ML19224C396
| ML19224C396 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/25/1979 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Ross D Office of Nuclear Reactor Regulation |
| References | |
| FOIA-79-98 NUDOCS 7907020269 | |
| Download: ML19224C396 (7) | |
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UNITED STATES J $,. e [j NUCLEAR REGULATORY COrAMISSION
" a $p(/. C WASHINGTON, D. C. 20555
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s Docket No.:
50-313 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkan:as 72203
Dear Mr. Cavenaugh:
By Order of May 17, 1979, the Commission confirmed your undertaking a series of actions, both immediate and long term, to increase the capability and reliability of Arkansas Nuclear One, Unit No.1 (AriO-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 accomrlished:
(a) Upgrade of the timeliness and reliability of the Emergency Feedwater System (EFW) by performing the items specified in of the licensee's letter of May 11, 1979.
Pro-vide changes in design for I'RC 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 tripi (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 t'o. 2 training on the Babcock & Wilcox simulator to the control rcom (one each shift).
271 070
Arkansas Power & Light Company By submittal of May 17, 1979, as su'pplemented by letters dated May 21 g
g and 22, 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) throug:1 (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 pages and of the Safety Evaluation you will be required g
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to conduct a test during power operation to demonstrate operator capability to remove the Integrated Control System from the EFW System and assume manual control of the system.
Appropriate Technical Specifications for Limiting Conditions for Operation and for Surveillance requirements 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 pro-visions of the May 17, 1970 Commission Order. The revised Technical Speci-fications should cover:
(1) Changes to the EFW System; (2) Plant alignment changes made to ensure control of the emergency feedwater independent of the Integrated Control System; (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 emergency feedwater ecuipment.
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 II of the May 17 Order.
27!
071 e
Arkansas Power & Light Company 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 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 modificatinns.
Sincerely, Harold R. Denton, Director Office of Nuclear Reactor Regulation Er. closure:
Notice of Authorization to Resume Operation cc w/ enclosure:
See next page 271 OL72
Arkansas Power & Light Company cc w/erclosure(s):
Phillip K. Lyon, Esq.
Director, Technical Assessment House Holts & 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 Protec+. ion Agency Little Rock, Arkansas 72203 Region VI Office ATTN: EIS COORDINATOR Mr. Jares P. O'Hanlon 1201 Elm Street General Manager First International Building Arkansas Nuclear One Dallas, Texas 75270 P. O. Sox 603 Russellville, Arkansas 72801 Mr. William Johnson Director, Bureau of Environmental U. S. Nuclear Regulatory Commission Health Services P. O. Box 20'90 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 Bethesca, Maryland 20014 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 Arkansas Polytechnic College Russellville, Arkansas 72801 Ho'norable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 271 073
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION ARXANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 NOTICE OF AUTHORIZATION TO RESUME OPERATION The United States Nuclear Regulatory Commission issued an Order on May 17,1979 (44 FR 29997, May 23,1979), to Arkansas Power & Light Company (the licensee), holder of Facility Operating License No. OPR-51 for Arkansas huciear One, Unit No. 1 (ANO-1), confirming that the licensee accomplish a series of actions, both immediate and long term, to in;rease the capability and reliability of AND-1 to respond to various transient events.
In addition, the Order confirmed that the licensee would maintain AN0-1 in a shutdcwn condition until the following actions had been satisfactorily completed:
(a) Upgrade of the timeliness and reliability of the Emergency Feedwater (EFW) System 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 controliing 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 Bcbcock & 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 de May 17, Order.
Notice is hereby given that the Director of Nuclear Reactor Regulation (the Director',
hJ reviewed this submit:al and has concluded that the licensee has satisfactcrily cs gleted the actions prescribed in items (a) through (e) of paragraph (1) of Srtion IV of the Order, that the specified modifications and analyses are 271 074
7590-01.
acceptable and the specified implementing procedures are appropriate.
Accordingly, by letter dated 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 Copies of (1) the licensee's letters dated May 17, 21 and 22.1979, (2) the Director's letter dated
, and (3) the Safety Evaluation dated are available for inspection at the Commission's Public Occudent Room at 1717 H Street, N. W., Washington, D. C. 20555, and are being placed in the Commission'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 Commission, Washington, D. C.
20555, Attention:
Director, Division of Operating Reactors.
FOR THE NUCLEAR REGULATORY C0" MISSION Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors Dated at Bethesda, Maryland this day of May 1979.
271 075 O