ML20134H367
| ML20134H367 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 11/12/1996 |
| From: | Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20134H370 | List: |
| References | |
| GL-89-10, NUDOCS 9611140075 | |
| Download: ML20134H367 (5) | |
See also: IR 05000313/1996023
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C. Randy Hutchinson, Vice President
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Operations
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Arkansas Nuclear One
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Entergy Operations, Inc.
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1448 S.R. 333
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Russellville, Arkansas 72801-0967
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SUBJECT: NRC INSPECTION REPORT 50-313/96-23; 50-368/96-23
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Dear Mr. Yelverton:
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An NRC inspection was conducted September 16 20 and September 30 through
October 4,1996, at your Arkansas Nuclear One, Units 1 and 2 reactor facilities. This was
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supplemented by an October 9,1996, conference call. The enclosed report presents the
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scope and results of that inspection. The overall conclusions of this report were discussed
with Mr. Dwight Mims of your staff on November 7,1996.
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We have determined that your motor-operated valve program, as revised in response to
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several concerns raised during the inspection, has successfully implemented your
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commitments to Generic Letter 89-10, " Safety-Related Motor-Operated Valve Testing and
Surveillance." Consequently, the NRC review of your Generic Letter 89-10 motor-operated
valve program has been closed. The NRC will evaluate your periodic verification program,
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as well as your response to emerging motor-operated valve performance issues, within the
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framework of Generic Letter 96-05," Periodic Verification of Design Basis Capability of
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Safety-Related Motor-Operated Valves."
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During the inspection, an unresolved item was identified concerning the potential inability
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of certain safety systems to survive a control room fire. The concern is that redundant
motor-operated valves may stall from multiple hot shorts and be damaged to an extent that
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local operation may not be available as a contingency action. Your analysis did not include
consideration of the potential for more than one motor-operated valve to be affected by a
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hot short during a control room fire. Consequently, you chose not to modify any motor-
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operated control circuits to provide hot short overload protection via the torque or limit
switch. The function of certain safety systems in both units could be defeated in the event
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of multiple hot shorts. These facts are being reviewed as a possible violation of 10 CFR 4
Part 50, Appendix R.
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in accordance with 10 CFR 2.790 of the .!RC's " Rules of Practice," a copy of this letter,
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its enclosure (s), will be placed in the NRP Public Document Room (PDR).
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9611140075 961112
ADOCK 05000313
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Entergy Operations, Inc.
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Should you have any questions concerning this inspection, we will be pleased to discuss
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them with you.
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Sincerely,
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8 Kenneth E. Brockman, Acting Director
Division of Reactor Safety
Docket Nos.: 50-313;50-368
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Enclosure:
NRC Inspection Report
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50-313/96-23:50-368/96-23
cc w/ enclosure:
Executive Vice President
& Chief Operating Officer
Entergy Operations, Inc.
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P.O. Box 31995
Jackson, Mississippi 39286-1995
Vice President
Operations Support
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286
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Manager, Washington Nuclear Operations
ABB Combustion Engineering Nuclear
Power
12300 Twinbrook Parkway, Suite 330
Rockville, Maryland 20852
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County Judge of Pope County
Pope County Courthouse
Russellville, Arkansas 72801
Winston & Strawn
1400 L Street, N.W.
Washington, D.C. 20005-3502
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Entergy Operations, Inc.
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Bernard Bevill, Acting Director
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Division of Radiation Control and
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Emergency Management
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4815 West Markham Street, Slot 30
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Little Rock, Arkansas 72205 3867
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Manager
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Rockville Nuclear Licensing
Framatone Technologies
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1700 Rockville Pike, Suite 525
Rockville, Maryland 20852
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Entergy Operations, Inc.
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E-Mail report to D. Nelson (DJN)
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L. J. Callan
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DRP Director
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Project Engineer (DRP/C)
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W. Kropp, Rlli
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bec distrib. by RIV:
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