IR 05000313/1990038
| ML20062G930 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/23/1990 |
| From: | Collins S Office of Nuclear Reactor Regulation |
| To: | Carns N ENTERGY OPERATIONS, INC. |
| References | |
| EA-88-283, NUDOCS 9012030085 | |
| Download: ML20062G930 (46) | |
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tin Resident Inspector DkS F ef(DU/A)
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Lisa Shea, RM/ALF DRP Project Engineer (DRP/A)
T. Alexion, NRR Project Manager (MS:
13-E-21)
DRS C. Poslusny, NRR Project Manager (MS:
13-D-18)
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NOV 2 31990
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Docket Nos. 50-313/90-38 50-368/90-38 License Nos. DPR-51 HPF-6 EA No.88-283 Entergy Operations Inc.
ATTN: Neil S. Carns Vice President Operations. Arkansas Nuclear One Route 3. Box 137G Russellville Arkansas 72801 Gentlemen:
This refers to the Enforcement Conference conducted at Region IV's request in the Region IV office on October 30, 1990. This meeting related to activities authorized by NRC License Nos. DPR-51 and NPF-6 for Arkansas Nuclear One and was attended by those on the attached Attendance List.
The subjects discussed at this meeting are described in the enclosed Meeting Sunenary.
It is our opinion that this neeting was beneficial and has provided a better understanding of the findings of the NRC inspection conducted October 1-5, 1990 (NRC Inspection Report 50-313/90-38;50-368/90-38), in followup of an issue identified during the operational safety team inspection conducted Septenber 10-21, 1990.
In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2. Title 10, Code of Federal Regulations, a copy of this letter will'be placed in the NRC's Public Document Room.
Should you have any questions concerning this matter, we will be pleased to discuss them with you.
Sincerely
OdglnalSigned Gy:
L Thomas P.0wynn
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Samuel J. Collins, Director Division of Reactor Projects Enclosure:
Meeting Surrrnary w/Attachnents cc w/ enclosure:
Entergy Operations Inc.
ATTN: Donald C. Hintz, Executive Vice President & Chief Operating Officer P.O.' Box 31995 Jackson, Mississippi 39286 RIV:C:DRP/M D:DRS E0 RP
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TFWesterman;df LJCal GF9an orn SJCollins
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11/g/90 11/g/90 11/t(/90 11/23/90 (
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-2 Entergy Operations, Inc.
ATTN:
Gerald W. MuencF. 'iite President Operations S@ port P.O. Box 31995 Jackson, Mississippi 39286 l
Wise, Carter, Child & Caraway ATTN:
Robert B. McGehee, Esq.
P.O. Box 651 Jackson, Mis:;issippi 39205 Arkansas Nuclear One ATTN:
Early Ewing, General Manager Technical Support and Assessment
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Route 3, Box 137G
Russellville Arkansas 72801 Arkansas Nuclear One ATTN: Jerry Yelverton, Director Nuclear Operations i
Route 3, Box 137G Russellville, Arkansas 72801 Arkansas Nuclear One ATTN: Mr. Tom W. Nickels
Route 3, Box 1370 Russellville, Arkansas 72801
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Combustion Engineering. Inc.
ATTN: Charles B. Brinkman, Manager Washington Nuclear Operations 12300 Twinbrook Parkway Suite 330
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Rockville, Maryland 20852 Honorable Joe W. Phillips
County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Winston & Strawn
.
ATTN: Nicholas S. Reynolds. Esq.
1400 L Street, N.W.
Washington, D.C.
20005-3502
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ATTN: Ms. Greta Dieus, Director Division of Environmental Health Protection 4815 West Markam Street Little Rock, Arkansas 72201 d
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Entergy Operations, Inc.
-3-Babcock & Wilcox Nuclear Power Generation Division ATTN: Mr. Robert B. Borsum 1700 Rockville Pike, Suite 525
Rockville Maryland 20852 Admiral Kinnaird R. McKee, USN (Ret)
P.O. Box 41 0xford, Maryland. 21654 bcc to DMB (IE14)
bec distrib. by RIV:
R. D. Martin Resident Inspector DRSS-FRPS SectionChief(DRP/A)
Lisa Shea, RM/ALF RIV File DRP.
