ML20148F495
| ML20148F495 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/15/1988 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| NUDOCS 8803280179 | |
| Download: ML20148F495 (20) | |
See also: IR 05000302/1987041
Text
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MAR 15 E88
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Docket No. 50-302-
License No. DPR-72
Flprida Fower Corporation
(Yr. W. S. Wilgus
LVice President Nuclear Operations
ATTN: Manager, Nuclear Licensing
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P. O. Box 219
Crystal River, FL 32629
Gentlemen:
SUBJECT:
ENFORCEMENT CONFERENCE SUMMARY
(NRC INSPECTION REPORT NO. 50-302/87-41)
This letter refers to the Enforcement Conference held at our request on
February 22, 1988.
This meeting concerned activities authorized for your
Crystal River facility.
The issues discussed at th's conference related to diesel generator loading and
cooling water temperatures.
A sumary, list of attendees, and a' copy of your
handout are. enclosed.
We are continuing our review of these issues to
determine the appropriate enforcement action.
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 and its enclosures
will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, please contact us.
Sincerely,
t
sS
J. Nelson Grace
Regional Admiriistrator
Enclosures:
1.
Enforcement Conference Summary
2.
List of Attendees
3.
Handout
cc w/encls:
(Seepage 2)
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MAR 151988
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Florida Power Corporation
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eg w/encls:
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W. F.- McKee, Di rector,
Nuclear Plant Operations
M . C. Simpson, Director,
Nuclear Site Support
bec w/encls:
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o V Lieberman, DOE
G..'R. Jenkins, EICS
LMC Resident-Inspector
'DRS Technical Assistant
Document Control Desk
State of Florida
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03/
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ENCLOSURE 1
ENFORCEMENT CONFERENCE SUMMARY
An Enforcement Conference was held on February 22, 1988, to discuss the
potential violation described in Inspection Report No. 50-302/87-41.
The licensee did not provide any information during the enforcement conference
which would require correction to the information in the inspection report.
The licensee did, however, point out that he reported to the NRC the fact that
the 30-minute rating of the diesel generators had been exceeded during previous
18-month surveillance test and the vendor recommended special inspections had
not been performed.
This information was verbally reported on September 14,
1987, and the licensee was give verbal approval to continue operation until
September 19, 1987, when the outage began.
While addressing the root cause and corrective actions for the proposed
violation, the licensee stated that he will expedite his Configuration
Management Program.
The licensee proposed extensive corrective actions
directed at the broad scope of potential design errors through the Configura-
tion Management Program.
The licensee suggested a meeting, at a date to be
detennined later, to discuss the details of the program, and the handling
of problems that may come to light as a result of the review process.
The adequacy of the ultimate heat sink temperature was discussed even though
this was not within the scope of Inspection Report No. 50-302/87-41.
Refer to
Enclosure 3 for details.
The licensee stated that his best estimate for the load on Diesel Generator A
is 3112kw.
This value was determined by calculation and testing and,
represents a blending of the two methods. A meeting is scheduled for March to
discuss options for reducing the load below the 30-minute rating range of
3001-3300kw.
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ENFORCEMENT CONFERENCE
LIST OF ATTENDEES
LICENSEE: FPC
DATE:
2/22/88
FACILITY: CRYSTAL RIVER
IR NO:
LOCATION: ATLANTA, GA
NAME.
POSITION / TITLE
ORGANIZATION
Malcolm L. Ernst
NRC/RII
Luis A. Reyes
Director, DRP
NRC/RII
Herbert N. Berkow
Director, PDII-2
NRC/NRR
Harley Silver
PM CR-3
NRC/NR3
Tom Stetka
NRC
Paul Fillion
Reactor Inspector
NRC/RII
T. E. Conlon
Chief, PSS
NRC/RII
Paul R. Tanguay
Mgr. Mech /Struct Engrg
Donald A. Shook
Mgr., Elect /I&C Eng
E. C. Simpson
Dir., Nuc. Ops. Engineering
and Licensing
K. R. Wilson
Mgr., Nuclear Licensing
D. G. Green
Licensing Specialist
Walter S. W11gus
V. P., Nuclear Ops.
R. C. Widell
Mgr., Nuclear Eng
R. V. Crienjak
Section Chief /DRP
NRC/RII
Howard Wong
Sr. Enforcement Specialist
NRCOE
George R. Jenkins
Director, EICS
NRC/RII
A. R. Herdt
Chief, Engineering Bra.ich
NRC/RII
B. D. Wilson
Chief, Projects Branch 2
NRC/RII
McKenzie Thomas
Reactor Inspector
NRC/RII
R. H. Bernhard
Reactor Inspector
NRC/RII
M. S. Lewis
Reactor Inspector
NRC/RII
Bruno Uryc
Enforcement Coordinator
NRC/RII
John D. Schiffgens
NRC/NRR
Dominic Tondi
Section Chief
NRC/NRR/ DEST
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ENCLOSURE 3
February 22, 1988
ENFORCEMENT CONFERENCE
AGENDA
Introduction
Hally N11gus
Chronology
Ken Nilson
Corrective Actions
Rolf Hidell
Conclusions / Mitigating Circumstances
Bert Simpson
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IHDBUM SODPE
Tectnical Wicatica required a 60 mimte duraticm test at 2
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3000 kw. 'the diesel ratirq is for S 30 airutes between 3001 ard
3300 kW.
