ML16161A882
| ML16161A882 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/30/1987 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16161A883 | List: |
| References | |
| 50-269-87-30, 50-270-87-30, 50-287-87-30, NUDOCS 8710050421 | |
| Download: ML16161A882 (23) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Duke Power Company Docket Nos. 50-269, 50-270 and 50-287 Oconee License Nos. DPR-38, DPR-47 and DPR-55 During the Nuclear Regulatory Commission (NRC) inspection conducted on July 21-24,
- 1987, a violation of NRC requirements was identified.
The violation involved failure to include in operations procedures the Final Safety Analysis Report (FSAR) value of 750F for the maximum low pressure service water (LPSW) inlet temperature and failure to perform a safety evaluation for operation with the LPSW inlet temperature above 750 F. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1986), the violation is listed below:
10 CFR 50, Appendix B, Criterion III, requires in part that measures shall be established to assure that the design basis, as defined in 10 CFR 50.2 and as specified in the license application, for those structures,
- systems, and components to which Appendix B applies are correctly translated into procedures and instructions.
The Oconee FSAR states that the design value for the LPSW system inlet temperature is 750F.
This value is also the maximum LPSW inlet temperature assumed in the Oconee design basis accident analyses for the Low Pressure Injection (LPI) coolers and Reactor Building Cooling Units (RBCU) coolers.
Contrary to the above, as of May 1, 1987, the LPSW inlet temperature had exceeded 750 F for various lengths of time during nine of the past 11 years. An evaluation was not performed to determine the consequences of the higher LPSW temperatures on the accident analyses; and there were no procedures to monitor or detect LPSW inlet temperature for compliance with the limit.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notff a written statement or explanation in reply including:
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results 8710050421 870930 PDR ADOCK 05000269 PDR
Duke Power Company 2
Docket Nos. 50-269, 50-270 and 50-287 Oconee License Nos. DPR-38, DPR-47 and DPR-55
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending the response time.
FOR TH NUCLEAR REG 5
ULATOY CO MISSION J. Nelson Grace Regional Administrator Dated at Atlanta, Georgia this kday of September 1987
ENCLOSURE 2 Enforcement Conference Summary On September 15, 1987, representatives of the Duke Power Company (DPC) met with the NRC at the NRC's request in the Region. II office in Atlanta, Georgia.
The topic of discussion was operation of Oconee Units 1, 2, and 3 with LPSW inlet temperatures greater than the value stated in the FSAR (750 F) and assumed in the design basis accident analysis.
The list of those attending the Enforcement Conference is in Attachment 1.
Following opening remarks given by Dr. J. N. Grace,
- NRC, Region II Regional Administrator, DPC gave a presentation which addressed the specific concerns that the NRC had requested.
The presentation consisted of a system overview, history, safety significance, and corrective actions.
The outline of the DPC presentation is contained herein as Attachment 2.
NRC concerns with whether adequate measures have been established for ascertaining when FSAR values used in procedures or accident analyses have been exceeded were expressed. DPC responded by stating that a system-by-system review is being performed to determine if other FSAR values used in accident analyses calculations have been overlooked or exceeded.
It is the NRC's understanding that this system-by-system review will continue until all safety-related systems have been reviewed.
This meeting served to enhance Region II's understanding of the issue and DPC's plans to prevent recurrence of similar problems.
The NRC enforcement action concerning this issue is discussed in Enclosure 1.