Project Engineer (DRP/A)
T.' Alexion, NRR Project Manager (MS:
13-E-21)
DRS C. Poslusny, NRR Project Manager (MS:
13-D-18)
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MEETING SUMMARY Licensee:
Entergy Operations, Inc.
Facility:
Arkansas Nuclear One License No.:
50-313; 50-368 Subject:
ESCALATED ENFORCEMENT CONFERENCE CONCERNING NRC FINDINGS (NRCINSPECTIONREPORT 50-313/90-38;CO-368/90-38)
On October 30, 19901, representatives of Arkansas Power & Light Company met with Region IV personnel in Arlington, Texas, to discuss the apparent violation identified during the NRC inspection conducted October 1-5, 1990, in followup to an issue identified during the operational safety team inspection conducted September 10-21, 1990, and corrective actinns taken or planned by the licensee.
Attachments:
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Attendance List 2.
Licensee Presentation (NRC distribution only)
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a ATTENDANCE LIST.
Attendance at the Enforcement Conference between Arkansas Power & Light Company and NRC on October 30, 1990, at the NRC Region !Y office.
Enterqy Operations Inc.
Neil S. Carns, Vice President - Operations
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J. J. Fisicaro, Manager, Licensing C. H. Turk, Manager, Nuclear Engineering Design D. C. Mims, Manager, Systems Engineering, Unit 2 M. R. Chisum, Assistant Operations Manager, Unit 2 T. G. Mitchell, BOP System Engineering Supervisor R. J. King, Supervisor, Licensing NRC T. P. Gwynn, Acting Director, Division of Reactor Projects (DRP)
L. J. Callan, Director, Division of Reactor Safety (DRS)
R. Wise Allegations Coordinator T. F. Westerman, Acting Deputy Director, DRP P.'H. Harrell, Acting Chief, Project Section A, DRP
, J. E. Gagliardo, Chief Operational Programs Section, DRS
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J. E. Cunnins, Reactor Inspector, DRS C. C. Warren, Senior Resident Inspector, ANO, DRP T. W. Alexion, Project Manager, Office of Nuclear Re. actor Regulation
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OPERATOR DOSE Ih1 PACT I
CURRENT GDC SRP
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DESIGN
6.4 CASE CASE (REht)
LIMITS GUIDANCE I
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WilOLE I.6
5 3.6
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i TilYROID 26.8 (EQUIV)
37 3.7
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j SKIN (IlETA)
32.3 (EQUIV)
64 6.4 i
CASEI:
ESTIMATED DOSE DUE TO DEGRADED ISOLATION SYSTEM ASSUMING (NON.MECilANISTIC)
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1)
ISOLATION LOST AT 1 IIOUR i
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TID SOURCE TERMS I
3)
30 CFM UNFILTERED IN LEAKAGE AFTER I HOUR
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ISOLATION RESTORED AT 8 liOURS 5)
S R P 6.5.2, REV 2 SPRAY EFFICIENCIES
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CASE II:
ESTIMATED DOSE REALISTIC ASSUMPTIONS i
(MECIIANISTIC)
1)
GAP ACTIVITY SOURCE TERM 2)
OTI1ER ASSUMPTIONS IIELD CONSTANT
ACCEPTANCE LIMIT FOR ANO PER MEETING WITII NRC b:-
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SAFETY SIGNIFICANCE SUMMARY ESTlh1ATED OPERATOR DOSE IS CONSERVATIVELY
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CALCULATED TO REh1AIN WITHIN ACCEPTANCE LIh1ITS ASSUh11NG THE CONTROL ROOh! ISOLATION SYSTEh1 IS DEGRADED AFTER ONE HOUR. THEREFORE, THE SAFETY SIGNIFICANCE IS CONSIDERED h11NIh1AL.
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