'Iherefore, Tacti Spas (ard hence p - trres) conflict with design
basis.
'Ihe calculated loads were haaari cn an a==unari + == A. poet-
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factor of 0.8, the actual "average" power factor is apprtaciately
0.9.
Parther, sczne loads were unitted.
'Iberefore, all reported diesel loads were underestinated ard the
additice of EFP-1 to the auto cuaCud loads pHM tha
& bility of lew11rg the EDG beycrd it's rated mpacity,
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'Ibctnical Specificaticns limit the ultisate heat sink (W)
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tyrature to 5105'F. 'Ibe design of the closed cycle safety-
related cooling systan (N, DC) ==neri a 85'F W inlet. 'Ihe
clocu3 cycle system have a 105'F limit.
'Ihe clooed cycle limit may not be able to be maintained less than
105'F with Wad real ultimte heat sink taaperatures of up to
92*F.
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BERE!NCY DH! EEL Q!NERMtR
Q H EDEDGY
TIMDG
IESQtIPTICH
July, 1974
PSAR revised awpac+=d lead fmn 2917 kw
(PGAR) to 2915 kw (within 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />
rating). Both PSAR and FSAR referenced
0.s power factor.
Martit, 1975
Chapter 15 'Ibtfrim1 Specifimtims
incitzled a 60 mimte tmt at 2915 kW.
nans=*=r, 1975
Mc arygestad a 1004 (3000 kw) test for
60 mimtes. FPC ag er e tly agreed and
'Ibcinical R=e ifications were so issued.
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July,1979
NEREG-0578 (2.1.7.a) regLtired motor
driven AFW ptmps be autcmatirmily 1rmiart
m emnergency bus.
July, 1979
FIC testad dIanal loads to dentmstrata
mrgin availahility. Iced was 2520 kw
without mu=?dcri for is.. -midant flow
rates or conservatively armwiting for
puma 11 loads.
Msy, 1980
FPC rrummitted to arriify EPP/EDG includirg
30 mimte trip to protect 30 minute
rating. Wimim haaari cri 2520 Mr test
value and 340 At ocultributical from EPP.
Atxpst, 1980
Re-performed arrif fied test with mi=ilar
rmults and shar+rreirgs.
Jtily, 1982
FSAR updated to reflect alculated worse
case load of 3180 kw.
August, 1986
[1Irirq perfnrmnae of SP-417 the DCP was
noted to not blodc load properly (UR 86-
15).
April, 1987
Pbllow-g to UR noted potetial for
"armaalve" voltage dip. C/CI also
calmlated worse case load >3300 kw.
'Ihis cala11atirn was in errut.
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April, 1987
FTC rgarted (UR 87-07) voltage dips
alirfitly more non-<rmervative that
desity/limansing basis. NFC/NRR folicWed
@ extensively begiming day-after red
Itama rgart.
June, 1987
Marne case load calculated to be 3276
vice 3180 kw.
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August, 1987
91te 1&r: lear Erginearirg riotified
Licensing of potential ocmflict between
Tacti Spec and diesel ratings.
August, 1987
FIC firumli'M NTR same day lagt; before
CErrI team ====har inquired about 'IWit.
Spec. value and it's relation to
ratings. FPC brought CErrI team q>-to-
date with our own zwiaw.
Seph=har, 1987
Colt h==arited clarified ratings,
detailed recylized maintenance and
ccrmrred with cperation tmtil Refuel VI
after meeting at Cblt, etc.
Sqtr=+cr - Octr+pr, 1987
FPC in an effort to renove e_q
ccnoervatism frun calculations looked
into debila of loads, power factors,
,
wM<=1t scenaries, etc. FPC ideritified
arti both Colt any G/CI ocmfI* power
factor error.
October, 1987
IIR 87-19 reported Tecti Spec / Design
conflict.
FTC notaa mm as ". ..'Ihe ocmflict
betwecn Tat Spec acceptance criteria and
the design rating limit was never
rarrrytized or resolved...".
It was
suumarized in the space limited abstract
as an agparent misinterpretatics of the
,
ratirgs early in plant life (e.g. Wum
the 'Iwis Spec was yW).
