ML19326C365

Requests Resolution of Disagreement Between Util & IE Inspectors Re Interpretation of Tech Specs 6.5.1.6 Concerning Plant Safety Committee Review Responsibilities

ML19326C365
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/10/1978
From:	David Williams ARKANSAS POWER & LIGHT CO.
To:	Desiree Davis Office of Nuclear Reactor Regulation
References
1-018-6, 1-18-6, NUDOCS 8004220907
Download: ML19326C365 (3)

Text

. . - . . . - . . . .- -...-.---.- - ....---. . . -

p 3

/

, REGULATORY INFORMATTON DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-313 REC: DAVIS D K ORG: WILLIAMS D H DOCDATE: 01/10/78 NRC AR PWR & LIGtiT DATE RCVD: 01/18/78 DOCTYPE: LETTER NOTARIZED. NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 0 REOUESTING NRC TO AID T*1 AP&L 1

PLANT NAME: ARKANSAS - UNIT 1 REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL:

• o**+++********** DISTRIBUTION OF THIS MATERIAL Is AS FOLLOWS ******************

GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE AOO1)

FOR ACTION: BRANCH CHIEF DAVT9**LTR ONLY(7)

^

7 INTERNAL: REG FILE **LTR ONLY(1) NRC PDR**LTR ONLY(1) 7 '- "- ' - ~ ~ l

. 2. - - OELD**LTR ONLY(1) l HANAUER**LTR ONLY(1) CHECK **LTR ONLY(1)

EISENHUT**LTR ONLY(1) SHAO**LTR ONLY(1)

BAER**LTR ONLY(1) BUTLER **LTR ONLY(1)

GRIMES ++LTR ONLY(1) J. COLLINS **LTR ONLY(1)

J. MCGOUGH**LTR ONLY(1)

EXTERNAL: LPDR'S RUSSELLVILLE, AR**LTR ONLY(1)

TIC **LTR ONLY(1)

NSIC++LTR ONLY(1)

ACRS CAT B**LTR ONLY(16)

DISTRIBUTION: LTR 40 ENCL 0 CONTROL NBR:

SI7E: 2P 3iii6t13005g Q

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • THE END **********************************o b

004 220 f6 y

k.  %.- emha-- h3- e e-- ,*- m

- - - es eism

_a,' -m

~

REGB.TOlY LMIRECOPY H ELPING BUILO A R KA NSA S ARK ANS AS POWER & LIGHT COMPANY PO. sox 551 UTTLE AOCK. A.K ANSAS 72203.(501)371-4000 January 10, 1978 1-018-6 co Director of Nuclear Reactor Regulation e 9\

ATTN: Mr. D. K. Davis, Acting Chief g g \

U. S. Nuclear Regulatory Commission N/ 4.

Washington, D. C. 20555 -

Subject:

Arkansas Nuclear One - Unit 1 -

Docket No. 50-313 'l /(U License No. DPR-51 Interpretation of Technical

'k

\'y.,

Specification Requirements N (File: 1511.1, 0232) '

Gentlemen:

In a recent inspection of Arkansas Nuclear One - Unit 1, a difference in interpretation of Technical Specification (TS) 6.5.1.6 between AP6L and NRC Inspection and Enforcement personnel was identified. The difference of opinion centers around the wording in TS 6.5.1.6 which reads in part that: "The Plant Safety Committee shall be responsible for review of...."

several items. Our interpretation of this wording, which is based on dis-cussions with your staff during develonment of these specifications in late 1976, is that the Plant Safety Coiinnittee (PSC) does not have to per-form as a committee all of the reviews and investigations called for, but that they are responsible for such reviews. In other words, the PSC is responsible such reviews.for This seeing that the reviews are perfomed but may delegate then allows the PSC to concentrate on: major items by delegating some work and hence reducing their review workload.

On the other hand, NRC I 5 E personnel interpret TS 6.5.1.6 as requir-ing that the PSC perfom all such reviews and investigations. We disagree based on our literal interpretation of TS 6.5.1.6 as issued in Amendment No.16 which became effective on March 7,1977.

It should also be noted that the wording in our Technical Specifications prior to Amendment No. 16 was that: "The PSC shall review...". Thus, prior to Amendment No.16, the PSC was perfoming the reviews and would have continued performing them if the wording had not been changed at the NRC's request in our conversion of this section to the Standard Technical Specifi-cations.

/l00 /

//6

/

,o .. ,~o.,~ .Svo.o.~.o

@ ,-- -oom=~r-rm= v=n=

p-

. i'

~,'

Mr. D. K. Davis January 10, 1978 1-018-6 We find now that we are unable to resolve our disagreement with I 6 E personnel without obtaining a written interpretation from your staff of our Technical Specification 6.5.1.6 which is based on the Standard Technical Specifications. Your prompt reply on this matter is requested to aid in our resolution of this matter. We would be pleased to discuss this matter with you during your review.

Ve truly yours, Daniel H. Williams Manager, Licensing DHW:DAR:nf cc: Mr.-G. L. Madsen Reactor Construction 6 Operations Branch United States Nuclear Regulatory Commission Office of Inspection 6 Enforcement Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 w wwm e--.m,+wme, m

-e.-.mm -~ -- ~ ~ .- .m ,-* *-s