Attachments:
- 1. List of Attendees at the Oconee Enforcement Conference
- 2. Oconee Nuclear Station Elevated Lake Water Temperature -
NRC Meeting September 15, 1987
ATTACHMENT 1 Enforcement Conference DPC-Oconee Attendees NRC J. N. Grace, Regional Administrator L. A. Reyes, Director, Division of Reactor Projects (DRP)
T. A. Peebles, Acting Branch Chief, DRP F. Jape, Section Chief, Division of Reactor Safety (DRS)
B. Bonser, Project Engineer, DRP M. Thomas, Reactor Inspector, DRS R. Bernhard, Reactor Inspector, DRS B. Uryc, Enforcement Coordinator H. N. Postis, Oconee Project Manager - NRR A. R. Herdt, Branch Chief, DRS G. R. Jenkins, Director, EICS A. F. Gibson, Director, DRS DPC H. B. Tucker, Vice President, Nuclear Production M. S. Tuckman, Oconee Station Manager G. B. Swindlehurst, Supervising Design Engineer N. Rutherford, System Engineer, Licensing C. Harlin, Oconee Compliance Engineer D. M. Hubbard, Oconee Performance Engineer
ATTACHMENT 2 OCONEE NUCL~EAR STATI ON ELE4AED L4AKE TEPERATU NRC M8EETING SEPTEM4BER 15 19 87
ATTACHMENT 2 2
M]EML IR p0jr u Ez m WTZ("
DOI M IE 2: W C=
X S'YS'ICEM OVRRVXEW
-CCW Syc3r#--m A-==, -&rig o--mf--r"r CCW ryp:Lc--.-xJL Yl-c>w D:Laa'jc.'am JPSW Sc:)-Lxjcc--o--
D:Ua&ir-m IPSW FXcDw D:L-Lg-=-.-am I, P S W I, C).-a a:s Hmslcon"y Cli c>rac>3Lc>ay Wat c_-jr rr *--mp o- -rja xx -. v c--
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- L C> E S.a E Nc>rl-SaEfaity Ic>.aa s
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XV.
COnnRC'rTVR AC!rXONS D-LR*-- R3nS:Lrxo--f--=:LriS
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ATTACHMEO 1
3 815
.1 7968O 8100 FULL POND 800m MAX.
ALLOWABLE 775 3
TOP OF. 770 WEIR BOTTOM OF 761 INTAKE EMERG. CCW DIC LINE T. 8.
PRW CC 9
A.B.
SSF WH R
CONTINUATION OF EMERG. CCW DISC. TO INTAKE PIPING ON cc -2 PipingU Layout miul Y/UU-
ATTACHMENT 2 4
FROM INTAKE Ccv LCSTRUCTURE BC C
cCvi ccw cCw ccw O
II 12 TO ATMOSPIILAE TO CONT. PRIMING CCW COOLER TO ATMOSPHENE rco as Ccw-8I rc COOL ERS CONDENSATE SURtGE COLUMN COOLERS TO UNWATERING
.a COOLER PUMP (S)
Lit CCW CHOSSOVER CCW-40 CC-4CC 79 ECCw-70 C
EFWPT A
6OIL COOLER ac cow a'
c,"
ae 20212 UNWATERING PUMP RCW COOLERS, LPSW.
I4pSW RETUIRNS
-jw TO ATMOSPtIifftf CONT. PRIMING PUMPS (Is d
____11-28-84 bi tal.IiNl NSII NClCULATINI 0
~
UNIT I (TY ICAl.)
1
ATTACHMENT 2 5
Urit 3
Un it 2
LPSW A B
Unit 1
ATTACH
@ 6 jM..~
ccwM)I I~vENL..
PSW LIN
'I aE iMWANEV AsI CROSSOVER I~P.
IAIIE Lpw"to COOLERS i615411 Is i-IO FooRIVEN ccwFi pfok OCAGEICYF VOW PUr INS lot.
an, EN "P. Fat mo aMME CCI ING OIL COLER OIL COOLER A
PA.
CCVW LOADS SOrvt t
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hIIE mMOOSAIE FLOWw I)ICRA OF
-Izo OCONEEI NUCLEA STATION 3IGR 9.2-4 LP t*~6Lld
ATTACHME@
LOW PRESSURE SERVICE WATER SYSTEM (REACTOR BUILDING & AUXILIARY BUILDING)
LPWS 1P1tt LhME '3 r
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2 a
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11
ATTACHMENT 2 8
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ATTACHMENT 2 9
CHRONOL~OGY 2/6/86 Evaluation of McGuire heat exchanger fouiliig le~d to rec ormmen dat i on t o periodically test LPI anid RBCU coolers 2/86 Cooler degradationl wa~s to obsered nd analyzed using 3/87 best available analytical methods.
