ML20247E296
| ML20247E296 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/08/1989 |
| From: | Haughney C Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-89-032, OREM-89-32, NUDOCS 8909150253 | |
| Download: ML20247E296 (16) | |
Text
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September 8,1989 MEMORANLUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment L
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING September 6, 1989 - MEETING 89-32 On September 6, 1989, we conducted an Operating Reactors Events meeting (89-32) to brief senior managers from NRR, RES, AE0D, ACRS, Commission staff, and regional offices on selected events that occurred since our last meeting on August 30, 1989. Enclosure 1 lists the attendees.
Enclosure 2 presents the significant elements of the discussed events.
Enclosure 3 contains a summary of reactor scrams for the week ending 09/03/89.
We identified one significant event for input into the NRC performance indicator program and one event was suggested for long term followup.
Or hin 1tS w h :
Charles J. Enu ,lr..: r Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
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8909150253 890908 On - Ib PDR ORG NRRB PNU ,y _ __ ___ -_______ ____ ____ _ __
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T. Hurley, NRR R. Lo,I;ER F. tiiraglia, NRR E. Adensam, NRR L J. Sniezek,. fiRR J. Partlow.-NRR-E. Jcrean, AE00
'J. Taylor, EE0
'E. Beckjord, RES' W. Russell -RI S. Ebneter, RII k~ B. Davis, RIII R. D. Martin, RIVl J. B. Martin, RV W. Kane, RI L. Reyes, RII' E. Greenman', RIII J. Milhoan,.RIV R. Zimmerman, RV
-S. Varga, NRR B. Boger NER-G. Lainas, NRR G. Holahan, NRR .
F. Congel. NRR E. Weiss, AE0D' T. Martin, EDO J. Lieberman, OE J. Guttmann SECY
.A. Thadani. NRR J.-Richardson, NRR S. Rubin., AE00 J. Forsyth INP0 R. Barrett, NRR
~M. Harper. AE0D R. Newlin,'GPA J. Roe, NRR-H. Alderman, ACRS e
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C' NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 l
Y September 8,1989
!"Ef'CRANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE CPERATING REACTORS EVEllTS MEETINC September 6, IEE9 - MEETit!G 89-32 :
On September 6, 1989, we conducted an Operating Reactors Events meeting (89-32) to brief senior managers from NRR, RES, AE00, ACRS, Commission staff, and :
regional offices on selected events that occurred since our last meeting on August 30, 1989. Enclosure 1 lists the attendees.
Enclosure 2 presents the significant elenents of the discussed events.
Enclosure 3 contains a summary of reactor scrams for the week endino 09/03/89.
We identified one significant event for input into the NRC performance indicator program and one event was suggested for long term followup.
I
" i e
Charles J. Hau ney, Chief N?
C i'
Events Assessment Branch Division of Operational Events Assessment
Enclosures:
1 As stated cc w/ Encl.:
See Next Page i
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.l ENCLOSURE 1 1
l'IST 0F ATTENDEES" OPERATING REACTORS EVENTS BRIEFING-(89-32I September 6, 1989 NAME ORGANIZATION NAME ORGANIZATION J. Sniezek NPR/DONRR J. Roe' NRR/DLPQ H. Alderman ACRS G. Lainas NRR/DRP W. Troskoski' OE 'L. Plisco NRR/LPEB R. Borchardt EDO P..Baranowsky. NRR/00EA J. Particw . NRR/ADP B. Grimes NRR/DRIS W.'Minners RES/DSIR J. Zwolinski NRR/DLPQ R. Lobel- NRR/DOEA C. Rossi NRR/DOEA W.-LeFave NRR/ DST ~T. Greene NRR/D0EA E. Adensam- NRR/PD2-1 C. Haughney NRR/00EA :
M. Reardon NRR/00EA P. Bobe . AEOD/DSP R. Lo NRR/PDE-1 l
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ENCLOSURE.2
.c CFERATING REACTORS. EVEf.TS' ERIEFIt!C ES , EVENTS ASSESSMENT BRANCH LOCATION: -10E-11, kHITE FLINT hECNESCAY, SEPTEMEER 5, 1969, 11:00 A.M.
ROBINS 0h LNIT 2 INADECLATE NPSH FOR AUX FEEDWATER FUMPS (AIT LPDATE) r T
NOTE: THE OPERATING REACTOR (OR) ERIEFING ON 09/06/89 WAS VIDE 0
[QEfERENCED AT 11:00 A.M. REGION 11 VIEE0 CONFERENCES BACK TO HEAD 00ARTERS AT THAT TIME.
