ML20235E358

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Discusses 870619 Meeting W/Util,Dresser & Schneider Engineering in Region IV Ofc to Discuss Progress in Determining Root Cause of Inoperable Pressurizer Code Safety Valves.Attendance List & Agenda Encl
ML20235E358
Person / Time
Site: Arkansas Nuclear 
Issue date: 06/30/1987
From: Johnson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Campbell G
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 8707110027
Download: ML20235E358 (13)


Text

T JUN 3 01987 I

In Reply Refer To:

Dockets:

50-313 j

i Arkansas Power & Light Company ATTN: Mr. Gene Campbell Vice President, Nuclear i

Operations I

P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:

This refers to the meeting conducted in the NRC Region IV office on June 19, 1987. This meeting related to activities authorized by NRC License DPR-51 for Arkansas Nuclear One, Unit 1, and was attended by those indicated in the enclosure.

This meeting was to discuss your progress in determining the root cause of inoperable pressurizer code safety valves.

It is our opinion that the meeting was informative.

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 j

the NRC's Public Document Room.

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Should you have any questions concerning this matter, we will be pleased to discuss them with you.

Sincerely, 1

Original Sicned by E.11. B htron E. H. Johnson, Director Division of Reactor Safety and Projects

Enclosures:

A.

Meeting Attendance List B.

Meeting Agenda CC w/ enclosures *,

8707110027 870630 J. M. Levine, Director PDR ADOCK 05000313 Site Nuclear Operations P

PCR Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Arkansas Radiation Control Program Director o

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L______-__-_____-_____-_________-___.

Enclosure A i

i MEETING ATTENDANCE LIST l

NRC REGION IV - ARKANSAS POWER & LIGHT COMPANY l

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NRC Attendees:

P. Check, Deputy Regional Administrator E. Johnson, Director, Division of Reactor Safety and Projects R. Hall, Deputy Directo-

'ivision of Reactor Safety and Projects J. Gagliardo, Chief, Reactor Projects Branch R. Ireland, Chief Engineering Section R. Mullikin, Project Inspector W. Johnson, Senior Resident Inspector G. Dick, Project Manager G. Hammer, NRR K. Leu, NRR Licensee Attendees:

D. Howard, Special Projects Manager D. James, Licensing Supervisor l

A. Wrape, III, Nuclear Services Manager l

J. Smith, Nuclear Services Engineer l

Licensee Consultants:

F. Bolger, S. P. Engineer, Dresser J. Murphy, Director, Power Services Division, Schneider Engineering L_ _ _________.___

l Enclosure B AGENDA

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BACKGROUND AND INTRODUCTORY DAN HOWARD REMARKS

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STATUS OF ROOT CAUSE JOHN SMITH /

INVESTIGATION JOE MURPHY 4

FURTHER TESTING AND JOHN SMITH EVALUATIONS j

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1R7 SEQUENCE OF EVENTS j

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0 PSV-1001 REPLACED WITH SPAM VALVE PWVIOUSLY l

l TESTED OFFSITE TO MEET TECMICAL SPECIFICATI0W SURVEILLANCE REQUIREMENTS o

PSV-1001 TESTED IN-SITU TO COWIM QFF5 Lit 21LLNG (NOT REQUIRED BY TECHNICAL SPECIFICATI0V9 l

0 PSV-1001 FOUND SLIGHTL Y LOW ; A0JU5 tut o

PSV-1002 TESTED IN-SITU TO CMFDM wtILNG (NOT REQUIRED BY TECMICAL stcit-LckTIGV5 l

VALVE LIFTED AT APR90KIMAT&Y 28!i0 PSIG AFTER ADJUSTMENT OF 10 NUT FLATS VALVE ADJUSTED TO PROPER SETTING l

ESTIMATED AS FOUND SETTING OF APPROXIMATELY 3000 PSIG o

INITIAL ROOT CAUSE INVESTIGATION INCONCLUSIVE NO PRIOR TESTING OR MAINTENANCE ERRORS FOUND

1R7 SEQUENE iF EVENTS (Cont.)

O DECISION TO C00LDOWN AND MPLAW PSV-1002 r

a FINAL IN-SITU TESTING AND ADVtBDQ5VT GF &PLACED PSV-1002 (ADDITIONALLY TESTED OFFSITG l

0 PLANT STARTUP l

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CMCLUSIONS o

FAILLW W VALVE IN PSV-1002 POSITION TO LIFT AT WWIMD SETPOINT WAS FOUND AS A RESULT W APGL INITIATED TESTING a

A00T CAUSE HAS NOT YET BEEN ESTAM.I98 IDEVER WVIEW TO DATE INDICATES NO INCGIECT MAINTB\\(Ah&

G1 TESTING ACTIVITIES a

AP&L TOOK PRUDENT ACTIM TO MPLACE TW SUSPECT' YALVE TO ALLOW FOR AWITIO\\lAL TESTING AND TO ASSME VALVE OPERABILITY a

SEFICIENT ASSURANCE EXIST THAT INSTALLED VALVES AE GSIABLE a

ROOT CAUSE EVALUATIM IS CMTINUING

i ROOT CAUSE INVESTIGATION PURPOSE c

TO WTERMINE THE ROOT CAUSE F TW FAILUE T PSV-1002 TO LIFT AT TM MSIMD MTPOINT 1

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'O VALIDATE THE TEST EThM6 IEED FW BOTH IN--SITU AhD WF-SITE TESTIM l