Anialys is resuilts showed acceptable for fuill power operations.
3/30/87 Coolers were evlated for post accident conditions and f ound to be u~nac cepta ble for futill power operation 5/1/87 Problem of elevated lake water temper atuire i dent ifiead by McKenzie Thomas in NRC Excit Interviiew.
5/13/87 Meeting held with Region II to discuss cooler fouilirg 7/21/87 Meeting held with ONRR to disctuss cooler fouilinig 7/23/87 Safety Ev.aluiation completed for operation with elevated lake wAater temp eratture.
ATTACHMENO
- 10 OCONEE NUCLEAR STATION CCW INLET TEMPERATURE HISTORY 85 80 75 70 65 60 1-55
- 50 m
45 -
40
-u-I-
-n 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 1986 1987 1976-1987
ATTACHMENT 2 11 OCONEE NUCLEAR STATION STATISTICS FOR CCW INLET TEMPERATURE HISTORY
- 75 DEGREES F
- 80 DEGREES F
- YEAR PEAK DATE EXCEEDED DURATION DATE EXCEEDED DURATION 1976 76.9 August 29 38 days 1977 75.7 September 26 11 days 1978 78.1 August 27 44 days 1979 74.4 1980 79.7 August ??
>30 days 1981 78.3 August 2 63 days 1982 74.1 1983 79.1 August 23 48 days 1984 78.3 August 17 50 days 1985 79.2 July 26 75 days 1986 81.7 July 15 92 days August 6 25 days 1987 81.6*
July 30 40 days*
August 19 20 days*
- The above data is current through September 7, 1987.
CCW Inlet Temperature is still above 750 F.
ATTACHMENT 2 12 SAFETY RELATED HEAT EXCHANGERS ORIGINAL SYSTEM DESIGN ('F)
COMMENTS LPSW SYSTEM HPI PUMP MOTOR BEARING 100.4*
OK COOLING JACKET MDEFW PUMP MOTOR COOLER 950 OK TDEFW PUMP TURBINE LUBE 78*
MUST KEEP OIL TEMP <160 0 F OIL COOLER TESTED AT 78*F AND OIL TEMF
=
129.7*F CALC SHOWS WITH 85*F WATER, OIL TEMP =
137'F THEREFORE OK TDEFW PUMP BEARING 950 OK JACKET COOLER LPI COOLERS 750 OK TO 850 WHEN CLEAN RBCU 750 OK TO 850 WHEN CLEAN LPSW PUMP NPSH 900 TEMP USED TO DETERMINE MIN LAKE LEVEL HPSW SYSTEM CCW PUMP MOTOR COOLERS 850 OK HPSW PUMP MOTOR AIR 93.20 OK COOLERS CCW PUMP SEALS 125*
OK HPSW PUMP SEALS 125*
OK AUX SERVICE WATER SYSTEM EFW SOURCE OF WATER 900 OK
ATTACHMENT 2 13 SYSTEM ORIGINAL SSF AUX SERVICE WATER SYSTEM DESIGN (oF)
COMMENTS SSF ASW PUMP NPSH 1000 OK SSF DIESEL COOLING 870 OK SSF HVAC 750 OK-With slight modifica tion to system operations.