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," 89-32 ROBINSON UNIT 2
't' APE 00 ATE t'PSli FOR AUX FEEDWATER PUMPS ( AIT UPDFTE)
AUGUST 16, 1989 CN SEPTEMBER 6, 1989, THE AIT TEAM LEADER BRIEFED AIT PRELIMINARY FINDINGS. ;
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AIT: YES l SIGEVENT: YES
REFERENCES:
10 CFR 50.72 16375 AND PNO-II-89-59 I
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89-32 ROBINSON UNIT 2 ~
INADECU' ATE-NPSH OF AUX FEEDFATER POMP 1 AUGUST 16,'1989 FROBLEM INADECUATE NET POSITIVE SUCTION HEAD (NPSH) FOR THE' AUX.FEEDWATER .
PUMPS..
L CAUSE DESIGN DEFICIEMCY. ALL THREE PUMPS TAl:E SUCTION FROM THE CST THROUGH A COMMON SUCTION LINE.. TiiE SIZE OF THE SUCTION LINE (6 INCHES) LED TO EXCESSIVE HEAD LOSS.
SAFETY SI.GNIFICANCE :
POSSIBLE LOSS OF ONE OR MORE AUX FEEDWATER PUMPS DUE TO PUMP CAVITATION.
DISCUSSION o INADEQUATE NPSH FOR THE AUX FEEDWATER PUMPS UNDER ALL PUMP COMBINATIONS.
o THIS PROBLEM IS BELIEVED TO EXIST DURING ANY PLANT CONDITION WHERE THE AUX FEEDWATER SYSTEM IS REQUIRED (E.G., NORMAL SHUTDOWN OPERATION AND STEAM LINE BREAK).
- IN 1986, THE LICENSEE EXPERIENCED A LOSS OF FEEDWATER TRANSIENT IN WHICH' INADEQUATE FLOW WAS NOTED. (SEE TABLE 1) o GN AUGUST 16, 1989, THE LICENSEE BELIEVED THAT THE NPSH PROBLEM EXISTED ONLY WHEN THE STEAM DRIVEN AUX FEEDWATER PUMP WAS IN OPERATION, THUS THEY REMOVED THE STEAM DRIVEN PUMP FROM SERVICE BY DE-ENE'RGIZING THE BREAKERS TO THE STEAM DRIVEN PUMP STEAM SUPPLY VALVES.- THE LICENSEE ENTERED AN LCO WHICH REQUIRES THAT THE PUMP BE RETURNED TO SERVICE WITHIN SEVEN DAYS OR BE IN HOT SHUTDOWN WITHIN SIX HOURS.
AIT: YES CONTACT: R. AZUA SIGEVENT: YES
REFERENCES:
10 CFR 50.72s #16375, #16375, AND PNO-II-89-59
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ROBINSON 2~ - 89 > o LICENSEE' TECliz SPECS REQUIRE A MINIMUM OF 35,000 GALLONS FOR
.THE:AUXFEEDUATERIPUP/PST0-MAINTAINI!0TSHUTDOWNFOR2:HCURS, DL'E TO Tile' INADEQUATE NPSH AVAILABLE FOR THE STEAM DPIVEN PUFP.
AN ADMINISTRATIVE REQUIREMENT TO MAINTAIN CST LEVEL GREATER THAN OR EGUAL TO 60% WAS PLACED INTO EFFECT, c CUESTION RAISED DURING Tills REVIEW:
-l', WHY-DID THE LICENSEE NOT IDENTIFY THE NPSH INADEQUACY-FOLLOWING-THE 1986 LOSS OF FEEDWATER TRANSIEMT.
L THE LICENSEE HAS BEEN UNABLE TO ANSWER THIS QUESTION YET.
o ON AUGUST 22, 1989, Tile LICENSEE INITI ATED A PLANT: SHUTDOWN FOLLOWING_ ADDITIONAL ANALYSIS RESULTS WHICH IDENTIFIED THE MOTOR DRIVEN AUX FEEDWATER PUMPS AS HAVING SIMILAR NPSH PROBLEMS.
o THE LICENSEE ANTICIPATES TliAT REPLACEMENT OF AUX FEEDWATER SUCTION PIPING WITH A LARGER DIAMETER PIPING MAY BE REQUIRED TO IMPROVE NPSH AT RATED FLOW, FOLLOWUP o THIS EVENT WILL BE FOLLOWED BY Tile REGION'II STAFF AND THE RESIDENT INSPECTORS, o EAB WILL REVIEW THE POSSIBILITY THAT OTHER PLANTS MAY HAVE NPSH-PROBLEMS'IN THEIR AUX FEEDWATER SYSTEMS. OR OTHER
' SAFETY-RELATED PUMPS,
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89-32 l
l l TABLE I I
H.B. ROBINSON UNIT 2 AUXII.IARY FEEDWATER PUMP FLOWS l
1986 LOSS OF FEEDilATER EVENT DESIGN FLOW RECORDED FLOW 3
- 1. "A" MOTOR DRIVEN 300 GPM 150-200 GPM '
AUXILIARY FEEDWATER FUMP
- 2. "B" MOTOR DRIVEN 300 GPM 150-200 GPM AUXILIARY FEEDWATER PUMP
- 3. STEAM DRIVEN 600 GPM 385 GPM AUXILIARY FEEDWATER PUMP e
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ENCLOSURE 3 hh a &
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Page No. , 1 -
14/05/E9 .
