ML20248K972
| ML20248K972 | |
| Person / Time | |
|---|---|
| Issue date: | 06/03/1998 |
| From: | Stolz J NRC (Affiliation Not Assigned) |
| To: | Roe J NRC (Affiliation Not Assigned) |
| References | |
| OREM-98-4, NUDOCS 9806100360 | |
| Download: ML20248K972 (11) | |
Text
.
June 3,1998
- o--
MEMORANDUM TO: Jack'W. Roe, Acting Director i
Division of Reactor Program Management FROM:
' John F. Stolz, Chief [ Original signed by]
Events Assessment, Generic Communications and Specialinspections Branch Division of Reactor Program Management
SUBJECT:
~ OPERATING REACTORS EVENTS BRIEFING MAY 20,1998 - BRIEFING 98-04 l
On May 20,1998, we conducted an Operating Reactors Events Briefing (98-04) to inform
. senior menagers from the Offices of the Commission, EDO, AEOD, NRR and regional offices of
- selected events that occurred since our last briefing on February 18,1998. Attachment i lists
- the attendees. Attachment 2 presents the significant elements of the discussed event.
- The statements contained in the attached briefing slides represent the best information currently available to the NRC. Future followup could produce new information that may alter the NRC's current view of the event discussed.
Attachments:
As stated (2) cc w/atts:
. See next page CONTACT: Kathy Gray, NRR (301)415-1166 e
e6: (w/atts) 3 PUBLIC LKilgore, SECY
/
PECB R/F KGray RKhan DOCUMENT NAME: G:\\KAG\\ORTRANS "E" =
"C" = Copy]without attachment / enclosure To receive a copy of tMs document, indicate in the box:
n W Copy with attachmen'./ enclosure "N" p No copy a e OFFICE PECB,/,j-lE PECB \\j] _ f PECM7 V CfPfCSU N
NAME KGrayN(Jlloy -
RKhan V @ RDddnik JStolz.
DATE-Ob/ o f /98 4
06/ O//98 06/ V /98 06/ 7 /98 OFFICIAL RECORD COPY m'
{$SE CU CEN a
,i ME E.
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_____,_,____._l_'_
Y o-cc:
S. Collins, NRR (0-12G18)
P. Tam, NRR (0-14H25)
F. Miraglia, NRR (0-12G18)
H. Berkow, NRR (0-14H25)
F. Gillespie, NRR (0-12G18)
- 8. Boger, NRR (0-14E4)
B. Sheron, NRR (0-12G18)
J. Zwolinski, NRR (0-14H3)
E. Adensam, NRR (0-13E4)
G. Lainas, NRR (0-7D26)
G. Holahan, NRR (0-8E2)
D. O'Neal, NRR (0-10E4)
L. Spessard, NRR (0-9E4)
M. Markley, ACRS (T-2E26)
T. Martin, AEOD (T-4D18)
C. Rossi, AEOD (T-4A9)
F. Congel, AEOD (T-4D28)
R. Barrett, AEOD (T-4A43)
S. Rubin, AEOD (T-4D28)
M. Harper, AEOD (T-4A9)
W. Leschek, AEOD (T-4A9)
G. Tracy, EDO (0-16E15)
J. Gilliland, PA (0-2G4)
D. Morrison, RES (T-10F12)
W. Hill, SECY (0-16G15)
H. Miller, Region I C. Hehl, Region I L. Reyes, Region ll L. Plisco, Region 11 S. Vias, Region il J. Caldwell, Region lli G. Grant, Region lli E. Mershoff, Region IV-P. Gwynn, Region IV K. Perkins, Region IViWCFO G. Fader, INPO J. Zimmer, DOE
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UNITED STATES j
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 3008H001
/
June 3,1998 MEMORANDUM TO: Jack W. Roe, Acting Director Division of Reactor Program Management J Events Assessment, Generic Communications FROM:
1 John F. Stolz, Chief and Specialinspections Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING MAY 20,1998 - BRIEFING 98-04 On May 20,1998, we conoucted an Operating Reactors Events Briefing (98-04) to inform senior managers from the Offices of the Commission, EDO, AEOD, NRR and regional offices of selected events that occurred since our last briefing on February 18,1998. Attachment i lists the attendees. Attachment 2 presents the significant elements of the discussed event.
The statements contained in the attached briefing slides represent the best information currently available to the NRC. Future followup could produce new information that may alter the NRC's current view of the event discussed.
Attachments:
As stated (2) cc w/atts:
See next page CONTACT: Kathy Gray, NRR (301) 415-1166
e j
~
LIST OF ATTENDEES -
OPERATING REACTORS EVENTS FULL BRIEFING (98-04)
May 20,1998 i
NAME QEELCE NAME OFFICE R. Khan NRR W. LeFave NRR R. Dennig NRR J. Rajan NRR K. Gray NRR G. Hubbard NRR B. Sweeney NRR P. Tam
-AEOD D. Desaulniers NRR M. Tschiltz OEDO C. Petrone NRR P. Cat,tleman OCM/NJD E. Goodwin NRR M. Miller OCM/SAJ l
TELEPHONE ATTENDANCE (AT ROLL CALL)
Regions Resident Insoectors Region i Region ll Region lli Region IV I
M K. Landis, AIT Team Leader ATTACHMENT 1
~
~
98-04 L
l l
l OPERATING REACTORS EVENTS BRIEFING 98-04 LOCATION:
0-10B11, WHITE FLINT WEDNESDAY, MAY 20. 1998 11:00 A.M.