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MITIGEING CIRCGEEDN3S
DERENCY DIESEL GNPENIT
o FTC idmtified prtblan as a result of rreself-diarlosirq
supon== tic review prmaasw==.
OS'I'I team idetification as
either dcw- eid. cn E idmtificaticn or omcurret with it.
o E is swirq extensive mocdve actions directed at broad
socpe of potential design errors through Ctnfiguration Management
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w.
'Ihis effort as undermy before ED3 probles as
riisamvered.
'Ihe ptatial overleed sceario is very Innote (loss of offsite
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power, ocncurrmt with EDG-B failure, emcurret with interwdiate
or large break IOCA) . In fact, the evmt is ncn-medanistic for
CR-3 (4-.
cdanted 11cmoed Inak-Defore-Break) .
'Ihe p*mtlal for timply ard effective cperator intervmticn is
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good. Operator, by EDP's, has always throttled HPI flow ard
manrad EDG loads,
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o E took sus, and effective u.uuvdve acticns -f ated with
Epecific prtblGR.
Scujht and gained Colt ardKocnourrmae to ocntime
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operatitz) for a fat days prior to tear down.
'Ibok significant actions to IMm loads to less than 3000
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kw.
Act:epted staff foertwst to reevaluate one arrif fication (EFP-1
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trip) ard revised 'Ibch Spec charge recpest to allow cperatico
in 30 mimte ratirg.
Prmmad exrmpticn when NFC achinistrative su --ws couldn't
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han11e original staff proposal.
Avoided cperatar turden are unwarranted decreases in safety
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mrgins in resolvirg iswawi.
o E does not have a history of significant design basis errors.
'Ihe invalid aas-tion was reascnable ard omaistet with irdustry
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ard NRC gnirknce (R.G.1.9)
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%.tcic action (drgping off 1 RB Cooling thit) would harve beam
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effective if naadsd.
o 'Ihe potetial for -ive Sli tauperature is sanall ( M heat
lovl in RB) .
Limited n=har of wuds affected (Sperit Fuel Rap and control
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complex Q1111er).
Analysis conservatim my yet be adegata to overazne error.
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ULTIMATE HEAT SIhK TEMPERATURE
Licensing Basis for 3-3 - 85'F Max.
Normally Observed Peak Susumer Temp. - 92*F
Operation Justified Until RH Temperature Exceeds 85'F
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SM/DC Design 105'F Nax.
SM/DC Calculated Max. for LOCA
Exceeds 105'F for 25 Minutes
Peak Temperature 110*F
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RH Temperature at 95'F
3 RB Fan Coolors Operating
All Equipment for Accident Mitigation On Line
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CRYSTAL RI'/ER UN*.T 3
CCNflGURATION M ANAGEM' INT PROGRAM
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FRIB4 REACTIR
3 TD REACTIR
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VESSEL
VESSEL
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DECAY K AT
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PLANT
PLANT
HEAT
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HEAT
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LOADS
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LOADS
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NuCtE4R StRv1CES
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CLDSED CYCLE
DECAY EAT _g,
_,,
CM LING PU W S
CLDSED CYCLE
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COOLING PUWS
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105 Deg
105 Deg
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uuctEaR SERvrCES
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DECAY EAT
CtDSE CYCtE
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NUCLEAR SERVICES
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SEAVATER PUWS
DECAY EAT
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SEAVATER PUMPS
SEAVATER
45 Deg~
DiSCuaRGE
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CONFIGURATION MANAGEMENT AT CR-3
o FPC HAS ALWAYS BEEN SENSITIVE TO CONFIGURATION MANAGEMENT
ORIGINAL DRAWINGS MAINTAINED BY FPC
CONTROLLED DESIGN CHANGE PROCESS
PROCEDURE CHANGE CONTROL
o PROGRAMMATIC ENHANCEMENTS
ENHANCED CONTROL OF A/E'S
1980
MODIFICATION PRDJECT MANAGEMENT
JULY 1983
