ML20244D310

Forwards SER & SALP Input for Util 831107 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Deficiencies in Response Noted.Recommends That Util Take Necessary Action to Correct Deficiencies

ML20244D310
Person / Time
Site:	Pilgrim
Issue date:	04/18/1985
From:	Beckham D Office of Nuclear Reactor Regulation
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML20149B797	List: BECO-84-061, Forwards INPO 84-010, Vendor Equipment Technical Info Program, Nuclear Operations Procedure,Operating Experience Review Program & Vendor Manual Control,In Response to Generic Ltr 83-28,Section 2.2.2 BECO-87-113, Submits Addl Info in Support of Util 870529 Proposed Tech Spec Change Re Standby Liquid Control Sys for Compliance W/ 10CFR50.62(c)(4),ATWS Rule IA-87-644, Forwards SER & SALP Input Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Identifying, Classifying & Treating Components Required for Performance of Reactor Trip Function as safety-related ML20236D144 ML20236Y028 ML20236Y139 ML20236Y336 ML20236Y345 ML20236Y350 ML20236Y359 ML20236Y371 ML20236Y399 ML20244D310 ML20244D452 ML20244D774 ML20244E058 ML20244E375
References
FOIA-87-644 GL-83-28, TAC-52786, NUDOCS 8504290261
Download: ML20244D310 (2)

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., ICB R/F AFh 161985 DHFS R/F (2) isocher Irrccker DShum f(MORANDtM FOR: Dennis Crutchfield. Assistant Director for Safety Assessmert Division of Licensing FROM: Don H. Reckham, Acting Deputy Director Division of Human Factors Safety

SUBJECT:

SAFETY EVALUAT!DN REPDRT FOR PILGRIM STAT!0ft, GEtlERIC LETTER 83-28, ! TEM 1.1 (POST-TRIP REVIEW) (TAC NO. 52786)

Ry letter dated Nnvenber 7, 1983, the licensee of Pilgrim Station responded to Generic letter 83-28 with regard to reouired actions based on generic implications nf Salem ATWS events. The enclosed SER and SALP were prepared by the Licensee Qualifications Branch based upon TFR input from its contractor, Science Applications International Corporation (SAI), af ter having reviewed tha applicable portions of the licensee's response to Cereric Letter 83-2R.

l We find that the licensea's response does not meet the guidelines developed for post-trip review in the following arees:

1. The criteria for deteminino the need for indepevant asseesment cf the event.

?. The mathnd and criteria for renoari.No the ovent with expected plant perfoma rca.

3. A systenatic safety assassrwnt progran to assets unscheduled reactor trips.

We recorryrd that the licensee take necessary action to enrrect the deficiencies noted above, which are discussed in creater detail in 5 action 111 ef the SER.

Acceptable responses to the 9 hove noted deficiencies are required be' ore wn can complete nur review of the licensco's Post-Trip Raview Pronran and Procedure for Pilgrin Station. We will review thasa resonnses whnn received i and rrport our findingt in a supplment to this SER.

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D. Crutchfield 2 APR 18 Ik i

l This review hat been conducted by D. Shum (x28906) and SAI, There are no known dissenting professional opinions on this matter.

Don /9 Ar. ting Deputy Director H Beckham, Divis on of Human factors Safety

Enclosures:

1. Safety Evaluation

2. SALP Evaluation ec: A Bournia J. Zwolinski G. Holahan