IR 05000285/1989048
| ML19354D803 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/10/1990 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Morris K OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 9001220156 | |
| Download: ML19354D803 (25) | |
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, In Reply. Refer' To
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Docket: 50-285/89-48
-Omaha Public Power District i
ATTN:
Kenneth J.'Mo ris, Division Manager
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Nuclear Operations
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444 South-16th Street Mall
- Omaha, Nebraska _ - 68102-2247 i
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- Gentlemen:
This refers to the Enforcement Conference conducted in.the Region IV office on j
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. January 5,1990, with you and other members of your staff. This conference related to the findings' of the NRC inspection conducted during the period October 12 through November 30, 1989, which was documented in NRC Inspection.
-Report 50-285/89-48, dated December 18, 1989. The meeting was attended by those-on the attached Attendance List.
The subjects discussed at this conference are described in-the enclosed Meeting
- Summary.
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, 'Je will be pleased to discuss them with you.
Sincerely,
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Original Signed By-x.
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Samuel J. Collins Samuel J. Collins, Director
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Division of Reactor Projects l
Enclosure:-
I Meeting Sumary w/ attachments cc w/ enclosure:
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LeBoeuf Lamb, Leiby & MacRae ATTN:. Harry H. Voigt, Esq.
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1333 New Hampshire Avenue, NW Washington, D.C.
20036 Washington County Board of. Supervisors n
/ ATTN:
Jack Jensen, Chairman y Blair, Nebraska 68008
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RIV:DRP/B C:DRP/B D:
@hD RPMullikin;df TFWesterman Colljns 1/3 /90 1/q/90
9001220156 900110
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M6 PDR ADOCK 05000285 Q
PDC l8
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..e Omaha Public Power: District-
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Combustion Engineering, Inc.
ATTH:. Charles B. - Brinkman, Manager Washington Nuclear Operations
'12300 Twinbrook Parkway, Suite 330.
.Rockville, MD 20852 v
Department of Health ATTN: Harold Borchert. Director Division of Radiological Health 301 Centennial Mall South P.O. Box 95007-Lincoln, Nebraska' 68509 e
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Fort Calhoun Station ATTN:
G.' R. Peterson, Manager
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P.O. Box 399
' Fort Calhoun', Nebraska. 68023
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.U.S. Nuclear Regulatory Commission
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ATTN: - Resident Inspector
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' P.O. Box 309-
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JFort Calhoun, Nebraska 68023 U.S. Nuclear Regulatory Commission J ATTN:'. Regional Administrator,. Region IV 6111Ryan Plaza Drive. Suite 1000
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' Arlington,yTexas 76011 bectoDMB(IE45)
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~ bec-distrib. by RIV: -
R. D.: Martin Resident Inspector
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DRSS-FRPS -
SectionChief(DRP/B)
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MIS-System RIV File
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DRP~
RSTS 0perator
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Project ' Engineer (DRP/B) -
Lisa Shea, RM/ALF A.' Bournia, NRR Project Manager (MS:
13-D-18)
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ATTACHMENT:1'
- ATTENDANCE LIST P-Attendance l at the OPPD/NRC Enforcement Conference on January 5,1990, in the
- Region IV_ office:
OPPD4
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,W. C. _ Joness. Senior Vice President K.' J. Morris, Division Manager, Nuclear Operations
- G. R..Peterson, Manager, Fort Calhoun Station D. R. Trausch, Supervisor,.0perations
. K. Holthaus Manager. Nuclear Engineering F. G. Buck, System Engineer G. M. Cook, Licensing: Engineer
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NRC-
' S. J. ' Collins, Dimctor, Division of Reactor Projects-L. J. Callan, Director, Division of _ Reactor _ Safety T. F. Westennan, Chief, Project Section B P.:H. Harm 11, Senior Resident Inspector, Fort Calhoun Station
~G. F. Sanborn, Enforcement Officer R. P. Mu111 kin, Project' Engineer, Project Section B R.-M. Perfetti, Enforcement Specialist OE (via'telecon)
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p-l FORT CALHOUN STATION-
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o OPPD/NRC ENFORCEMENT CONFERENCE
JANUARY 5,1990
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OPPD/NRC JANUARY 5,1990 ENFORCEMENT CONFERENCE AGENDA A.- INTRODUCTION W. C. Jones B.
COMPONENT COOLING WATER EVENT
- Event D. R.Trausch
- System Description D. R. Trausch
- Safety Significance F. G. Buck
- Root Cause G. R. Peterson
- Corrective Actions G. R. Peterson C. SURVEILLANCE PROCEDURE ST-CEA-1 EVENT
- Event G. R. Peterson
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- Procedure Change Process G. R. Peterson
- Safety Significance G. R. Peterson
- Root Cause G. R. Peterson
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- Corrective Actions G. R. Peterson D. CONCLUSION W. C. Jones
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Summary of CCW Event T
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On October -12,1989, Operation's personnel ; determine l
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that 2 of 4 Component Cooling Water. (CCW) heat exchangers were simultaneously inoperable for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in violation of Technical' Specification 2.3.
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Investigation determined the 2 heat exchangers.had been
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simultaneously inoperable for six days, from October 6 to October '12.
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- 4 COMPONENT COOLING WATER SYS.EM SIMPLIFIED DIAGRAM
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C/R HVAC
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Containment Air Coolers
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Letdown HX LPSI HPSI Containment Spray Pumps Shutdown Cooling Hx
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SI & Cont. Spray Seal Coolers Gas Compressors
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VALVE CONFIGURATION
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Valve shown in " Auto" position
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CCW HEAT EXCHANGERL EVENT
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i October 1,
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"A" CCW Heat Exchanger removed from
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service.
October 5, 1989
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Operations personnel fail to properly.
return "A" CCW Heat Exchanger to service.
