ML19320A304
| ML19320A304 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/30/1978 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19320A305 | List: |
| References | |
| NUDOCS 8004210583 | |
| Download: ML19320A304 (2) | |
Text
o REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-313 REC: DAVIS D K ORG: CAVANAUGH W DOCDATE: 01/30/78 NRC AR PWR & LIGHT DATE RCVD: 02/08/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
51 LTR 1 ENCL 40 LICENSE NO DPR-15 APPL FOR AMEND: TECH SPECS PROPOSED CHANGE CONCERNING REVISION TO MEASURED MODERATOR TEMPERATURE COEFFICIENT AT HOT ZERO PWR TO COMPARE WITH TECH SPEC LIMIT OF 95% OF RATED PWR.
PLANT NAME: ARKANSAS - UNIT 1 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:
ocoo************* DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION:
BRANCH _ CHIEF DAVIS **W/7 ENCL INTERNAL:
FILE **W/
NRC PDR**W/ ENCL ia E**W/2 ENCL OELD**LTR ONLY HANAUER**W/ ENCL CHECK **W/ ENCL EISENHUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL GRIMES **W/ ENCL J.
COLLINS **W/ ENCL J.
MCGOUGH**W/ ENCL EXTERNAL:
LPDR'S RUSSELLVILLE, AR**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL DISTRIBUTION:
LTR 40 ENCL 39 CONTROL NBR:
SIZE: 1P+1P
--c**o*******************************
THE END 800 4 210 5r#3 g
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i,..,L Udf AAKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK ARKANSAS 72203 (501) 371-4422 January 30, 1978 WILLIAM CAVANAUGH 111 Execucve Director Generacon & Constructon 1-018-20
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Director of Nuclear Reactor Regulation 7"c:ig ATEN: Fir. D. K. Davis, Acting Chief N
Operating Reactor Branch #2 U. S. Nuclear Regulatory Commission 3 ',
Washington, D. C.
20555
____J._'i Subj ect: Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Proposed Technical Specification (File:
1511.1)
Centlemen:
Enclosed please find a proposed change to the Arkansas Nuclear One-Unit 1 Technical Specifications for your review and approval.
Discussed below is the basis for our proposed change.
Presently, Specification 3.1.7 includes lengthy steps in its bases for correcting the measured moderator temperature coefficient (>frC) at hot zero power to compare with the technical specification limit at 95%
rated power. However, the measured FRC correction values are cycle depen-dent and must therefore be changed with each reload application. The pro-posed change to our Technical Specifications incorporates the requirements implied in the present bases that the birC be confimed by measurement and that the measured value be extrapolated and/or compensated to permit direct comparison with the limiting value (non-positive above 95% full power). The proposed wording is a combination of the limiting condition for operation and the corresponding surveillance requirements in Specification 3/4.1.1.3 of the B6W Standard Technical Specifications.
We request that this proposed change be approved and returned in conjunction with those proposed technical specifications transmitted by our December 28, 1977, letter.
If we may be of further assistance in this regard, please advise.
l Very truly yours,"
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William Cavanaugh III.
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