ML20237J351

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Forwards Questions Provided to Site Mgt by Resident Inspectors on 870807 Re Evaluation of Appropriateness of Maint Activities Recently Performed on Feedwater Isolation Valve & Atmospheric Steam Dump Valve
ML20237J351
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 08/10/1987
From: Zimmerman R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Baskin K
SOUTHERN CALIFORNIA EDISON CO.
References
NUDOCS 8708180111
Download: ML20237J351 (3)


Text

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- ,c AUG 101987..

IDocket No. 50-362.

Southern California Edison Company P. 0. Box 800 2244 Walnut Grove Avenue L, 'Rosemead,-California 92770 L . Attention:' 'Mr. Kenneth P. Baskin, Vice President.

, Nuclear. Engineering- Safety and Licensing -

Gentlemen:

Enclosed for. your information is a copy of questions provided to your site management by o k residentiinspectors on August.7,~1987. The information requested.will be used by our inspection staff .in evaluating the. appropriate-ness 'of maintenance activities:recently performed o'n a feedwater isolation valve 'and an atmospheric steam dump. valve in San Onofre Unit 3.

Since we anticipate that the information requested by the enclosed questions will' be provided directly by the San Onofre Plant Staff, a reply to-this '

letter is not required.

Sincerely, I R. P. Zimmerman, Chief

' Reactor Projects Branch cc w/ enclosure:

F. R. Huey, SRI H. B. Ray, Vice President (San Clemente)

H. E. Morgan, Station Manager-(San-Clemente)

State of California

-. bec' w/ enclosure:

'P. Johnson A. Johnson

'A. Chaffee RVf) p'E PMn RZimmerman 08//o/871 08/**/87 6PY REQURESTED DR OPY

'YE.S/ 0 YESh YES/ 0 8708180111 870s10 PDR ADOCK 05000362 \\

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JT00077 SPECIE 1C_CDUCEBNSL RE1_. hDY.. .( 3HY:M191_6 F.W2 Y..L3HY:1M H_MA.1NTENANCE

,1 . _ Basis;for concluding 1. hat. FWIV repairs conducted on April 10 and April 24,.1987,- were not in violati.on of Technical ~ Specification 3.3.2.

'2 . Basis for conc 3uding that the FWlV repairs conducted on April'10 and April 24, 1987, did not involve an unreviewed safety questions, including the following considerations:

a; Accident analycis:in UFSAR

b. Plant operation with the FWIV blocked open
c. Reduction !3 n .the margin of safet y of Technical Specification 3.3.2'

' 3 '. -Basis for concluding;that the ADV repajr conducted from March 1 through March 9, 1987, did not involve an unreviewed safety question, . including the following considerations:

.a. . Accident ana).y,ci in UFSAR i

b. Plant operat. ion with ADV isolated
c. Reduction in the marcin of safety of Technical

-Specification 3.4.5.2 (Operational Leakage)

With regard to these concernn please provide two (2) copies of '

applicab.le documentation and station implement.ing procedures for the following:

a. QA program requirements for 50.59 review including any specific requirements for maintenance activiticc, TFM, and NCR dispositions

-b. Saf ety Analysen 1. hat were performed f or the following:

(1) MShH incide containment (2) FSLH .insi de cont ai nment (3) MS).B outsi de cont.a i nment upstream of the MGIV (4) W,0).i c>utmide c o n t.i4 i n m e n t downutream of the b:m ku p FW:V (5) SGTR wi th ourrurrent LOP 1

y . ,

c. Backup or-supporting information of UFSAR Eystem Description & Accident Analyses that may relate to this issue (FW1V & ADV Bafety Evaluations)

, d. Emergency Op Procedures application to the operation of the ADV's, and any procedures for manual operation of the 31.enm generator code safeties

e. QA program requirements for post maintenance testing, and specific requirements for the F'".V maintent.nce activition, including requirements for 60. d review of maintenance activities
f. Work packages for repair & TFM on FWIV 3HV-4048-(April 10 and April 24, 1987), and for repair of ADV 3HV-8419'(March-1 through March 9, 1987)
g. 50.59' reviews that were conducted for FWIV 3HV-4048 repairs and for ADV 3HV-8419 repair listed in "f" etbove-y s J

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