ML20236R007
| ML20236R007 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/13/1987 |
| From: | Bournia A Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8711230019 | |
| Download: ML20236R007 (25) | |
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# o UNITED STATES 8" '
o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 h
,/ November 13, 1987
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Docket No. 50-285 LICENSEE: Omaha Public Power District FACILITY: Fort Calhoun Station, Unit 1
SUBJECT:
MEETING
SUMMARY
OF MEETING HELD ON NOVEMBER 13, 1987 IN BETHESDA, MARYLAND A meeting was held in Bethesda, Maryland on November 13, 1987 between Omaha Public Power District (0 PPD, the iicensee) and the NRC staff to discuss the recent instances of water intrusion into the instrument air system at Fort Calhcan. This meeting was a follow-up to the meeting held November 9,1987 in Bethesda, Maryland. A list of attendees and their affiliations is provided as Enclosure 1. The purpose of this meeting was to allow OPPD an additional opportunity to provide the staff with information concerning the recent occurrences of water intrusion into the instrument air system at Fort Calhoun. Enclosure 2 contains the slides provided by the licensee for this meeting. The licensee described, in some detail, the chronology of events and subsequent corrective actions. OPPD conceded that the plant was probably operating in an unanalyzed condition on July 6,1987 and that the plant would have been vulnerable to a design basis event and, in retrospect it would have been prudent to shut down. OPPD stated that their immediate corrective actions (blowing down systems and cycling valves) following the July 6, 1987 event had progressed to the point that by the end of that day, the plant probably could have met the applicable LCOs. RIV will be following up on the enforcement actions appropriate to the event itself. Neither the July 6, 1987 nor the subsequent August 25, 1987 event were reported to NRC and RIV will also be pursuing the deportability issues associated with the instrument air system water intrusion events. Senior OPPD management presented specific and programmatic corrective and improvement actions that, in total, provided the staff with adequate assurance that the plant is presently in a safe configuration and can continue to be operated safely. A schedule was developed for submittal, on the docket, of information that will be reviewed by the staff and will provide the basis for a future safety l evaluation. By November 20, 1987, OPPD will docket information concerning the systems affected by the events, the immediate corrective actions and subsequent testing that supports the conclusion that the plant is safe. This submittal will summarize the current state of the ISI & IST programs at Fort Calhoun and will outline and provide a schedule for revisions to the programs necessitated by the events. The submittal will also describe what is being done to establish the seismic pedigrees for safety-related valves and accumulators, along with some calculations demonstrating that the as-built configuration of the accumu-lators is adequate to withstand the seismic event. Additional calculations for the safety related valves supplied with instrument air will be submitted a week later, that is, on November 27, 1987. 8711230019 871113 PDR ADOCK 05000205 p PDR
2 Finally, the staff concluded that they were satisfied with OPPD's. work scope and response to the instrument air issue at Fort Calhoun, but expressed the hope that in the future, when other events take place, NRC will not have to play as large a role in getting OPPD to take appropriate action. k Anthony Bournia, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects
Enclosures:
As stated cc w/ enclosures: See next page I DISTRIBUTION 1 (DocketsEilen NRC PDR Local PDR PD4 Reading j J.'Calvo A. Bournia OGC-Bethesda E. Jordan l J. Partlow D. Crutchfield L. Shao J. Wilson E. Tomlinson J. Wermiel J. Ridgely L. Marsh A. Lee P. Kuo J. Callan T. Westerman D. Harrell J. Sharkey T. O. Martin ACRS (10) l PD4 M PD4/Dy)K JWilson:sr JCalvo 11/ /9 87 11/)/87 f ' i a 1
l s 4 7. '. as o i Mr. R. L. Andrews Fort Calhoun Station Omaha Public. Power District Unit No. l' cc: Harry H. ' Voigt, Esq. .. LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington,.D.C. 20036
)1 Mr. ' Jack. Jensen; Chairman
. Washington County Board- {
of Supervisors 1
.Blair, Nebraska = 68008 j
'Mr. Phillip Harrell,' Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309' Fort Calhoun, Nebraska > 68023- 4 Mr. . Charles B. Brinkman, ' Manager Washington Nuclear Operations-C-E Power Systems-7910 Woodmont Avenue Bethesda, Maryland 20814 o Regional Administrator,-Region IV-U.S. Nuclear Regulatory Commission. j Office of Executive' Director for Operations.
