ML20207A777
| ML20207A777 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/24/1999 |
| From: | Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20207A782 | List: |
| References | |
| 50-313-98-21, 50-368-98-21, EA-98-562, NUDOCS 9905270271 | |
| Download: ML20207A777 (5) | |
See also: IR 05000313/1998021
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGloN IV
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611 RYAN PLAZA drive, SulTE 400
ARLINGTON, TEXAS 760118064
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May 24,1999
EA 98-562
C. Randy Hutchinson, Vice President
Operations
Arkansas Nuclear One
Entergy Operations, Inc.
1448 S.R. 333
Russellville, Arkansas 72801-0967
SUBJECT: NRC SPECIAL INSPECTION REPORT 50-313/98-21; 50-368/98-21
,
Dear Mr. Hutchinson:
A special inspection was conducted at your Arkansas Nuclear One, Units 1 and 2, reactor
facilities from November 16-20,1998, and February 8-11,1999. Additionalin-office review was
conducted iollowing the onsite portions of the inspection and an exit meeting was conducted by
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telephone on May 17,1999. The enclosed report presents the results of this inspection.
Based on the results of this inspection, the NRC has determilled that one Severity Level IV
violation of NRC requirements occurred. The violation is being treated as a noncited violation ,
consistent with Appendix C of the Enforcement Policy. This noncited violation is described in
the subject inspection report. If you contest the violation or severity level of the noncited
violation, you should provide a response within 30 days of the date of this inspection report, with
the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control
Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the
Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington
DC 20555-0001; and the NRC Resident inspector at the Arkansas Nuclear One facility.
The violation involves the vulnerability of the Unit 1 reactor coolant system high pressure
injection valves to damagd from fire-induced circuit failures during a postulated control room or
cable spreading room fire. The violation is of concern because alternative shutdown capability
may not be availabie in the event of a fire. This violation would have been considered for
escalated enforcement using the guidance of Section 8.1.7," Actions involving Fire Protection,"
of the NRC Enforcement Manual (NUREG/BR-0195, Revision 2), but because of the number
artd type of circuit failures required to be postulated to cause a loss of the reactor makeup
function, we concluded that the risk significance of this issue warranted a Severity Level IV
violation. It is our understanding from Mr. James' statements during the telephonic exit meeting
that an hourly compensatory fire watch of the Unit 1 control room and cable spreading room
would be maintained until this issue is resolved. If our understanding of your compensatory
actions in response to this issue are not correct, please inform us within 30 days of the date of
this inspection report. During the inspection, you indicated disagreement with our position that
this issue was a violation and that there was a need to provide protection of at least one of the
9905270271 990524
ADOCK 05000313
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Entergy Operations, Inc.
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.'high pressure injection valves from damage. However, you documented in your corrective
action program an action item to submit a request for exemption to the NRC from the fire
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protection requirements for this condition by December 31,1999. Please inform us if you
should change or delay the plan for this action item.
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One unresolved item was identified involving your alternative shutdown capability with respect
to reactor coolant system high/ low pressure interfaces. We have questioned whether your
alternative shutdown capability meets the requirements of 10 CFR Part 50, Appendix R,
Sections lil.G.3, lli.L.1, III.L.2, and Ill.L7. Spurious operation of high/ low pressure interface
valves during a postulated control room or cable spreading room fire may result in the inability
to meet the performance goals of Appendix R. However, due to questions regarding the
licensing basis of your facility, we plan to fonward a request to the Office of Nuclear Reactor
Regulation for assistance in determining whether your alternative shutdown capability is
consiste.nt with the licensing basis, and if so, whether imposition of a backfit is warranted. You
will be advised in future correspondence regarding the disposition of this matter.
,
Additionally, it is our understanding from Mr. James' statements during the telephonic exit
meeting that Entergy Operations, Inc., will maintain an hourly compensatory fire watch of the
Units 1 and 2 control rooms and cable spreading rooms until the high/ low pressure interface
. valve issue is resolved. If our understanding of your compensatory actions in response to this
issue are not correct, please inform us within 30 days of the date of this inspection report.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its
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enclosure will be placed in the NRC Public Document Room.
Should you have any questions concerning this inspection, we will be pleased to discuss them
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Sincerely,
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Dr. Dale A. Powers, Chief
Engineering and Maintenance Branch
Division of Reactor Safety
Docket Nos.: 50-313;50-368
Enclosure:
NRC Inspection Report
50-313/98-21; 50-368/98-21
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Entergy Operations, Inc.
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cc w/ enclosure:
- Executive Vice President
. & Chief Operating Officer
Entergy Operations, Inc.
P.O. Box 31995
Jackson, Mississippi 39286-1995
Vice President
Operations Support
Entergy Operations, Inc.
P.O. Box 31995
-Jackson, Mississippi 39286
Manager, Washington Nuclear Operations
ABB Combustion Engineering Nuclear
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Power.
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12300 Twinbrook Parkway, Suite 330
Rockville, Maryland 20852
- County Judge of Pope County
Pope County Courthouse.
Russellville, Arkansas 72801'
Winston & Strawn
1400 L Street, N.W.
'
Washington, D.C. 20005-3502
David D. Snellings, Jr., Director
Division of Radiation Control and
Emergency Management
Arkansas Department of Health -
4815 West Markham Street, Mail Slot 30
- Little Rock, Arkansas 72205 3867
Manager --
- -
Rockville Nuclear Licensing
Framatome Technologies
1700 Rockville Pike, Suite 525 '
- Rockville, Maryland 20852-:
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E-Mail report to D. Lange (DJL)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
bec to DCD (IE01) .
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Allegations Coordinator (2)
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W. Brown, RC
J. Lieberman, OE, MS:7-HS
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DOCUMENT NAME: R:\\_ano\\An821rp.rlb
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E-Mail report to T. Frye (TJF)
' E-Mail report to D. Lange (DJL)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
bec to DCD (IE01)
bec distrib. by RIV:
Regional Administrator
Resident inspector
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DRP Director
MIS System
Branch Chief (DRP/D)
RIV File
Project Engineer (DRP/D)
DRS-PSB
Branch Chief (DRP/TSS)
Allegations Coordinator (2)
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W. Brown, RC
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J. Lieberman, OE, MS:7-H5
OE:EA File, MS:7-H5
S. West, NRR, MS:11-A11
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. DOCUMENT NAME: R:\\_ano\\An821rp.rlb
Tg receive copy of document, Indicate in box: *C" = Copy without enclosures "E" = Copy with enclosures *N" = No copy
RIV:RI:EB
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DPowers *
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- see previous concurrence
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