ML19224C946
| ML19224C946 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, Crane  |
| Issue date: | 05/30/1979 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19224C937 | List: |
| References | |
| NUDOCS 7907100288 | |
| Download: ML19224C946 (4) | |
Text
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Cocket No.:
50-313 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P.O. Box 551 Little Rock, AR 72203 Cear Mr. Cavanaugh:
By Order of May 17, 1979, the Commission confirmed your undertaking a series of F.ctions, both immediate and long term, to increase the capability and reliability of Arkansas Nuclear One, Unit No.1 (ANO-1) to respond to various transient events.
In addition, the Order confirmed that ANO-1 was shutdown and would not be restarted until the following actions had been accomplished:
(a) Upgrade of the timeliness and reliability of the Emergency Feedwater System (EFW) by performing the items specified in Enclosure 1 of the licensee's letter of May 11, 1979.
Provide changes in design for NRC review.
(b) Develop and implement operating procedures for initiating and con-trolling EFW independent of Integrated Control System (ICS) control.
(c)
Implement a hard-wired control grade reactor trip that would be actuated on loss of main feedwater and/or on turbine trip.
(d) Complete analyses for potential small breaks and develop and implement operating instructions to define operator action.
(e) Assign at least one Licensed Operator who has had Three Mile Island, Unit No. 2 training on the Babcock & Wilcox simulator to the control room (one each shift).
By submittal of May 17, 1978, as supplemented by letters dated May 21, 22, 23 and 24, 1979, you have documented the actions taken in response to the May 17 Order.
I have reviewed this submittal, and am satisfied that, with respect to ANO-1, you have satisfactorily completed the actions prescribed in items (a) through (e) of paragraph (1) of Section IV of the Order, the specified mofidica-tions and analyses are acceptable, and the specified implementing procedures are appropriate.
The bases for these conclusions are set forth in the enclosed Safety Evaluation.
7 9 0 7.10 0 2F8 259 lb0
Arkansas Power & Light Company As noted on page 5 of Safety Evaluation you will be required to conduct a test during power operation to demonstrate operator capability to assume manual control of the EFW system independent of ICS.
In addition, we have discussed the need for monitoring core exit temperature with your staff and they have provided 16 thermocouple indications of core exit temperature in the control Also, your staff has agreed to provide an additional 16 thermocouple room.
indications of core exit temperature in the control room by October 31, 1979.
Appropriate Technical Specifications. for Limiting Conditions for Operation and for surveillance requirements should be developed as soon as practhable and provided to the staff within seven days witn remd to the design and procedural changes whicn have been completed 1 compliance with the provisions of the May 17, 1979 Commission Order.
The revised Technical Specification sho Jld cover:
(1) Changes to the EFW Systems; (2) Plant alignment changes made to ensure control of the EFW independent of the ICS; (3) Addition of the Anticipatory Reactor Trip; and (4) EFW capacity.
We note that by letter dated April 24, 1979, you have submitted proposed Technical Specifications for changes in setpoints for high pressure reactor trip and pilot operated relief valve actuation.
Also by letter dated May 16, 1979 you have subnitted proposed changes to the Technical Specifications which define limiting conditions of operation upon loss of EFW equipment.
Within 30 days of receipt of this letter, you should provide us with your schedule for completion of the long-term modifications described in Section 11 of the May 17 Order.
My finding of satisfactory compliance with the requirements of items (a) through (e) of paragraph (1) of Section IV of the Order will permit resumption of operation in accordance with 7 terms of the Commission's Order; it in no way affects your duty to contint
.a effect all of the above provisions of the 259 Is:,
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sansas Power & Light Company..cder pending your submission and approval by the Commission of the Technical sis.ification changes necessary for each of the required modifications.
Sincerely, Harold R. Denton, Director Office of Nuclear Reactor Regulation r cirsure-Netice of Authorization to Resume Operation oc w/ enclosure (s):
inillip K. Lyon, Esq.
Director, Technical Assessment iiouse, Holms & Jewell Division
- 5E0 Tower Building Office of Radiation Programs c:tcle Rock, AK 72201 (AW 159)
U.S. Environmental Protection M. David C. Trimble Apancy FinaCer, Licensing C ryst.t1 Mall #2 Arkansas Power & Light Company Arlington, VA 20460 P.O. Box 551 wittie Rock, AK 72203 U.S. Environmental Protection Agency Mr. James P. O'Hanlon Region VI Office General Manager ATTN:
EIS C0ORDINATOR
^rkansas Nuclear One 1201 Elm Street
.u.
Box 608 First International Building Russellville, AK 72801 Dalla, TX 75270 William Johnson Director, Bureau of Environmental U S. Nuclear Regulatory Commission Health Services P.O. Box 2090 481E West Markham Street Rutsellville, AK 72801 Little Rock, AK 72201 Mc Robert B. Borsum Babcock & Wilcox Nuclear Peer Generation Division duit 420, 7735 Old Georgetown Road Bethesda, MO 20014 Troy B. Conner, Jr., ESq.
Conner, Moore & Corber I;'47 Pennsylvania Avenue, N.W.
Wasnington, DC 20006 259 152
Arkansas Power & Light Company Arkansas Polytechnic College Russellville, AK 72801 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, AK 72801 259 15: