ML19270G611
| ML19270G611 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/09/1979 |
| From: | Doug Garner Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906140176 | |
| Download: ML19270G611 (2) | |
Text
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e UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
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O WASHINGTON, D. C. 20555 g
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May 9, 1979 Docket No. 50-313 LICENSEE: ARKANSAS POWER & LIGHT COMPANY (AP&L)
FACILITY: ARKANSAS NUCLEAR ONE, UNIT NO.1 (ANO-1)
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 3,1979 TO DISCUSS SHORT AND LONG TERM COMMITMENTS FOR ACTIONS INVOLVING THE EMERGENCY FEEDWATER SYSTEM In their letter of April 26, 1979, AP&L pledged commitments for actions to resolve NRC's concerns related to feedwater transients in D&W plants. In this letter, AP&L stated the intent to meet with the NRC staff to review these comitments. A meeting was held on May 3, 1979, to discuss the subject matter. A list of attendees of this meeting is given in Enclosure 1.
The presentation by AP&L personnel included a review of present comitments (IE Bulletin responses), a discussion of operator tra'.ning on the TMI-2 event that will be completed by the end of May, and a description of the ANO-1 emergency feedwater design (both present and proposed designs). Following these discussions, AP&L presented a letter revising their comitments to provide particular resolution of items (a) through (e) on pg.1-7 of the ONRR Status Report to the Commission of April 25, 1979. The AP&L letter (dated May 3,1979) is provided as.
In the course of the meeting, AP&L agreed to the addition of two actions listed as items 8 and 9 of Enclosure 1 of their letter.
Av.G{
Daniel J.
rner, Project Manager Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
List of Attendees 2.
AP&L letter of May 3, 1979 2270 170 7 906140t76. e
S List of Attendees Meeting with AP&L, May 3,1979 AP&L B&W John Griffin J. Taylor Rick Lane E. Womach Jerry Maulden C. Parks William Cavanaugh, III R. Washer Bob Terwilliger Donald Rueter NRC T. Novak M. Chiramal John Burdoin Dom Dilanni Frank Ashe Louis Riani 997n j7j Art Oxfurth LLIU Bruce Boger Robert Reid Dan Garner Jerry Mazetis Howard Walker
ARKANSAS POWER S LIGHT COMPANY PCST CFFICE BCX 551 UTTLE ROCK. ARKANSAS 722C3 GOU 371-1422
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I May 3, 1979
. WILLIAM CAVANAUGH lli vice Ameenc Generston & Consme.m 1-059-1 Or. Harold R. Denton Director, Nuclear Reactor Regulation 1717 H Street North West Washington, D. C.
20555
Subject:
Arkansas Nuclear One - Unit i Docket No. 50-313 License No. OPR-51 (File:
1510)
Dear Mr. Denton:
In response to the staff safety concerns identified as items a. through Tmission of April 25, 1979,
- e. on pages 1-7 of ONRR Status Report to the Co:
Arkansas Power and Light proposes the following actions:
Upgrade of the timeliness and reliability of the Emergency (a)
Feedwater (EFW system by perfonning the items specified in Enclosure 1.
Develop and implement operating / emergency procedures for (b) initiating and controlling EP4 independent of Integrated Control System (ICS) control.
(c) Implement a hard-wired control-grade reactor trip on loss of main feedwater or on turbine trip.
Complete sufficient small break LOCA analyses to develop (d) and implement necessary operator instructions in the emergency procedures.
At least one Licensed Operator who has had TMI-2 training (e) on the B&W simulator will be assigned tc the control room (one each shift).
Arkansas Nuclear One - Unit 1 (ANO-1) is currently shutdown and will not be restarted until the items a. thr: ugh e. above are completed.
2270 172 veves= v:: us scum u u ss svsrsv
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Mr. H. R. Denton May 3,1979 1-059-1 To provide an increased margin of safety the following "Long-term" items will be implemented:
1)
The items in Enclosure 2 will be implenented during our next outage (following completion of the design change engineering) to cold shutdown conditions which is of sufficient length to accommodate the change but no later than the next refueling outage. Further we will provide a schedule for implementing any other modifications iden-tified as necessary as a result of our reviews shown on.
