IR 05000313/1990038

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Forwards Summary of 901030 Enforcement Conference Re Insp Repts 50-313/90-38 & 50-368/90-38 on 901001-05
ML20062G930
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
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 gifpi", ef(DU/A) ;

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 In 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 Lis The subjects discussed at this meeting are described in the enclosed Meeting Sunenar 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 Roo Should you have any questions concerning this matter, we will be pleased to discuss them with yo

Sincerely

OdglnalSigned Gy:

Thomas P.0wynn L

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Samuel J. Collins, Director Division of Reactor Projects Enclosure:

Meeting Surrrnary w/Attachnents cc w/ enclosure:

Entergy Operations In 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 ,

TFWesterman;df LJCal GF9an orn SJCollins -

11/g/90 11/g/90 11/t(/90 11/23/90 (

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.4 Entergy Operations. In Entergy Operations, In 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, Es P.O. Box 651 Jackson, Mis:;issippi 39205 Arkansas Nuclear One ATTN: Early Ewing, General Manager Technical Support and Assessment ,

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 4 Route 3, Box 1370 Russellville, Arkansas 72801 --

Combustion Engineering. In ATTN: Charles B. Brinkman, Manager Washington Nuclear Operations 12300 Twinbrook Parkway Suite 330  !

Rockville, Maryland 20852 Honorable Joe W. Phillips  ;

County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Winston & Strawn .

ATTN: Nicholas S. Reynolds. Es L Street, Washington, <

Arkansas Department of Health  !

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, In 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 DR 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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. 1 MEETING SUMMARY I

Licensee: Entergy Operations, In l Facility: Arkansas Nuclear One License No.: DPR-51; NPF-6 Docket 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 license Attachments:  !

' Attendance List Licensee Presentation (NRC distribution only) ,

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a ATTENDANCE LIS Attendance at the Enforcement Conference between Arkansas Power & Light Company and NRC on October 30, 1990, at the NRC Region !Y offic Enterqy Operations In Neil S. Carns, Vice President - Operations ,

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 -

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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ANO-1

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ANO 1 10/30/90 ENFORCEN1ENT CONFERENCE ON CONTROL, ROO51 ISOLATION SYSTEN1 l I I ,

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INTRODUCTION N.S. CARNS

. OPENING REh1 ARKS R.A. FENECil

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SYSTEh! DESCRIPTION D.C. 51th1S  ;

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PROllLEh! IDENTIFICATION CilRONOLOGY R.A. FENECll  !

OPERAlllLITY I

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REPORTAHILITY g .

SYSTEh! DESIGN HASIS C.ll. TURK

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AS FOUND CONDITIONS AND D.C. hiihtS lhlhlEDIATE CORRECTIVE ACTIONS

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TEST PLAN DEVELOPMENT g -

AS FOUND TESTING  !

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SIODIFICATIONS/ REWORK I

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SYSTEM RESTORATION

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ROOT CAUSE R.A. FENECil l

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CORRECTIVE ACTIONS J.J. FISICAR0 I ,

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SPECIFIC ACTION RELATED TO i i CONTROL ROOM ISOLATION CONCERN ,

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RELATED CORRECTIVE ACTIONS  !

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G. L. 8814 INVESTIGATION

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SAFETY SIGNIFICANCE C ll. TUR K k .

CONCLUSIONS R.A. FENECill N.S. CARNS  !

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ELEN1ENTS OF SYSTEM CONF.(GUR ATION '

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NORMAL VENTILATION I

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NORMALINSTRUMENT AIR g_ HEADER PRESSURE i

80 - INSTRUMENT AIR HEADER PRESSURE LOW (ANNUNCIATOR K-12-D3, 70 - IN CONTROL ROOM)

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50 - (ANNUNCIATOR M16-B3,

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ACTUAL DAMPER DEFLATION BEGINS -

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CHRONOLOGY OF EVENTS /10/90 09/21/90 NRC OPERATIONAL SAFETY

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TEAM INSPECTION (OSTI)

09/15/90 NRC INSPECTOR REQUESTED DATA l 09/12/90 - -

REGARDING CONTROL ROOh1 g

EMERGENCY VENTILATION Jq SYSTEM (CREYS)

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09/15/90 - RESEARCH CONCI'UDED THAT FOUR

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VALVES HAD NOT BEEN i g ADEQUATELY TESTED

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- CONDITION REPORT C 90 00f'?