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 N Harold Borchert, Director Division of Radiological Health Department of Health 301 Centennial Mall, South 1 P.O. Box 95007 .i Lincoln, Nebraska 68509 . W. G. 'ates,
. Manager Fort Calhoun Station 1 l
P. O. Box 399-Fort Calhoun, Nebraska 68023 _; c 1 i o
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.. j Enclostre 1- .
List of Attendees at Meeting Between Staff and.0 PPD Held in Bethesda, Maryland on November 13, 1987 j i i NRC OPPD 1 D. M. Crutchfield W. C. Jones L. Shao R. C.'Andrews. J. A. Calvo S. K. Gamblin-J. H. Wilson R. F. Mehaffey' E. Tomlinson J. J. Fisicaro J. Wermiel W. G. Gates J.'K. Gasper. j J. Rudgely L. Marsh R. L. Jaworski' { M. E. Eiden-A. Lee P. Kuo. T. L. Patterson. -l T. J. McIvor j
- J. Callan l- T. Westerman M. T. Frans ;J
! D. Harrell M. R. Core l 1 ! J. M. Sharkey G. L. Roach G. Brown. f l T. O. Martin a i 1
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'l FORT CALHOUN STATION INSTRUMENT AIR SYSTEM l NRCOPPD M1EnNG ,
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, . INSTRUMENT. AIR SYSTEM NOVEMBER 13, 1987 AGENDA
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Est. Section Topic' Presenter- Time- .s I. Opening Remarks W. C.-Jones 5 mins.
.i II. Current Operational Status W. G. Gates; 20 mins ]
- July 6, 1987 Event / Scope ,
1
- Invest.igation and Results Corrective Action To Date
- Inspections and Maintenance
- Basis for Continued Operation
. c III. Safety Evaluattor. -(July 6,1987) J. K. Gasper: .15 mins
- Plant Transient Response Capability. 1
- Technical Specification Implications. ;
Emergency Plan Implications
- Corrective Actions i
R. L. Jaworski- a IV. Specific Corrective and Programmatic 10~ mins-Improvement Actions !
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V. Management Issues .R. L. Andrews'. - 5 mins VI. Summary W. C. Jones- 5 mins t I~ f , Ka-___- --_--------_--__----__-_-x------_-.-------.--__x-- - - - -->- A._._ __ - - - - - - - - u - - - - - - -- .s---, -a
4 e e INSTRUMENT AIR SYSTEM EVALUATION W. C. JONES OPENING REMARXS l i l l 1 l l l _)
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INSTRUMENT AIR SYSTEM CURRENT OPERATIONAL STATUS AREAS OF DISCUSSION A. UNDERSTANDING OF INITIAL EVENT AND SCOPE ; B. DISCUSSION OF COMPONENT CONFIGURATION E C. SPECIFIC PROGRAMS AND CURRENT RESULTS 1 BASIS FOR CONTINUED OPERATION I D. CORRECTIVE MAINTENANCE PROGRAM AND SCHEDULE . f i i i 1 i l l ____m___ ____.___.__..___________.___.__._m_ - . _ _ _ . _ _ _ . _ . _ t .'D.. 5
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INSTRUMEN1 AIR SYSTEM-CURRENT OPERATIONAL STATUS SPECIFICS A. QUALITY AIR SYSTEM DEW POINT-
- PARTICULATE HYDROCARBONS
- 8. LEW POINT MONITORING PROGRAM C. VALVE CYCLING ISI PROGRAM ADDITIONAL ISI PROGRAMS D. VALVE OPERATOR INSPECTION (NO OPERATORS FOUND TO BE INOPERABLE)'
VALVE SOLEN 0ID INSPECTION VALVE REGULATOR INSPECTION E. CHEMISTRY DISCUSSION RESULTS AND LIST OF VALVE OPERATOR VENDOR COMMENTS F. ACCUMULATOR AND ACCUMULATOR CHECK VALVE INSPECTION G. REINSPECTION OF DG-1 AND DG-2 AIR DAMPERS H. REINSPECTION OF 385/386 AND ITS SIGNIFICANCE
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CONFORMANCE FITH TECHNICAL SPECIFICATIONS
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- Conformance determined by compliance with LC0
- Air operated components
- Status assumed unknown
- Many Ls0's verifiaDie by testing
- Some LCO's not verifiable at power
- Main Steam Isolation Valves
- Initiate power reduction to achieve hot shutdcwn
- Technical Specification 2.01(2)
- Additional information obtained during the day
- Could have stopped power reductinn
- Precluded going to cold shutdown Event underestimated
- Focused on the limited number of component failures seen in the control room rather than potential for failures.