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October 6, 1989
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"B" CCW Heat Exchanger is' removed from service.
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October 12, 1989
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Operators attempt to initiate flow through "A" CCW Heat Exchanger.
Operability restored within 5 minutes.
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VALVE CONFIGURATION
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SAFETY SIGNIFICANCE
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MINIMAL SAFETY SIGNIFICANCE
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= Adequate CCW cooling capacity was available to meet Design Basis Accident requirements.
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= Plant operates with 3 or 4 CCW Heat Exchangers
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at higher river temperatures.
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= The Raw Water System is a backup.
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= The Containment Spray System is a backup.
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SIMPLIFIED COMPONENT COOLING SYSTEM DIAGRAM
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VA 1 A/B VA BAB VA-14A/B" SI-4A/BC/D "
RC-3A/BCD "
CEDM COOLERS (37)"
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CONCLUSION
= Adequate CCW cooling capacity was available
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to meet Design Basis Accident requirements.
= The Raw Water System is a backup.
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= The Containment Spray System is a backup.
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- ROOT CAUSE FOR CCW EVENT
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Lack of effective administrative controls
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- Lack of operability. testing
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Inappropriate action by operations ; personnel
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- Lack of training not recognized
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CORRECTIVE ACTIONS
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= Interim memorandum issued
= Event discussed at safety meeting
= Event discussed.with Shift Supervisors
= Event discussed in Operator requalification training
= Standing Orders revised
= Operator training and qualification program to be revised
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L SUMMARY OF ST-CEA-1 EVENT m
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If it had been performed, surveillance procedure ST-CEA-1
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" Control Element Assemblies" would have required both Diesel Generators to be placed in the "OFF AUTO" position for a
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portion of the test.
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EVENT CHRONOLOGY
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June 15,1989
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ST-CEA-1 change is initiated.
l June - July 1989
- PRC members review procedure change.
July 18, 1989
- PRC discusses procedure change.
Procedure change is inadvertently stamped "PRC Approved."
August 1, 1989
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Comments are resolved by System Engineer.
Procedure change is signed.
September 27, 1989
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Shift Supervisor prevents performance of revised test.
November 3,1989
- SARC requests an investigation by NSRG.
November 13, 1989
- NSRG identifies potential USQ.
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l PROCEDURE CHANGE PROCESS (SO-G-30)
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t Regular PRC meeting
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PRC Quorum or Procedure Change '
is held. FCS Manager Subcommittee Clerk places
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recommends
description of agrees with changes?
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approval and change and reason
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documents on PRC agenda M
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SARC Reviews
APP [ovM revision adon as requM
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procedure change is incorporated by PRC, Plant j
(if required)
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SAFETY SIGNIFICANCE
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MINIMAL SAFETY SIGNIFICANCE
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= Shift Supervisor did not allow performance of l
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Diesel Generators were never
placed in "OFF AUTO" during the event.
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= Significance supported by Safety Analysis.
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SAFETY ANALYSIS
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PLANT IS IN HOT SHUTDOWN Te = S32'F
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Minimal core decay heat
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ASSUMPTIONS:
LOSS OF OFF-SITE POWER IS EVENT INITIATOR RESULTIN o
OPERATORWILLTAKEMANUALACTIONTOSTARTDIESELGENERAT o
MINUTES ACTUAL RESPONSE TIME IS BELIEVED TO BE S-10 MINUTES o
Operator Awareness of Plant Configuration
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Loss of Control Room Lighting
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Early E0P-00 Guidance to Manually Start Diesels
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ANALYSIS:
STATION BLACKOUT INITIATED FROM HOT SHUTDOWN IS B o
GUIDE 1.155 ANALYSIS A00s BOUNDED BY EXISTING ANALYSES AND POSTULATED o
BELOW LOCA AND MSLB CONTAINMENT PRESSURE ANALYSES ARE B o
ACCIDENTS
-- LOCA: 'One hour allowed for operator action MSLB Containment Pressure Analysis:
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than 60 psig containment design basis limitPeak containment pressure less i
CONCLUSIONS:
ALTHOUGH HIGHLY UNDESIREABLE TO BE IN A MODE WITH BOTH INOPERABLE, FORT CALHOUN STATION WOULD REMAIN WITHIN THE DESIGN BA DOCUMENTED IN CHAPTER 14 0F THE USAR, SHOULD ANY OF THESE A00s O ACCIDENTS OCCUR FROM THE HOT SHUTDOWN MODE.
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ROOT CAUSE FOR ST-CEA-1 EVENT
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= Inadequate administrative controls over procedure
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change process.
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= Inadequate performance of Safety Evaluation.
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CORRECTIVE ACTIONS
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= Corrected ST-CEA-1 l
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= Clarified position on Technical Specification 2.0.1 j
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= Discussed Case Study with Shift Supervisors i
= Discussed Case Study with PRC and System Engineers
= Revised Standing Order G-5 " Plant Review Committee" i
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= Conducted review of approved procedures j
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= Withdrew qualifications of persons preparing the
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Safety Evaluation i
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= Investigated event
= Performed Safety Analysis l
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CORRECTIVE ACTION
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= Present Case Study to remainder of PRC members
= Incorporate Lessons Learned into revised Safety Evaluation Training Program to include periodic j
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= Review ESF related surveillance tests l
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CCW Event Promptly corrected
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Promptly reported r
Thorough investigation
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= Broad scope of corrective action Minimal Safety Significance
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CONCLUSIONS
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ST-CEA-1 Event l
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Licensee identified
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Shift Supervisor took proper action
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Procedure promptly changed by PRC
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Diesel Generators not made inoperable
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Plant never in an unanalyzed condition-
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Thorough investigation
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Broad scope of corrective action
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Minimal safety significance
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