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O TO I&NTIFY ACTILMG NHICH CGX.D M TAKEN TO IM990VE ANY NOTED A90L96

ACTIM PLAN a

CGillRACTED OUTSIDE FIM TO ASSIST IN IW INVESTI-GATIM ; THIS CONSULTANT HMS BlR59 TIE IN THIS AWA BASED W EXTENSIVE h0K F09 KdVAL MACTUB o

00ENED A MORE INTENSE DIALORE WITH TE VALE VENDORS CONCERNING DETAILED DATA M ARDT.ICHE INDUSTRY DATA o

PERF09M A MTAILED DIMNSIWAL M VISUAL INSPECTIM OF VALVE IBOVED FROM PSV-1002 POSITIM (Pt'eliminary Inspection W-Site With the Vendor Revealed no Obvious Cause of ttle High Setpoint) o PERF0@f A COLD SET PWSSIRE TEST AhD A HOT TEST OF VALVE IBOVED FROM PSV-1002 POSITIM o

PFJFQ@f ADDITIWAL DATA SEARCH OF APGL AND INDUSTRY FILES FW SIMILAR OCClHiRENCES o

PERFO@f A PIPING EVALUATION ON THE INSTALLED CONFIGURATIM OF THE N0ZZLES ON BOTH UNITS WITH EMPHASIS ON CMTRIBUTIWS TO SETPOINT CHANGES

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ACTIM PLAN (Cont.)

o PERFORM ADDITIONAL REVIEW LF APIGL M VEN009 PROCEDURES USED TO SET M TEST TIE VALVES FOR SIGNIFICANT DIFFERENCES W IAH0 VESTS FOR BOTH UNITS o

PREPA% A DOCUMENTATION PAWAW FW MPlA hENT VALVE (AS A CMTINGENCY) IF IT CANT E CERTIFIED THAT VALVE WILL PBFQW SATISFACTWILY a

PROVIM SWCIFIC MC0iNSDITIM BASEl1 M TW EVALUATIM M EXAMINATIM MLATIVE TO PROCElMER TEST EWIPMNT

TRAINING, 09 OTWR ASWCTS Note:

These Tests and Inspections Will be Performed by a Contractor Other Than Those Previously used

CURRENT STATUS / PROJECTED SCHEDULE JANUARY 27 ISSUE ACTION PLAN FW ROOT CAUSE DETERMINATIM FEBRUARY 7 CONTRACT A THIM PARTY FW ASSISTANCE FEBRUARY 15 ISSUE BID PACKAW TO PUEN4 SING WPARTMENT FW liEPLALBENT VALVE

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MARCH 20 WCEIVED BIOS FW MPLALBENT VALVE FW EVALUATIM (CWTINGENT ACTIW OtY)

APRIL 30 C0FLETE ANALYSIS W M1 AM AM-2 PIPIM QMFIGWATIM JULYf BEGIN MT FWCTIMAL TEST (4 WEEKS)

AUGUST 28 ISSUE PRELIMINARY RECOMMENDA TIONS AND COMMENTS FOR DISCUSSION l

SEPTEMBER 20 ISSUE ROOT CAUSE INVESTIGA TION FINAL REPORT l

SEPTEMBER 30 PREPARE FOLLOW-UP LER RESPONSE 1

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j CURRENT STATUS (JUNE 19,.1987) 0 PIPING EVALUATIONS ARE COMPLETE (IN REVIEW)

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- AND-1 CONCLUSION - THE INSTALLED CONFIGURATION DOES NOT CONTRIBUTE TO PSV OPERABILITY PROBLEMS.

- ANO-2 CONCLUSION - THE. INSTALLED CONFIGURATION DOES CONTRIBUTE TO l

THE LEAKAGE OF ONE VALVE LOCATION.

APSL ENGINEERING IS PREPARING LONG TERM MODIFICATIONS.

O REVIEW OF APSL AND VENDOR PROCEDURES ARE COMPLETE (IN REVIEW)

- CONCLUSION IS THAT PROCEDURES DID NOT l

CONTRIBUTE TO THE SETPOINT VARIATION

- SOME COMPARATIVE TESTING BETWEEN IN-SITU AND OFFSITE METHODS o

DETAILED VISUAL AND DIMENSIONAL INSPECTION OF VALVE PSV-1002 WAS COMPLETED ON MAY 12 l

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- PARTS MET MANUFACTURER'S DIMENSIONS WITH ONLY l

ONE EXCEPTION

FUTURE WORK o

IDENTIFY THE MOST PROBABLE SCENARIO THAT WOULD CAUSE THE INDICATIONS NOTED ON THE VALVE.

O PERFORM A TEST TO SIMULATE THAT SCENARIO.

o INVESTIGATE IN-SITU TEST METHODS VERSUS OFF-SITE TESTING.

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