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1i RESPONSE TO POSTULATED TRANSIENTS
- Success judged by maintenance of Safety Functions in E0P
- E0P Implementation Review Team j
- Safety Analysis Engineers !
- SRO
- Assumption:
- Air operated components below 1025' in Auxiliary Building inoperable
- All Safety functions maintained if:
- Diesel' generators operabl e l1l
- SWIRT Level Instrument operable l
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- Dieself assumed operable
- DG-1 operated 7-8-87
- July and August Surveillance
* .SWIRT Level Instrument known operable as of 7-6-87
- All Safety functions maintained for all events not involving !
a system rupture .. c ;
- No air operated components below 1025'. operable'
- Station blackout
- E0P-2 1
- Hot Shutdown achievable d
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SAFETY. SIGNIFICANCE
- 0F JULY 6, 1987 WATER INTRUSION OF INSTRUMENT AIR
- Objective: Identify Actions To Increase Safety Consc'iousness 4 i
- Evaluate Plant Capability To Successfully Respond To Trans<ents Through E0P Implementation ;
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- Evaluate Conformance With Technical Specifications During Event .,
Evaluate Implementation of Emergency Plan
.i Perform " Design Basis" Safety Evaluation 1
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- IMPLEMENTATION OF- EMERGENCY PLAN Current Procedures
- Declaration of NOVE not mandated
- Not lead personnel to. consider EmergencyLPlan -
Declaration of NOUE-
- Would have been prudent j
- Quick staff augmentation-ry .
4 j SAFETY EVALUATION 'USING THE CRITERIA Of 50.59
- Performed by independent reviewer !
- Knowledgeable in 50.59
- Criteria for Unreviewed Safety Question Satisfied !
- Consequence of accident increased 1
- Different type of malfunction (i.e., common mode failure) l
- Margin of Safety reduced l
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- Reportable under 50.72 and 50.73 1
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LESSONS LEARNED i AND i i CORRECTIVE ACTIONS i Lesson
- Improved safety consciousness and procedural compliance, ;
i needed Corrective Action q
- Individual Division Management and employee discussions l
- GET reinforcement
- Field observations
- Improved A0P and EPIP
- Improved knowledge of potential for multiple failure events Lesson
- Formal approval mechanism for JCO's needed' Corrective Action J
- Develop formal guidance including review by PRC and SARC Lesson
- Increased detail in lesson plans on unique system features
- 1 Corrective Action i
- Identify and emphasize unique system features in lesson plans
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LESSONS LEARNED-AND CORRECTIVE ACTIONS-(continued) Lesson
- Improved event evaluation.for safety significance needed
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Corrective Action
- Improve plant incident. report system
- Institute incident investigation team Lesson y
- Prompt reporting of events to NRC'needed-Corrective Action
- Plant incident reporting system revised to further emphasize 50.72 and 50.73 evaluation upon event discovery l
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. i Specific Corrective Actions f A. Design Review of Instrument Air System B. System functiona1' Inspection on Instrument Air System C. Upgrade Operating Procedures on Instrument Air System 1
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D. Safety Significance of Events and Deportability Evaluation -l E. Common Mode Failure Consideration During Design F. Equipment Operated by Plant Workers-G. Equipment Tag-out Procedure Upgrade ] H. Safety Consciousness and Procedural Compliance
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I. JC0 Approval Process i j J. Lesson Plans to Include Unique System Features Programmatic Improvement Actions
,i A. Root Cause Determinations 1
- 8. Procedures llpgrade .,
C. Assign System Engineers , D. Design Basis Documents E. Upgrade Testing and Preventive Maintenance i. i' l l
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