ML19259C451
| ML19259C451 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 05/14/1979 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906220076 | |
| Download: ML19259C451 (4) | |
Text
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e MEETItG SLTTARY DISTRIBUTION ORBd4 Mr. William Cavanaugh, III Vice President, Generation and Constru cion Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Docket File R. Reid
-NRC PCR?
V. Noonan
, DDfi P. Check ORB #4 Rdg G. Lainas NRR Rdg G. Knighton H. Denton Project Manager E. G. Case OELD V. Stello 0I&E (3)
D. Eisenhut R. Ingram R. Vollmer R. Fraley, ACRS (16)
W. Russell Program Support Branch B. Grimes TERA T. J. Carter J. R. Buchanan A. Schwencer Meeting Summary File D. Ziemann NRC Participants T. Ippolito B. Boger D. Fischer F. Ashe R. Wessman T. Novak G. Mazetis 2281 2L55 7 906 22007(b -
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UNITED STATES
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May 14, 1979 Docket No.: 50-313 LICENSEE: ARKANSAS POWER & LIGHT CCMPANY FACILITY: ARKANSAS NUCLEAR ONE-Unit 1
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 9, 1979, WITH AP&L CONCERNING THE AP&L COMMITMENT WITH REGARD TO THE CONFIRMATORY ORDER Introduction The subject meeting discussed the short term modifications which were connitted to by AP&L in their letter of May 3,1979, and which would appear subsequently in a Order. The meeting also discussed and defined the necessary supporting material which was necessary for the staff to complete the review of the licensee's commitments.
The attendees are identified in Enclosure 1.
Conclusions The staff requested and AP&L agreed to provide the following:
1.
One line Electrical drawings of the Integrated Control System and the reactor trip circuit for the loss of feedwater trip and turbine trip.
2.
Associated operating and surveillance procedures for the proposed modified hard wire reactor trip on loss of feedwater and /or turbine trip.
3.
A single line diagram showing the arrangement of the essential bus and the nonessential bus which provides power to the EFW pump electric motor together with the tie breaker and the breakers which connect the loads to the nonessential bus.
4.
Data on number of times the turbine driven EFW pump has been called upon to operate other than for testing, surveillance, or maintenance.
8 256
Meeting Sumary for Arkansas Nuclear One Unit 1 Held on 5/9/79 5.
By 10:00 a.m., May 10, 1979, feasibility of performing a test to demonstrate the operations of the motor driven EF4 pump during a loss of off-site power.
6.
A discussion on the method of tripping the EF4 systera as compared to other plants.
7.
From Enclosure 1 of the AP&L letter dated May 3,1979:
a) Submit the procedures which are to assure timely starting of the motor driven EF4 pump from an ES bus for loss of offsite power. Discuss alternatives for the short term which would further reduce the manual actions needed. Discuss the titre available & the analytical basis.
Discuss the overall reliability of the EF4 system with regard to the operating history at Arkansas. Compare and justify the EFW actuation signals to alternate signals (i.e., 1600 psig RCS pressure, 4 psig containment pressure, or low OTSG level).
b) Submit the procedures that the operator will use during the surveillance or maintenance mode to carry out valve alignment changes upon EFW demand events.
c) Submit procedures for the tranual initiation & control of EF4 folicwing ICS failure (and controlling EF4 independent of ICS). Discuss the time available and the analytical
- basis, d) Submit procedures for providing alternate sources of water to the EF4 pump suction, e) Submit the auto start modification for the motor driven pump.
f) Submit procedures which provide guidance for timely operator verification of automatic initiation of EF4.
8.
Provide a discussion of the need for, and description of, the imorovements in the suction piping to the EFA pumps.
Include specific comment on effect on required operator actions and relate to item 7 d above.
2281 257
Meeting Summary for Arkansas Nuclear One Unit 1 Held on 5/9/79 9.
Cescribe the flow modification to the EFAS and discuss testing /
calibration plans.
- 10. Submit the control room mod.on anaunciation of EFA auto start and the procedure for timely verifu.ation of auto start.
- 11. Provide a discussion of EFW Tech Spec capacity relative to accident analyses.
Include consideration of recirculation flow.
- 12. Submit procedures to define operator actions for accidents, particularly with regard to HPI actuation, EPA actuation and natural circulation cooling.
- 13. Discuss backup alternative indication and existing redundancy in pressurizer level indication.
- 14. Submit the operating procedure which discusses all indications to the operator for detennination of PORV status.
- 15. Submit test plans for design modifications.
- 16. Discuss alternate means provided to the operator to initiate switchover to other water sources.
Discuss the time available.
What is switch setpoint?
Discussion A primary discussion concerned the possibility of providing an actual test of the manual switching involved in starting the electric motor driven EFA pump off of the vital bus. AP&L discussed a proposed test which would start the Diesel Generator, load it with a decay heat pump, a spray pump and two service water pumps (the SW pumps would substitute for the Make up pump).
AP&L committed to provide the staff a copy of the test procedures for review before conducting the test.
auy S. Vissi,, Project Manager Operating Reactors Brancn d4 Division of Operating Reactors Enclosure -
" List of Attendees" 2281 258
ENCLOSURE 1 Attendance List for Meeting With Arkan'sas Power and Light Co.
concerning Arkansas Nuclear One - Unit 1 May 9, 1979 NAME ORGANIZATION Guy S. Vissing ORB #4/ DOR /NRC Bruce Boger NRC/DPM/0LB Donald Fischer NRR/ DSS /ASB Frank Ashe NRC/ DSS /PSB David Mardis Arkansas Power & Light Rick Lane Arkansas Power & Light Larry D. Young Arkansas Power & Light Phillip L. Almond Arkansas Power & Light Don Rueter Arkansas Power & Light R. H. Wessman NRCC-IE Tom Novak NRC G. Mazetis NRC 2281 259
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