: Other
ML20235Z7661987-04-29029 April 1987
Confirms Telcons Establishing 870518-22 as Dates for NRC Equipment Qualification Insp.Items to Be Included in Insp Listed.Encl Withheld
Project stage: Other
1981-09-09
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s U rilandGeneralElectricCoriixviy Co. 94 Pb
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Bad D VAners Vce Presdert February 3, 1982 m
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BEC5fVED F
't Mr. Cyril J. Crane
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, EB2 D Jgg I'j Franklin Research Center The Parkway at 20th Street
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Philadelphia, PA 19103 Cy A
Dear Mr. Crane:
w Attached is the information requested by RFI-C5257-485, which was for-warded to us by the NRC.
It is our understanding that you may also require additional test reports or evaluations that may either supplement or supersede those mentioned. The information provided for each request is itemized below.
Request 1.a: Amphenol Report 123-1236; 8/23/72.
Response: Attachment I is the complete report. This report does not contain any aging documentation and therefore a material analysis was required. The materials analyzed are identified by Amphenol letter BJA:1:1:001. A copy of this letter is inserted at the back of Attachment I.
Request 1.b: Joy Report on Fan Model'No. 60-30-120.
Response: Attachment II is the applicable ' test report.
Request 1.c: Connecticut Yankee Report; 3/16/78.
Response : The report referred to is enclosed in Attachment III. This has been supplemented by the following:
a.
Qualification Tests of Terminal and Fuse Blocks; FIEL Report F-C5143; 7/17/80.
I b.
Qualification Tests of Terminal Blocks and Spliced Insulating Assemblies in a Simulated LOCA - Phase A; FRC Report F-C5022-1; 10/78.
8202110299 820203 0 o PDR ADOCK osooo g (,8 0 P
121 S.W Sairnon Street Pon:and. Oregon 97204
O W W M C0f74XNV Mr. Cyril J. Crane February 3,1982 Page two c.
Preliminary Evaluation and Examination of TMI Equipment: Terminal Blocks; Sandia National Laboratory Report SAND 80-2447A.
Copies of these documents can be provided upon request.
Request 1.d: Westinghouse Letter NC-CE-692.
Respons a : This was an incorrect reference. The letter referred to was an analysis of the effects of the post-accident chemical environment on transmitters inside Containment. The correct reference is Westinghouse letter NS-CE-719 and is included in Attachment III.
To expedite your evaluations, we should inform you that the Barton Series 300 transmitters remaining on the master list will be replaced by qualified units prior to June 30, 1982. Therefore, review of this equipment type would appear to be academic.
Request 1.e: Westinghouse Letter NS-CE-69.
Response: This was an incorrect reference. The letter referred to was a failure-mode analysis for safety-related solenoid valves in an accident environment. The correct reference is Westinghouse letter NS-CE-755 and is included in Attachment III.
Request 2:
The postulated post-accident (HELB) environmental profiles are not specified in the FSAR. FRC requests that the licensee provide these profiles for all harsh environments.
Response
The two areas susceptible to harsh temperature and pressure
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environments due to a high-energy line~ break are Containment and the main steam support structure.
As allowed by Section 4.2.1 of the DOR guidelines, and explained in our August 26, 1981 SER response, the LOCA profiles described in the FSAR reflect the HELB requirements for Containment.
For the main sterm support structure, we had previously identified a profile with a maximum temperature and pressure of 225'F and 4.3 psia, res pectively. Subsequent analyses show Figures 1 and 2 (in Attach-ment III) to be the environment that safety-related equipment must endure for a high-energy line break in the main steam support structure.
The relatively low values are due to the separation of safety-related equipment from high-energy lines and the compartmented design of the main steam support structure.
Portlivid Genieral Bechic Corry)arly Mr. Cyril J. Crane February 3, 1982 Page three Although the enclosed reports are not the originals, we will require their return. Should you require additional information from our Qualification Central File to adequately perform your evaluations, please notify us.
Sincerely, t ! _' r' Bart D. Withers Vice President Nuclear Attachments c:
Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 U. S. Nuclear Regulatory Commission wo/ attach Mr. Lynn Frank, Director State of Oregon Department of Energy wo/ attach e
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