ML19260B429
| ML19260B429 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/09/1979 |
| From: | Hoefling R NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | FRIENDS OF THE EARTH |
| Shared Package | |
| ML19260B410 | List: |
| References | |
| NUDOCS 7912100161 | |
| Download: ML19260B429 (3) | |
Text
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4 UNITED STATES OF A:: ERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
SACRAMENTO MUNICIPAL UTILITY DISTRICT )
Docket No. 50-312 (SP)
)
(Rancho Seco Nuclear Generating
)
Station)
)
NRC STAFF REQUEST TO PRODUCE DIRECTED TO FRIENDS OF THE EARTH (F0L, Pursuant to 10 CFR Section 2.741, the NRC Staff requests that F0E permit inspection and ccpying of all documents identifi d by F0E in its responses e
to the "First Set of NRC Staff Interrogatories to Friends of the Earth (F0E)" which was served upon F0E contemporaneously with this Request. The interrogatory responses are due to be served on Noven.. 'r 28, 1979. Although 6 2.741 would normally provide 30 days after service for F0E to respond, the Staff requests an opportunity to inspect and copy documents identified in those responses subsequent to November 28, 1979 at a time and place convenient to F0E.
Respectfully submitted, a di Richard K. Hoefling Counsel for NRC Staff Dated at Bethesda, Maryland this 9th day of November,1979 1517 346 291.n oo 4 /
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSIf(G BOARD In the Matter of SACRAMENTO MUNICIPAL UTILITY Docket No. 50-312 DISTRICT Rancho Seco Nuclear Generating Station
)
CERTIFICATE OF SERVICE I hereby certify that copies of "FIRST SET OF NRC STAFF INTERR0GATORIES TO THE CALIFORNIA ENERGY COMMISSION (CEC)", "NRC STAFF REQUEST TO PRODUCE DIRECTED TO CALIFORNIA ENERGY COMMISSION (CEC)", "FIRST SET OF NRC STAFF INTERR0GATORIES TO GARY HURSH AND RICHARD CASTR0", "NRC STAFF REQUEST TO PRODUCE DIRECTED TO GARY HURSH add RICHARD CASTR0", "FIRST SET OF NRC STAFF INTERR0GATORIES TO FRIENDS OF THE EARTH (F0E)", and "NRC STAFF REQUEST TO PRODUCE DIRECTED TO FRIENDS OF THE EARTH (F0E)", dated November 9,1979, in the above-captioned proceeding, have been served on the following, by deposit in the United States mail, first class, or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Comission's internal mail system this 9th day of November,1979.
Michael L. Glaser, Esq., Chairman Gary Hursh, Esq.
1150 17th Street, N.W.
520 Capitol Mall Washington, D.C.
20036 Suite 700 Sacramento, California 95814
- Dr. Richard F. Cole Atomic Safety and Licensing Board Panel Mr. Richard D. Castro U.S. Nuclear Regulatory Commission 2231 K Street Washington, D.C.
20555 Sacramento, California 95816
- Mr. Frederick J. Shon James S. Reed, Esq.
Atomic Safety and Licensing Board Panel Michael H. Remy, Esq.
U.S. Nuclear Regulatory Commission Reed, Samuel & Remy Washington, D.C.
20555 717 K Street, Suite 405 Sacramento, Califorriia 95814 David S. Kaplan, Esq.
General Counsel Christopher Ellison, Esq.
Sacramento Municipal Utility District Dian Grueneich, Esq.
P. O.
Box 15830 California Energy Comission Sacramento, California 95813 1111 Howe Avenue Sacramento, California 95825 Timothy V. A. Dillori, Esq.
Suite 330 a
1850 K Street, N.W.
Washington, D.C.
20006 1517 347
- Atomic Safety and Licensing Mr. Michael R. Eaton Board Panel Energy Issues Coordinator U.S. Nuclear Regulatory Comission Sierra Club Legislative Office Washington, D.C.
20555 1107 9 Street, Room 1020 Sacramento, California 95814
- Atomic Safety and Licensing Appeal Board Panel U.S. Nuclear Regulatory Comission Washington, D.C.
20555
- Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l, M /0 s Richard K. Hoefling b'
f Counsel for NRC Staff
- 17 T48
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April 27, 1979
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Mr. Harold R. Denton I
Director Office of Nuclear Reactor Regulation
~2 USNRC I
o Washington, D. C.
20555 r
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Re: Rancho' Seco iluclear Station
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Occket No. 50-312
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Dear Mr. Denton:
In resconse to the staff safety concerns identified as items a. through
- e. on page 1-7 of the ONRR Status Recort to the Conmission of April 25, 1979, the Sacramento Municipal Utility District proposes t'he following actions:
(a) Upgrade of the timeliness and reliability of delivery freci the Auxiliary Feedwater System by carrying out items 1 through 9 identified in enclosure 1.
(b) Develop and imolement operating procedures for initiating and controlling auxiliary feedwater independent of ICS control.
(c)
Imolement a hard-wired control-grade reactor trip on loss of main feedwater and/or turbine trip.
(d) Complete analyses for potential small breaks and develop and imolement operating instructions to define operator action.
(e) The District will provide for one Senior Licensed Operator assigned to the control room who has had TMI-2 training on the S&W simulator.
Rancho Seco will be shutdcwn on April 23,197s and will not be restarted until item a. through e. above are completed.
The District further comits to the follcwing additional actions f or imorovement and in assuring safety that is related to items a. through
- e. in CNRR Status Recort of April 25, 1979:
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Mr. Harold R. Denton 2
Acril 27,1979 (a) ' The District will provide a p.roposed schedule for j implementation of id:ntified design modifications which specifically relate to items 1 through 9 of enclosure 1 and would significantly improve safety.
(b) The failure mode and effects analysis of ICS is underway with high oriority by B&W and will be subnitted.as soon as practi-cable.
(c) The hard-wired trips will be revised to safety grade.
(d) A more complete description of the transient analyses is provided ir. closure 2 entitled " Guidelines for the Development c. Operational Procedures for Safe Managenent of Small Breaks in the Reactor Coolant System Pressure Soundary."
( e)- The District will continue operator training and drilling and will have a minimum of two licensed operators per shift with TMI-2 simulator training at B&W by June 1,1979. There-after at least one licensed operator with TMI-2 simulator training at B&W will be assigned to the Control Room. All training of licensed personnel will be completed by June 28, 1979.
The District is confident that these steps will meet your Staff concerns and provide additional assurance of public safety.
0.v &$
d
. J. Mattimoe Assistant General Manager and Chief Engineer e
1517 350
ENCLOSURE (1)
Auxiliary Feedwater System Upgrade v/ 1.
Review procedures, revise as necessary and conduct training to ensure timely and proper starting of motor driven auxiliary feedwater (AFW) pumo(s) from vital AC buses upon loss of offsite power.
v 2.
To assure that AFW will be aligned in a timely manner to inject on all AFW demand events when in the surveillance test mode, procedures will be imolemented and training conducted to provide an operator at the necessary valves in phone contunications with the control room during the surveillance mode to carry out the valve alignment changes upon AFW demand events.
3.
Procedures will be developed and implemented and training conducted to provide for control of steam generator level by use of safety grade AFW bypass valves in the event that ICS steam generator level control fails.
d.
Verification that Technical Specification requirements of AFW capacity are in accordance with the accident analysis will be conducted. Pump caoacity with mini flow in service will also be verified.
5.
Mcdifications will be made to provide verification in the control room of AFW flow to each steam generator.
5.
Review and revise, as necessary, the procedures and training for pro-viding af ternate sources of water to the suction of the AFW ? umps.
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1517 351
ENCLOSURE (1)
.,_. 7. Design review and modificatfor, as necessary, will be conducted to I
provide control room annuncir.cian for all auto start conditions of the j
AFW systen, t
8.
Procedures will be developed and implemented and training conducted to provide guidance for timely operator verification of any automatic i
initiation of AFW.
v-9.
Verification will be made that the air operated level control valves (a)
Fail to the 50% open position upon loss of electrical power to the electrical to pressure co/verter, and (b) Fail to the 100% open position upon loss of service air. The AFW bypass valves are safety grade.
1517 352
April 27, 1979 ENCLOSURE (2)
GUIDELINES FOR THE DEVELOPMENT OF OPERATIONAL PDOCEDURES FOR SAFE MANAGEMENT OF SMALL SREAKS IN THE REACTr a COOLANT SYSTEM PRESSURE SOUNDARY Ocerational guidelines will be prepared for the safe handling of small breaks as an extension of and addition to previously issued guidelines and IE Bulletin 79-0EA. These guidelines will include prov'isions for operator recognition of small breaks and discrimina-tion of other accidents which might produce similar symptoms.
The guidelines will include expected system response insofar as recuired to assure effective operator understanding and action.
The guidelines will include necessary precautions and will describe those acticns which the operator must take to assure safe management and mitigation of small break events, including natural circulation cooling where it is predicted to occur in the course of the accident.
These guidelines will specifically cover cases in which RCS stabili-
- ation will occur with a partially filled reactor coolant system for both the case with the reactor coolant pumps on and the reactor coolant pumos off. Celay in the initiation of auxiliary feedwater up to 20 minutes will be consietred. System conditions covered will assume availability of ECCS systems at full design ficw in the event that auxiliary feedwater is not available or with single failure in the ECCS systams in the event that auxiliary feedwater is available.
1517 353
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ENCLOSURE (2)
- April 27,1979 The guidelines will be based on existing analyses and by specific additional cemeuter calculations. These calculations will be per-formed to define system response to re-start of reactor coolant pumps in a partially filled system and responsa of the partially filled system to re-start of auxiliary feedwater.
These guidelines will be developed by B&W and revie.wed by the NRC staff in time for implementation of the corresponding procedures by the Sacramento Municipal Utility District on,or before May 15, 1979.
APRIL 27, 1979 1517 354
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION y
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g WASHINGTON. D. C. 20555
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June 27, 197C Docket No. 50-312 Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utlity District.
6201 S Street P. O. Box 15830 Sacramento, California 95813
Dear Mr. Mattimoe:
By Order of May 7,1979, the Commission confimed your undertaking a series of actions, both immediate and long term, to increase the capability and reliability of the Rancho Seco Nuclear Generating Station to respond to' various transient events.
In addition, the Order confirmed that you would I
shut down Rancho Seco on April 28, 1979, and maintain the plant in a shut-down condition until the following actions had been satisfactorily completed:
(a) Upgrade the timeliness and reliability of delivery fra the Auxiliary Feedwater System by carryi/1g out actions as identified i
in Enclosure 1 of your letter of ANil 27, 1979.
(b) Develop and implement operating procedures for initiating and controlling auxiliary feedwater independent of Integrated Control System control.
l (c)
Implement a hard-wired control-grade reactor trip that would be
~
actuated on loss of main feedwater and/or turbine trip.
(d) Complete analyses for potential small breaks and develop and implement operating instructions to define operator action.
1 (e) Provide for one Senior Licensed Operator assigned to the control room who has had Three Mile Island Unit No. 2 (TMI-2) training on the B&W simulator.
By submittal of May 14, 1979, as supplemented by seven letters dated May 22, 24,29,30(3) and June 6,1979, you have documented the actions taken in response to the May 7 Order. We have reviewed this submittal, and are satisfied that, with respect to Rancho Seco, you have satisfactorily completed the actions 1517 355 b u+t
l, i
Mr. J. J. Mattimoe.
O prescribed in items (a) through (e) of paragraph (1) of Section IV of the Order, the specified analyses are acceptable, and the specified implementing procedures are appropriate. The bases for these conclusions are set forth in the enclosed Safety Evaluation.
t As noted on page 13 of the Safety Evaluation, you will be required to conduct a test during power operation to demonstrate operator capability to assume manual control cf the Auxiliary Feedwater System independent of the Inte-grated Control System.
Appropriate Technical Specifications for Limiting Conditions for Operation and for sur.veillance 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 provisions of the May 7,1979 Commission Order. The revised Technical Specifications should cover:
(1) Addition of flow indication to the Auxiliary Feedwater System; (2) Addition of the Anticipatory Reactor Trips; and (3) Changes in set points for high pressure reactor trip and PORV actuation.
t Within 30 days of receipt of this letter, you should provide us with your schedule for completion of the long tem modifications described in Section II of the May 7 Order,and you should submit for staff review the model used in the analysis for potential small breaks referenced in your letter of May 14, 1979.
My finding of satisfactory compliance with the requirements of items (a) througia (e) of paragraph (1). of Section IV of the Order will permit resumption of operation in accordance with the tems 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 Specifi-l cation changes necessary for each of the required modifications.
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Sincerely, A-
{
Harold R. De ton, Director i
Office of Nuclear Reactor Regulation i
Encl osures:
1.
Safety Evaluation 2.
Notice cc w/ enclosures: See next page
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l EVALUATION OF LICENSEE'S COMPLIANCE i
WITH THE NRC ORDER DATED MAY 7, 1979
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I SACRAMENTO MUNICIPAL UTILITY DISTRICT t
RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 t
i I
i 1517 357 DUPLICATE DOCUMENT Entire document previously entered into system under:
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