05000289/LER-1982-004

LER 82-004:on 820413,EPRI Tests on Pressurizer Code Safety Valves Revealed Failure to Determine Ability of Valve to Perform Under Feed & Bleed Cooling If Pressurizer Power Operated Relief Valve Isolated.Investigation Underway

ML20054D188
Person / Time
Site:	Three Mile Island
Issue date:	04/14/1982
From:	Toole R GENERAL PUBLIC UTILITIES CORP.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 5211-82-090, 5211-82-90, LER-82-004, LER-82-4, NUDOCS 8204220423
Download: ML20054D188 (1)

LER-2082-004,

Event date:
Report date:
2892082004R00 - NRC Website

text

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GPU Nuclear P O. Box 480 Q Mf Middletown Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:

April 14, 1982 5211-82-090 -

A to D

Of fice of Inspection and Enforcement S Attn: R. C. Haynes SIECEIVED 3 Region I, Regional Administrator >

U.S. Nuclear Regulatory Commission - APR 211982>- --

631 Park Avenue {IIE"g '

King of Prussia, PA 19406 nK If

Dear Sir:

_ g Three Mile Island Nuclear Station, Unit 1 (D1I-1)

Operating License No. DPR-50 Docket No. 50-289 Licensee Event Report No.82-004 This telecopy is to confirm the conversation between Mr. D. R. Haverkamp, Region 1 NRC and Mr. M. A. Nelson, PORC Chairman, TMI-1, at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on April 13, 1982, that an item was discovered which is considered prompt reportable per TMI-1 Techni-cal Specification 6.9.2.A (9).

Pressurizer code safety valves, representative of the DiI-1 Dresser model 31739A, were subjected to water flow during the EPRI valve tests being conducted in rela-tion to NUREG 0737 task action plan item II.D.l. Although the EPRI tests were terminated prior to completion for long inlet piping configuration, the final EPRI results which were recently made available require evaluation to determine the ability of the Hil-1 safety valves to perform under feed and bleed cooling if the pressurizer PORV is isolated. Licensee is currently evaluating these test results (which NRC has received from EPRI as well) to determine whether and to what extent the EPRI test conditions are representative of Licensee's configuration. This re-port is being submitted pursuant to Technical Specification 6.9.2.A (9) in recogni-tion that further analysis, evaluation and possible modifications may be necessary to prevent the occurrence of an unsafe condition at TMI-1 in the event this backup mode of feed and bleed cooling were to be utilized at HII-1. Our schedule for cor-rective action will be reported in a followup report. TMI-l continues to remain in an extended cold shutdown condition.

Additional information and proposed corrective action will be forwarded in the fol-lowup report within 14 days.

Sincerely, 1

I J. Toole 8204220423 820414 operations & Maintenance l PDP ADOCK 05000289 Director, DiI 1 S PDR RJT/ MAN /amh cc D. R. HaverkampGPU Nuclear is a part of the General Pubhc Utihties System l$

L. Barrett h