CATAWBA, UNIT 1 AUXILIARY FEEDWATER (AFW)
INOPERABILITY DUE TO SUCTION SOURCE HIGH WATER TEMPERATURE PRESENTED BY:
EVENTS ASSESSMENT,' GENERIC COMMUNICATIONS AND SPECIAL INSPECTION BRANCH DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR ATTACHMENT 2
r 98-04 CATAWBA, UNIT 1 AUXILIARY FEEDWATER (AFW) INOPERABILITY DUE T0 SUCTION. SOURCE HIGH WATER TEMPERATURE MAY 7, 1998 PROBLEM e
POTENTIAL AFW SYSTEM INOPERABILITY DUE TO UNEXPECTED &
IMPROPER CONTROL VALVE SET POINT.
SAFETY SIGNIFICANCE e
AFW SYSTEM IS A SAFETY-RELATED COOLING WATER SOURCE FOR SEVERAL TRANSIENTS & ACCIDENTS.
l PLANT CONDITION O
ON 5/7/98, POWER WAS BEING REDUCED DUE TO AN UNRELATED ISSUE.
O-AT 30-40% POWER, THE UPPER SURGE TANK (UST) HI TEMPERATURE (130 F) & HI-HI TEMPERATURE (134 F) ALARMS ACTUATED.
1
. CONTACT:
R. KHAN NRR/DRPM/PECB AIT: XES
~
REFERENCE:
-10 CFR 50.72 #34191:
SIGEVENT: IBD PNO-2-98-025
^
2 98-04 GD EVENTUALLY, EXCESSIVE FLOW THRU 1-CM-127. THE MINIMUM FLOW RECIRCULATION VALVE FOR CONDENSATE B00 STER PUMPS (CBP) WAS IDENTIFIED AS THE CAUSE AND WAS ISOLATED.
UST WATER TEMPERATURE DROPPED RAPIDLY.
Gb AFW SYSTEM WAS DECLARED INOPERABLE BECAUSE OF CONCERNS
- WITH THE EFFECTS OF ELEVATED SUCTION SOURCE WATER TEMPERATURE.
dp THF. SYSTEM WAS DECLARED OPERABLE THE NEXT MORNING AFTER i
FURTHER EVALUATION.
I DISCUSSION ED UST & HOTWELL ARE THE PREFERRED NON-SAFETY RELATED SOURCE OF WATER FOR THE AFW SYSTEM.
NUCLEAR SERVICE WATER IS THE SAFETY-RELATED SOURCE.
GD 1-CM-127, LOCATED DOWNSTREAM OF THE INTERMEDIATE PRESSURE FEEDWATER HEATERS MAINTAINS MINIMUM FLOW FOR THE CBP BY DIVERTING IT INTO UST DOME.
tD-16" VENT:FROM UST TO THE MAIN CONDENSER.
l L
L 1D 1-CM-127 SET INCORRECTLY.
PASSED MORE THAN TWICE THE CBP
-MINIMUM FLOW TO UST.
UST WATER TEMP ROSE TO 234 F.
m-
-_-A.-._
~ - - _.
-l
f; 3
L 98-04 EVALUATION O
138 F IS THE MAXIMUM DESIGN BASIS SUCTION TEMPERATURE FOR
'AFW OPERATION & PERFORMANCE.
O AFW SYSTEM OPER!aILITY' COMM0h! MODE FAILURE:
NPSHa ++ NPSH A
AUTOMATIC SWAPOVER TO SAFETY-RELATED SOURCE ELEVATED WATER TEMPERATURE IMPACT ON AFW SYSTEM DESIGN BASES COOLING CAPABILITY O
SIX SIMILAR EVENTS IN LAST TWO YEARS.
NONE DECLARED AFW SYSTEM INOPERABLE.
O ROOT CAUSE INSUFFICIENT OPERATIONS AND ENGINEERING TRAINING INADEQUATE PROCEDURES
~
O'
.0THER-POTENTIAL SIMILAR FAILURE. MECHANISM FOR UST AND
.0THER AFW WATER SOURCES.
p 4
~
98-04 LICENSEE IMMEDIATE-AND LONG-TERM CORRECTIVE ACTIONS 9
IMMEDIATE 1-CM-127 & 2-CM-127 ISOLATED UNTIL LONG-TERM CORRECTIVE ACTIONS DEVELOPED & IMPLEMENTED EVALUATION & SYSTEM WALK DOWN TO INSPECT FOR DAMAGES, ESPECIALLY TO THE PIPING SYSTEM & TANKS DUE TO EXCESSIVE FLOW AND TEMPERATURE PROCEDURES MODIFICATION ALARM RESPONSE GUIDELINES WATER SOURCE SWAPOVER OPERATOR TRAINING ON PROCEDURE MODIFICATIONS FULL ROOT CAUSE ANALYSES l
AFW SYSTEM OPERABILITY WITH ELEVATED SOURCE WATER TEMPERATURE (Discussed Earlier) l l
5 98-04 CONSIDER DESIGN MODIFICATIONS PASSIVELY LIMIT 1-CM-127 VALVE OPENING A SEPARATE EMERGENCY FEEDWATER TANK NRC FOLLOWUP GD AUGMENTED INSPECTION TEAM (AIT) ESTABLISHED FOR INSPECTION AND ASSESSMENT.
ED NRR/DSSA/SPSB PERFORMING RISK ASSESSMENT FOR THE EVENT.
ED UST AS AFW SYSTEM WATER SOURCE AND MINIMUM FLOW RECIRCULATION LINE TO UST ARE UNIQUE TO THREE DUKE POWER PLANTS.
DUKE POWER NOTIFIED THE OTHER SITES.
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