DESIGN BASIS DDCUMENT PROGRAM
OCT. 1983 - DEC. 1987
ENHANCED MODIFICATION PROCESS
AUGUST 1984
INSTRUMENT DATA SHEET / CALIBRATION SHEET
SEPT. 1985 - SEPT. 1989
REALIGNMENT OF ENGINEERING ORGANIZATION
1986
ENGINEERING ASSURANCE ORGANIZATION
1986
QUALITY PROGRAMS AUDIT PROGRAM
1986
ELECTRICAL DRAWING UPGRADE
1986 - 1988
ANALYSIS BASIS DOCUMENT
1987 - 1988
SURVEILLANCE PROCEDURE VERIFICATION / VALIDATION
1987 - 1988
COMPREHENSIVE DRAWING SYSTEM REVIEW
1987
SAFETY LISTING INTERIM ENHANCEMENTS
1987
CONFIGURATION MANAGEMENT PROGRAM PLAN
1987
TAG NUMBER DATA BASE
SAFETY LISTING COMPUTERIZATION
o WEAKNESS IN DOCUMEliTATION OF ORIGINAL DESIGN DEVELOPMENT
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CONFIGURATION MANAGEMENT PROGRAM
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IMPROVE THE QUALITY OF CONFIGURATION DATA
DESIGN BASIS RECONSTITUTION
DESIGN BASIS DOCUM:NT
ANALYSIS BASIS DOCliMENT
PRIORITIZATION
CONSISTENCY OF THE DATA
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DEVELOP OVERALL CONTROL ELEMENTS TO ASSURE HIGH QUALITY DATA
IS MAINTAINED
IDENTIFY ALL CONFIGURATION DOCUMENTS
IDENTIFY ALL SOURCES OF CHANGE
INTEGRATE OVERALL CONFIGURATION CONTROL
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EXPAND USER CAPABILITY OF THE DATA
COMON DATA BASE
BASED ON TAG NLMER
LINK TO OTHER AUTOMATED SYSTEMS
SPARE PARTF
AUTOMATED WORK REQUEST
CHANGE STATUS
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PROGRAM PLAN
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SAFETY CLASSIFICATION LIST PROGRAM
REQUIREMENTS DEFINITION
SOFTWARE DEVELOPMENT
DATA DEVELOPMENT
DATA MANAGEMENT SYSTEM DEVELOPMENT
IMPLEMENTATION
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DATA PROGRAMS
ENGINEERING CALCS PROGRAM
ENGINEERING DRAWING PROGRAM
ENGINEERING DATA LIST PROGRAM
CORE DATA PROGRAM
SURVEILLANCE PROGRAM VERIFICATION PROGRAM
ISI REQUIREMENTS INTEGRATION PROGRAM
DOCUMENT UPGRADE PROGRAM
TAG YALIDATION PROGRAM
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PROCESS ENHANCEMENT PROGRAM
CONFIGURATION CONTROL PROCESS DEVELOPMENT
CM DATA DEVELOPMENT PROGRAM
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MAINTENANCE SYSTEM PROGRAMS
DEVELOPMENT AND IMPLEMENT MAINTENANCE SYSTEM
CM INTERFACE WITH MAINTENANCE SYSTEM
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CMIS DESIGN
CONCEPT DEFINITION
INTEGRATED SYSTEM REQUIREMENTS
INTERFACING SYSTEM REQUIREMENTS
REQUIREMENTS FINALIZATION
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CMIS SOFTWARE DEVELOPENT PROGRAM
SAFETY CLASSIFICATION LIST SOFTWARE
CMIS INTEGRATED SOFTWARE
CMIS INTERFACING SOFTWARE
DATA DEVELOPENT SUPPORT
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IMPLEMENTATION PROGRAM
OPERATING ORGANIZATION
TRAINING
CM PROGRAM DOCUMENTATION
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PROGRAM MANAGEMENT
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ORGANIZATION
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PROGRAM MANAGER AND KEY LEAD POSITIONS FILLED BY FPC PERSONNEL
KNOWLEDGE OF PLANT, PA0BLEMS AND SYSTEMS
CONTROL OF SCHEDULE AND BUDGET
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PROGRAM MANAGER REPORTS TO MANAGER, NUCLEAR OPERATIONS ENGINEERING
RESPONSIBLE FOR DESIGN CONTROL /CR-3 DESIGN BASIS
INTEGRAL PART OF ENGINEERING ORGANIZATION
STRONG INTERFACE WITH OTHER KEY FUNCTIONAL AREAS
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IN-HOUSE CONTRACTOR SUPPORT
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FORMALLY IN EFFECT MARCH 1988
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SCHEDULE
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OVERALL PROGRAM
4-5 YEARS
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DESIGN BASIS RECONSTITUTION
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EXPEDITE SCHEDULE
PRIORITY NUCLEAR OPERATIONS PROGRAM
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BUDGET
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APPROXIMATELY $1.5 MILLION PER YEAR
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CONCLUSION
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FPC NUCLEAR PHILOSOPHY HAS ALWAYS BEEN SENSITIVE TO THE
CONTROL OF PLANT CONFIGURATION
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FPC HAS EXPENDED CONSIDERABLE RESOURCES TO UPGRADE PROGRAM
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IDENTIFICATION OF PROBLEMS WAS NOT A SURPRISE
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PLAN FOR MAJOR REVIEW OF DESIGN BASIS IN PLACE BEFORE OSTI
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DESIGN BASIS REVIEW / RECONSTITUTION IS BEING EXPEDITED
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