WRITTEN l- - CONDITION CONSIDERED SIGNIFICANT - MANAGEMENT lg-INVOLVED

- OPERABILITY DETERMINATION PERFORMED g . CONTROL ROOM ISOLATION DAMPERS

- EXPEDITIOUS TESTING

'l CONSIDERED MANDATORY 09'/21/90 - CONTROL ROOM ISOLATION ll.

L DAMPER INSTRUMENT AIR SYSTEM FAILS INTEGRITY TEST 1,

k - CV 7905/7 DECLARED INOPERABLE

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- 50.72 REPORT MADE

. 09/27/90 - CV 7905/7 DECLARED OPERABLE 50.73 REPORT SUBMITTED

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DESIGN BASIS EVOLUTION

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OTilER THAN THE CONTROL ROOM SHALL BE

[ AUTOMATICALLY CLOSED, SIMULTANEOUSLY WITH THE CLOSING OF THE OUTDOOR AIR INTAKE DAMPER AND THE OUTDOOR EXHAUST AIR DAMPER, THEREHY CAUSING

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100% RECIRCULATION OF THE CONTROL-ROOM AIR."

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1974 DESIGN AT STARTUP *

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- HIGH PRESSURE ACCUh1ULATORS (850# DESIGN)

- SOLENOID VALVES FOR CONTROLLING

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AIR SOURCE BASED ON RADIATION _

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SIGNAL AND INST. AIR PRESSURE J

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STARTUP TESTS CONFIRh1ED ABILITY OF g RESERVE AIR TO HOLD 24 HOURS 1.-; 4 .

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DOSE CALCULATIONS NOT TIED TO SPECIFIC CLOSURE TIh1E, NO TECHNICAL SPECIFICATIONS FOR CL,OSURE TIh1E t

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- TIE IN OF NEW " PRESSURIZATION" SCHEME

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PRESSURE TO " FLOAT" ON INSTRUMENT AIR (REQUIRING CHECK VALVESh CHANGES MADE TO ENSURE 10 SECOND CLOSURE TIMES ACHIEVED

- CHLORINE DETECTORS / ISOLATION FEATURE ADDED

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CLOSURE ADDED (BASED ON CHLORINE RESPONSE CLOSURE REQUIREMENTS FOR ANO 2)

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ANO-1 REOUIREMENTS SUMM ARY g

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LEAKTIGHT CONTROL ROOM (10CFM IN LEAKAGE ASSUMED)

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NO SPECIFIC CLOSURE TIME REQUIREMENTS

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AUTOMATIC ISOLATION UPON HIGH RADIATION

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BY EITHER INSTRUMENT AIR OR-RESERVE AIR Lg BOTTLES

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THIRTY (30) DAY POST ACCIDENT TIMES ASSUMED

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24 HOUR ISOLATION HOLD WITHOUT INTERVENTION

1978 - DCR 569 (ANO 1/ANO-2 INTERTIE) PRESSURIZED CONTROL ROOM (3 CFM IN LEAKAGE ASSUMED)

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AUTOMATIC ISOLATION WITHIN 10 SECONDS

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TEST PLAN

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GENERIC LETTER 8814 REQUIREMENTS

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CONSERVATIVE TEST CONFIGURATION

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TEST CHECK VALVES ALONE

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ORIGINAL TEST - FOUR PARTS

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COMPENSATORY ACTIONS

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N - VERIFIED REGULATOR PERFORMANCE BLADDER INFLATION g = BLADDER INTEGRITY

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h . DATA REDUCTION ,

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- MOST PROBABLE SCENARIO - MAINTAIN

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ISOLATION 75 MINUTES r-4 _

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SIGNIFICANT CHANGES TO PLANT MODIFICATION

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IMPROVED SAFETY REVIEW OF CHANGE PACKAGES ig~

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L OSE CALCULATIONS ARE IIASED ON j huh 1EROUS CONSERVATISh1S

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GDC Llh11TS ARE CONSERVATIVE h I -

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