KEOWEE HYDRO TURBINE-GENERATOR OIL/AIR 850 OK COOLERS
ATTACHMENT 2 14 Alr 8 5 ccw S"Yslrvm CONDIENSArrM COOIRnS ILPSW S"YS=M nCP MO'"EOI:Z COOILEnS MAMN
RBMNR OTL. rANK COOILRR MSR DR.AXN PUMP COOILHR rB SUMP PUMP SBAILS r]CB SUMP SAMPI IE BACKWASH MNS'1CnUMRN7r AMR COMPnRSSOR COOIRnS FLADTA=ON MONTrrOR SAMPIB COOIRnS MAKR-UP DMMMNRRAIXZRn MAL AMR COMPnRSSOR POT-.XSHXNC I)HI-IXNRI;LAI=Hn AMR COMPRRSSOR MAIIN VACUUM PUMP SIEAILS CON=NUOUS VACUUM PnXMXNC; PUMP S-AIS nB AUXXT MARIZ COOL.RnS AUXTIMAn'Y BIDC; AMR HANDITNO UN=S CON'ICROIL ROOM A/C CHXI-.I.BnS ncw SYS=M XNS rHUMIENrr AMR COMPRRSSOR SI-EnVXCIE AMR COMPRRSSOR SPIENrr YUI-IL COOIMRS SRAI nF-'EUR.N COOILRn S/C; AND PnMSSXJRTZRn SAMPT R COOI MnS WAS
C;AS COMPRRSSOn
,,Dtt HmA rRn mRAmN Pump cooi.Rn "B"
HRA r3En DRAMN PUMP'COOL.IER CONDF-NsAvr]E BooSrrF-R PUMP COOL.]En HorrwmL.T-.
PUMP COOL.Hn IEI..IECrr]ROHWIDRAUT-.J[C CONrrROL.
OXI-.
COOILIEn PRRDWArrRn PUMP rrURBMNB OML. COOL.RR TSOT.A=n PHASM BUS COOT-.]En AIL=nNArrOn AMR COOL.RR RC BI-RZD, WASrrM, AND.MN-rMnXM RVAPOP-A-EOnS cc SwSrrmM nCP rHIEIZMAI, BAJRRXRH HX A14D SRAIL COOIXNO aACKRrrS QURNCH r-&NK COOI..Zn I.RwrDOWN Cooilmn CRID COOI-.MNC; COMI-,S
ATTACHMENT 2 is RADWASTE FACILITY INSTRUMENT AIR COMPRESSOR INSTRUMENT AIR DRYER BREATHING AIR COMPRESSOR SEAL WATER LOOP EC SUPPLY PUMP NPSH EC CIRCULATING PUMP NPSH AEROJET CONDENSER PUMP NPSH LW EVAPORATOR CHEMICAL CLEANING CHEMICAL CLEANING EQUIPMENT AND HEAT EXCHANGERS
ATTACHMENT 2 16 DESIGNT CRITERIA NORMAL PLAT OPERATI ONS REACTOR BUILDING COOLING UNITS MAIN TAIN CONTAINMENT ENVIRONMENT RBCU OPERATE UNDER DRY AIR CONDITIONS USING SENSIBLE HEAT TRANSFER COMBINED HEAT REMOVAL OF BOTH TRAINS OF LPI CAN COOL REACTOR FROM 250 DEGREES TO 140 DEGREES IN 14 HOURS EMERGEN CY PLA]NTD OPERAT I ONS COMBINED HEAT REMOVAL CAPABILITY OF RBCU' S
AND LPI CAN MEET ACCIDENT HEAT GENERATION IN CONTAINMENT LOSS OF COOLANT ACCIDENT HEAT REMOVAL AT 30 MINUTE TIME FRAME (AFTER INJECTION PHASE)
LOSS OF COOLANT ACCIDENT HEAT REMOVAL LONG TERM TO ASSURE THAT CONTAINMENT TEMPERATURE PROFILE MATCHES ENVIRONMENTAL QUA IF I CA TION REQUIREMENTS 0
10 s
125' ramp to 286*F 10 sec 10 mir 286 0 F 10 miii 24 hr 286F aramp tc>
125"F 24 hrs 125*F ABOVE CRITERIA ASSUMES THE LOSS OF THE BEST LPI COOLER BEST REACTOR BUILDING COOLING UNIT AS WELL AS OTHER CREDIBLE SINGTLE FAILURES
ATTACHMENT 2
- 17.
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ATTACHMENT 2 0
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