IR 05000425/1989012

Forwards Enforcement Conference Meeting Summary on 890322 Re Misalignment of RHR Sys Valves That Occurred on 890309,per Insp Rept 50-425/89-12.Handout & List of Attendees Encl

ML20244C309
Person / Time
Site:	Vogtle
Issue date:	04/05/1989
From:	Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Hairston W GEORGIA POWER CO.
References
NUDOCS 8904200148
Download: ML20244C309 (10)

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- , APR' 0 5 1989 - ,

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g s P  : Docket' No'. L 50-425 '

License'No. NPF-79 -

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' Georgia' Power-Company

. ATTN: .Mrs W. G.LHairston, III; .

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' Senior Vice. President -

Nuclear.' Operations

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P. O. Box 1295'

' Birmingham,"AL '35201

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Gentlemen:

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. SUBJECT: ' ENFORCEMENT CONFERENCE SUMMARY

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(NRC INSPECTJON REPORT-NO.~ 50-425/89-12).

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.1 This' refers to the Enforcement Conference held at our request on March 22,

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• 1989. . This meeting concerned activities.-authorized for your Vogtle . facilit ' 'The issues discussed at this conference related to the misalignment of residual

'- '. heat- removal system.. valves that occurred 'on March 9,1989. A. meeting summary,

-list of attendees,' and a copy of your~ handout .are enclosed. We are continuing our-review of these' items to determine lthat appropriate enforcement actio D

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> LIn accordance with ~ Section 2.790 of - the NRC's " Rules of Practice," Part 2,-

L Title;10, Code of' Federal. Regulations, a copy of this letter and its enclosures will'be placed in the NRC Public' Document Roo Should you' have 'any questions concerning this letter, we will be _ pleased 'to

' discuss the

Sincerely,

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m.L.Ernd i Stewart D. Ebnete Regional Administrator Enclosures:

1. -Enforcement Conference Summary ,

2. List of Attendee .

3. Georgia Power Company Presentation  ;

I cc w/encls: -(See page'2)

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8904200148 890405 PDR ADOCK 05000425 s(

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R.JP;' Mcdonald,' Executive Vice.-

,. President,< Nuclear Operations P. D. Rice,'Vice President, Project

, , J Di rector . .

. . C. W. Hayes, Vogtle Quality

! Assurance. Manager-G. Bockhold, Jr. ,' General Manager, Nuclear _ Operations-J. P. Kane,. Manager Licensing

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and Engineering JP A. Bailey, Project Licensing Manager B. W. Churchill, Esq.,' Shaw,

. Pittman,.Potts and<Trowbridg *

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D. Kirkland, .III, . Counsel, Office of-the. Consumer's Utilit . Council

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Nuclear Energy-State of.Georgial

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-E. Reis,'0GC J. Hopkins, NRR-LM. Sinkule,LRII DRS Technical: Assistant-

'NRC Resident Inspector Document' Control Desk

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l ENCLOSURE 1 J

l ENFORCEMENT CONFERENCE SUMMARY

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On March 22, 1989, representatives of Georgia Power Company (GPC) met with the L NRC in the Region II office in A?lanta, Georgia to discuss the misalignment of residual heat removal system valvas at Plant Vogtle. A list of the meeting attendees is in Enclosure NRC management opened the meeting and stated that the root cause and corrective actions as a result of the misaligned valves needed to be fully addresse GPC'made a presentation giving the sequence of events which led to two normally locked closed valves being inadvertently left open for over 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. GPC management stated the overriding cause was a decision by plant operators to operate a plant safety system without a procedure. Other factors such as better communications, system status sensitivity, and a questioning attitude by other operators may have prevented the valve misalignment. The ' safety significance of the event was minimized by the fact that no decay heat was present because the core had not yet been critical. An outline of GPC's presentation is given in Enclosure NRC management stated that more than token corrective action was needed to

. prevent personnel errors. Unit 1 experienced a high number of reactor trips and personnel errors after receiving an operating license in 1987. As Unit 2 prepares to receive an operating license similar problems must be avoided. NRC management expressed a concern regarding the operating experience level of the operations shift on which the valve misalignment occurred. The balance of experienced operators on each shift needed to be thoroughly reviewe I

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ENCLOSURE 2 LIST OF ATTENDEES U. S. Nuclear Regulatory Commission - Region II

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S. D. Ebneter, Regional Administrator ]

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M. L. Ernst, Deputy Regional Administrator L. A. Reyes, Director, . Division of Reactor Projects (DRP)

G. R. Jenkins, Director,-Enforcement and Investigation Coordinator Staff (EICS)

A. R. Herdt, Chief, Branch 3,~DRP C. Julian, Chief, Engineering Branch, Division of Reactor Safety M. V., Sinkule, Chief, Section 3B, DRP J. F. Rogge, Senior Resident Inspector C. Burger, Senior Resident Inspector C. A. Patterson, Project Engineer B. Uryc, Senior Enforcement Specialist, EICS NRC - Office of Nuclear Reactor Regulation D. B. Matthews, Project Directorate II-3 NRC - Office of the Executive Director for Operation R. Borchardt, Region II Coordinator Georgia Power Company R. P. Mcdonald, Executive Vice President, Nuclear Operations W. G. Hairston, III,. Senior Vice President, Nuclear Operations C. K. McCoy, Vice President, Nuclear Operations G. Bockhold, General Manager, Nuclear Operations J. A. Bailey, Manager, Licensing J. E. Swartzwelder, Manager, Operations l

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i ENCLOSURE 3 l

l EXFORCEMEXT COXFERENCE l RHR SYSTEM CHRONOLOGY CAUSES CORRECTIVE ACTIONS SAFETY SIGNIFICANCE ENFORCON

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SEQUEXCE OF EVEXTS .

e3-8-89 1900 RHR SECURED; MODE 3 ENTRY e3-9-89 0230 PREPARATION FOR VALVE LEAKAGE TESTING; USS ORDERS 027 & 226 OPEN MOMENTARILY-0250 PE0 OPENS 027 & 226 0300 INDEPENDENT VERIFICATION PERFORMED  ;

1050 PRESSURE ISOLATION VALVE LEAK TEST STARTED 1550 NUE DECLARED DUE TO CHECK VALVE LEAKAGE 1630 RCS LEAKAGE INVESTIGATION 1707 027 & 226 DISCOVERED OPEN-T.S. 3.0.3 ENTERED 1720 VALVES CLOSED; EXITED . ;

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CAUSES e. INADEQUATE PROCEDURE e CLOSED LOOP COMMUNICATIONS e SYSTEM STATUS SENSITIVITY e SELF-CHECKING INADEQUACY (LOCKED VALVE PROGRAM')

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CORRECTIVE ACTIONS SHORT TERM -

e EVENT REVIEW TEAM ASSIGNED e LETTER FROM OPERATIONS MANAGER e RHR SYSTEM PROCEDURE REVISED e USS COUNSELLED LONG TERM e LOCKED VALVE PROCEDURE REVISION e INCREASED EMPHASIS ON CLOSED LOOP COMMUNICATIONS e REFRESHER /REQUALIFICATION TRAINING TO INCLUDE SENSITIVITY TO SYSTEM STATUS AND ENCOURAGE THE " QUESTIONING ATTITUDE" e I.S.E.G. REVIEW 0F LOCKED VALVES FOR OPERABILITY IMPACT CORRACTS

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SAFETY SIGNIFICANCE i

e PRE-CRITICAL STAGE

• NO DECAY HEAT

• NO RCS ACTIVITY e SAFETY INJECTION AND CHARGING PUMPS AVAILABLE SAFESIGN

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