ML20028H035
| ML20028H035 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/01/1990 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | Carns N ENTERGY OPERATIONS, INC. |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR GL-89-19, TAC-74906, NUDOCS 9010050263 | |
| Download: ML20028H035 (5) | |
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UNITED STATES
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NUCLE ATI REGULATORY COMMISSION
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October 1, 1990 Docket. No. 50 313 ritetyy N eintions, Inc.
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I,t. Neil S. Carns Vice President, Operations Artanses I;uclect One Post Office Box 551 Little Rock, Arkansas 72203 t
Dear Mr. Carns:
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SUBJECT:
GENERIC LETTER 89-19, " SAFETY IMPLICATIONS OF CONTROL SYSTEMS IN LWR l
NUCLEARPOWERPLANTS"(TACNO.74906) by "1CAN039001, Responds to Generic Ltr 89-19 Re USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Individual Plant Exam Approach Will Result in Best Safety Solution to [[generic letter" contains a listed "[" character as part of the property label and has therefore been classified as invalid. & Listed NUREGs|letter dated March 19, 1990]], Arkansas Power and Light Company responded to Generic Letter 89-19, *kequest for Action Felated to Resolution of Unresolved Safety Issue A-47, 'Saf ety Implications of Control Systen.s in LWR Nuclear Power Plants' Pursuant to 10 CFR 50.54(f)," In your letter, you r,tated that more detailed design studies and safet assessments must be completed before a decision can be made regarding i lementation of a steam generator overfill protection system (SGOPS) at Arkansas Huclear One, Unit 1 (ANO-1). This conclusion is based upon inherent plant-specific differences and the suggestion that implementation of SGODS may increase the probability of loss of feedwater events due to inadvertent SGOPS actudtion. Moreover, your letter stated that the appropriate framework to evaluate steam generator overfill events and the safety impact of implementing a steam the Individual Plant Examination (IFE) generator overf til protection system is We do not agree with your position that a more detail'ed design and safety assessment using the IPE is an appropriate framework to continue the evaluation j
of _ steam generator overfill safety impacts.
Previous NRC analyses performed to y
evaluate alternatives to resolve USI A-47 prof.: led insight with respect to the safety benefits, impacts, and costs of modifications for overfill protection.
l Plant-specific differences were considered in the development of NUREG-1218
" Regulatory Analysis for Resolution of USI A-47,* and in the preparation of the Generic Letter 89-19. You had ample opportunity to provide comments on this issue when the Federal Register notice was published in May 1989.
Overfill events have occurred at light water reactors. The consequences resulting from such events cepend largely on piping system integrity, are-difficult to model accurately, and have large uncertainties.
It is for these reasons that the IPE evaluation will not add significant information to close this issue. Further, we believe that the potential negative impacts of inadvertent isolation of feedwater can be made insignificant through sound design, with reliable equipment, and with implementation of a reasonable test strategy.
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Mr. Neil S. Carns 2-October 1, 1990 In regard to the implementation schedule for ANO.1, the staff is of the opinion that implementation of the SGOPS prior to the startup following the IR10 refueling outege is feasible. We request your response within 45 days from receipt of this letter.
Sincerely, fkuck0 =
y Theodore R. Quay, Acting Director i
Project Directorate IV.1 Division of Reactor Projects. III, i
IV, V and Special Projects Office of Nuclear Reactor Regulation l
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I DATE ' 09//# /90
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- 09/2F/90 OFFICIAL REORD COPY Document Name: AND GL 8919 RESPONSE 74906
Mr. Nell'S. Carns
- In regard to the implementation schedule for ANO-1, the staff is of the opinion that implementation of the SGOPS prior to the startup following the IR10 refueling outage is feasible. We request your response within 45 days from receipt of this letter.
Sincerely, hechu S-r ay Theodore R. Quay, Acting Director Project Directorate IV-1 Division of Reactor Projects - 111, IV, Y and Special Projects Office of Nuclear Reactor Regulation ec: See next page i
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Entergy Operations, Inc.
Arkansas Nuclear One, Unit 1 CC' Mr. Early Ewing, General Manager Mr. Donald C. Hintz Technical Support and Assessment Executive Vice President Arkansas Nuclear One and Chief Operating Officer Route 3 Box 137G Entergy Operations, Inc.
Russellville, Arkansas 72801 P. O. Box 31995 Jackson, Mississippi 39286 Mr. Jerry Yelverton Mr. Gerald Muench Director Nuclear Operations Vice President Operations Support Arkansas Nuclear One Entergy Operations, Inc.
Route 3 Box 137G P. O. Box 31995 Russellville, Arkansas 72801 Jackson, Mississippi 39286 iii. Mcholes S. Reynolds Mr. Robert B. McGehee, Esquire Bishop, Cook, Purcell & Reynolds Wise, Carter, Child & Caraway 1400 L Street, N.W.
P. O. Box 651 Washington, D.C.
20005-3502 Jackson, Mississippi 39205 Mr. Robert B. Borsum Mr. Tom W. Nickels Babcock & Wilcox Arkansas Nuclear One Nuclear Power Generation Division Route 3, Box 137G 1700 Rockville Pike, Suite 525 Russellville, Arkansas 72801 Rockville, Marylard 20852 l
Senior Resident Inspector t
U.S. Nuclear Regulatory Commission 1 Nuclear Plant Road Russellville, Arkansas 72801 Regional Administrator, Region IV V.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable Joe W. Phillips County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health l
Protection l
Arkansas Department of Health l
4815 West Markam Street Little Rock, Arkansas 72201 4-
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NRC PDR Local PDR P04-1 Reading M. Virgilio MS 13E4 T. Quay L. Berry T. Alexion K. Jabbour MS 9H3 S. Newberry MS 8H3 OGC MS15B10 E. Jorden MS MNBB 3701 ACRS(10)MSP-315 PD4-1 Plant File