ML19225A370
| ML19225A370 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/31/1979 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19225A371 | List: |
| References | |
| NUDOCS 7907190096 | |
| Download: ML19225A370 (6) | |
Text
..
A hRC NR j%,
UNITED STATES
+
y
>c g
NUCLEAR REGULATORY COMMISSION g
-l WASHINGTO N, D. C. 20555
%.v
/
May 31, 1979
+...
Docket No.: 50-313 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203
Dear Mr. Cavanaugh:
By Order of May 17, 1979, the Comission confirmed your undertaking a series of actions, both imediate and long term, to increase the capability and reliability of Arkansas Nuclear One, Unit No.1 (AM-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 accomplishea:
(a) Upgrade of the timeliness and reliability of the Emergency Feedwater System (EFW) by perfoming the items specified in of the licensee's letter of May 11, 1979. P ro-vide changes in design for NRC review.
(b) Develop and implement operating procedures for initiating and controlling EFW independent of Integrated Centrol 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 rocm (one each shift).
t 79073g0' "'
0De 3d7 2 } 2' t
i
Arkansas Power & Light Company -.
By submittal of May 17, 1979, as supplemented by letters dated May 21, 22, 23, 24 and 29,1979, 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 pre-scribed in items (a) through (e) of paragraph (1) of Section IV of the Order, the specified modifications and analyses are acceptable, and the specified implementing procedures are appropriate. The bases for these conclusions are set forth in the enclosed Safety Evaluation.
As noted on page 5 of the 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 agreed to provide a minimum of sixteen thennoccuple indicttions of core exit temperature in the control room prior to startup. Al,,, your staff has agreed to provide an additior.tl sixteen thermocouple indications of core exit temperature in the control roon. ; Jctober 31, 1979.
Appropriate Technical Specifications for Limiting Conditions for Operation and for surveillance requiremerits should be developed as soon as practicable and provided to the staff within seven days with regard to the design and procedural changes which have been completed in compliance with the provisions of the May 17, 1979 Commission Order. The revised Technical Specifications should cover:
(1) Changes to the EFW System; (2) Plant alignment changes made to ensure control of the EFW independnt 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 submitted 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 t s with your schedule for completion of the long-term modifications described in Sution II of the May 17 Orcer.
3d[
')L,J 7 -
2
Arkansas Power & Li,nt Company My finding of satisfactory compliance with the requirements of items (a) through (e) of paragraph (1) of Section IV of the Order will pemit resumption of operation in accordance with the terms of the Commission's Order; it in no way affects your duty to continue in effect all of the above provisions of the Order pending your submission and approval by the Commission of the Technical Specification changes necessary for each of the required modifications.
Sincerely, Y
Harold R. Denton, Director Office af Nuclear Reactor Regu4 tion
Enclosure:
Notice of Authorization to Resume Operation Safety Evaluation cc w/ enclosure:
See next page
Arkansas Power & Light Conpany cc w/ enclosure (s):
Phillip K. Lyon, Esq.
Director, Technical Assessment House, Holas & Jewell Division 1550 Tower Building Office of Radiation Programs Little Rock, Arkansas 72201 (AW-459)
U. S. Environmental Protection Agency Mr. David C. Trimble Crystal Mall #2 Manager, Licensing Arlington, Virginia 20460 Arkansas Power & Light Company P. O. Box 551 U. S. Environmental Protection Agency Little Rock, Arkansas 72203 Region VI Office ATTN:
EIS COORDINATOR Mr. James P. O'Hanlon 1201 Elm Street General Manager First International Building Arkansas Nuclear One Dallas, Texas 75270 P. O. Box 608 Russellville, Arkansas 72801 Mr. William Johnson Director, Bureau of Environmental U. S. Nuclear Regulatory Commission Health Services P. O. Box 2090 4815 West Markham Street Russellville, Arkansas 72801 Little Rock, Arkansas 72201 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
~20006 A-kansas Polytechnic College Russellville, Arkansas 72801 Honorable Ennil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 347 215
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION ARXANSAS POWER & LIGHT COMPANY DOCXET NO. 50-313 NOTICE OF AUTHORIZATION TO RESUME OPERATION The United States Nuclear Regulatory Comission issued an Order on May 17,1979 (44 FR 29997, May 23,1979), to Ai nansas Power & Light Company (the licensee), holder of Facility Operating License No. DPR-51 for Arkansas Nuclear One, Unit No.1 (ANO-1), confiming that the licensee accomplish a series of actions, both immediate and long term, to increase the capability and reliability of ANO-1 to respond to various transient events. In addition, the Order confirmed that the licensee would maintain /RO-1 in a shutdown condition until the following actions had been satisfacterily completed:
(a) Upgrade of the timeliness and reliability of the Erergency Feedwater (EFW) System by performing the items sper.ified it.
nclosure 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 controlling EFW independent of Integrated Control System 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, 1979, as supplemented by letters dated May 21 and 22, 1979, the licensee has documented the actions taken in response to te May 17, Order.
Notice is hereby given that the Director of Nuclear Reactor Regulation (the Director) has reviewed this submittal and has conviuded that the licensee has satisfactorily
,ccmpieted the actions prescribed in items (a) throuch (e) of paragraph (1) of Section I'! of the Order, that the specified mcdifications and analyses are 07190] gy 347 2ib
7590-01 acceptable and the specified implementing procedures are apprcpriate.
Accordingly, by letter dated May 31, 197 0 the Director has authorized the licensee to resume operation of ANO-1. The bases for the Director's conclusions are more fully set forth in a Safety Evaluation dated May 31, 1979.
Copies of (1) the licensee's letters dated May 17, 21 and 22,1979, (2) the Director's letter dated May 31,1979, and (3) the Safety Evaluation dated May 31,1979 are available for inspection at the Comission's Public Document Room at 1717 H Street, N. W., Washington, D. C. 20555, and are being placed in the Comission's local public document room at the Arkansas Polytechnic College, Russellville, Arkansas. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D. C.
20555, Attention: Director, Division of Operating Reactors.
FOR THE NUCLEAR REGULATORY COMMISSION bh-
.x Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors Dated at Bethesda, Maryland this 31stday of May 1979.
4[
2 l,7