FEFFDEr.ANCE INDICAT0FS SIGNIFICANT EVENTS FLANT NAME EVENT EVENT IESCElFTIDN GTE SIGNIFICANCE
- ATE 3 3
- ER 1 09/25/29 FREESURIZER Ct5 5AFETY VALVE LIFTED SFURIOUSLY, 0 FOTENTIAL FDR CR ACTUAL DEERADAilCN RELIEV!NB REACTCR C00LANT. CF FRIMARY CCDLANT FRES5URE FDUNIARY 0
e, AEACTOR SCRAM SUEARY WEEK ENDINE 09/03/B9
!, PLANT $FECIFIC IATA IA'E SITE UNIT R0WER S!SNAL CAUSE CD"FL1- YTD YTD YTD CATIONS AF0VE FEL0h TOTAL 151 131 OE/:S/S? t!AE'.0 lANtCN 2 100 M EQUIFFENT ND 3 0 3 0S/29/S9 SOUTH TEIAS 2 100 M EDU!FPENT N0 5 1 6 09/29/S9 VAD EE R0kE 0 1A FEF50hNEL N2 0 1 1 02/30/E9 F0fE CREEr 1 81 A EQUIFFENT ND 1 0 1 05/30/29 FILERI" 0 60 A EQUIFMENT ND ! 0 1 04/01/E9 EEAVEr ' ' LEY
. ! OA EQUIF*ENT N0 3 1 4 09/02/25 SAN ON0ril 2 25 P EQUIPMENT ND 1 1 2 09/03/S9 HATCH 2 70 A EQUIP =Ehi ND 1 0 1 4
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II.' COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES i- SCRAMS FOR WEEK'ENDING
.09/03/89 POWER . NUMBER 1989 1988 1987 1986 1985
' SCRAM CAUSE WEEKLY
, OF WEEKLY WEEKLY WEEKLY. WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (3)(4) (8)(9)
YTD t
- -POWER >15% 4.3 5.4
>15% 6 3.1 3.1 3.9 EGUIP. RELATED 1.3 1 . 18 :2. 0 0 1.1 1.0 PERS. RELATED(6) >15% 0.5 1.2 0.4 0.6 OTHER(7) >15% 0 0.1
- 1 Subtotal ** 6.5 8 .' O 6 4.3 4.6 6.4
'** POWER <15% 1.2' 1.4 1.3 EQUIP. RELATED <15% 1 0.4 0.5 0.3 0.3 0.6 0.8 0.9 PERS .oELATED. <15% .1 0 0.0 0.1 0.3 0.2 0. 2.
OTHER <15%
- Subtotal ** 2.1 2.4 2.4 2 0.7 0.9
- Total t**
8.5 8.9 10.4 8 5.0 5.5 MANUAL VS AUTO SCRAMS NUMBER 1989 1988 1987 1986 1985 TYPE WEEKLY OF WEEKLY WEEKLY WEEKLY - WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD 3 0.9 1.0 1.4 1.0 1.0 MANUAL SCRAMS 7.9 9 . <4 5 4.2 4.5 7.0
-AUTOMATIC SCRAMS s
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NOTES-1.- PLANT SPECIFIC DATA BASED CN INITIAL REVIEW 0F 50.72 REPORTSL I- FOR THE WEEK 0F. INTEREST...PERICP IS HIDNIGHT SUNDAY THROUGH
.!U0 NIGHT SUNCAY SCRAliS ARE DEFillED AS-FFACTOR PFOTECTIVE ACTUATIONSWHICfiRESULT.INR00 MOTION,ANDEXCtVDEPLANNED.
TESTS OR SCRAt15 AS-PART OF PLANNED SHUTCOWN IN'ACCOR0ANCE~
WITil A PLANT PRCCEDURE. THERE ARE 111' REACTORS HOLDIt.G AN OPERATING LICEt15E.
F. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSCFt:EL ERRORS Ut:REL ATED TC CAUSE OF SCRAtl. .
- 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN' ERROR, PROCEDURAL l- DEFICIENCIES,.AND MANUAL STEAM'GEf;ERATOR LEVEL CONTROL 1: PROBLEMS.
4 "0THER" It CLUDES AUT011ATIC ' SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.-
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