2)
The failure modes and effects analysis (FMEA) of the ICS is underway with high priority and will be submitted as soon as practicable.
3)
The hard-wired trips addressed in Item c. above will be upgraded to safety grade.
4)
Complete the ECCS small breaks analyses as outlined in.
5)
We will continue operator training and drilling of response procedures as a part of our ongoing program to assure the high state of readiness and safe operation at ANO-1.
AP&L is confident that these steps will resolve the Staff concerns and provide an additional degree of assurance of public safety.
Ver,y truly your f
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M William Ca'.. ugn II.?'
WC:JTE:vb Enclosures 2270 173
ENCLOSURE (1)
EMERGENCY FEE 0 WATER SYSTEM UPGRADE 1.
Review procedures, revise as necessary and conduct training to ensure timely and proper starting of motor driven energency feedwater (EFW) pump from an engineered safeguards bus upon loss of offsite power.
2.
To assure that EFW will be aligned in a timely manner to i -
ject on all EFW demand events when in the surveillance test mode, procedures will be implemented and training conducted to provide an operator at the necessary valves in communica-tion with the control room during the surveillance mode to carry out the valve alignment changes upon EFW demand events.
Write and implement procedures for the manual initiation and 3.
control of the EFW System following failure of the Integrated Control System.
4.
The EFW pumps will be verified operable in accordance with the ANO-1 Technical Specifications and Surveillance Procedures.
5.
Review and revise, as necessary, the procedures and conduct training for providing alternate sources of water to the suc-f tion of the EFW pumps.
6.
In the event emergency feedwater is necessary and offsite power is available, an auto start signal will be provided to the motor driven emergency feedwater pump.
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7.
Procedures will be developed and implemented and training conducted to provide guidance for timely operator verifi-cation of any automatic initiation of EFW.
E 8.
Verification that Technical Specifi~ cation requirements for EFW capacity are in accordance with the accident analysis will be conducted.
Modifications will be made to provide verification in the control 9.
rcom of EFW flow.
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ENCLOSURE (2)
EMERGENCY FEEDWATER SYSTEM UPGRADE 1.
Connect the motor driven Emergency Feedwater (EFW) pump to a vital AC power supply.
2.
Modify the suction piping to improve system separation.
3.
Modifications will be made to provide verification in the control room of EFW flow to each steam generator.
4.
Provide control room annunciation for all auto start conditions of the EFW system.
2270 i75
ENCLOSURE (3)
May 3, 1979 GUIDELINES FOR THE DEVELOPMENT OF OPERATIONAL PROCECURES FOR SAFE MANAGEMENT OF SMALL BREAXS IN THE REACTOR COOLANT SYSTEM PRESSURE SOUNDARY Operational guidelines will be prepared for the safe handling of small breaks as an extension of and addition to previously issued guidelines These guidelines will include provisions for and IE Bulletin 79-05A.
operator recognition of small breaks and discrimination of other acci-dents which might produce similar symptoms.
The guidelines will include expected system response insofar as required to assure effective operator understanding and action. The guidelines will include necessary precautions and will describe those actions 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 stabiliza-tion will occur with a partially filled reactor coolant system for both the case with the reactor coolant pumps on and the reactor coolant pumps off. Delay in the initiation of auxiliary feedwater up to 20 minutes will be considered. System conditions covered will assume availability of ECCS systems at full design flow in the event that auxiliary feed-water is not available or with single failure in the ECCS systens in the event that auxiliary feedwater is available.
The guidelines will be based on existing analyses and by specific addition-These calculations will be perfonned to define al computer calculations.
system response to restart of reactor coolant pumps in a partially filled system and response of the partially filled system to restart of auxiliary feedwater.
These guidelines will be developed by B&W and reviewed by the NRC staff in time for implementation of the corresponding procedures by Arkansas Power & Light on or before May 15, 1979.
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