ML20045H473
| ML20045H473 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/15/1993 |
| From: | Packer D, Vinci D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-93-002-01, LER-93-2-1, W3F1-93-0164, W3F1-93-164, NUDOCS 9307200258 | |
| Download: ML20045H473 (12) | |
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- &m EM'Or9Y Entergy Operations, Inc.
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D. F. Packer -
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v.w e m W3F1-93-0164 A4.05 PR July 15, S93 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Jashington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reporting of Licensee Event Report Gentlemen:
Attached is Licensee Event Report Number LER-93-002-00 for Waterford Steam Electric Station Unit 3. This Licensee Event Report is submitted in accordance with the requirements of 10CFR50.73(a)(2)(iv).
Very truly yours, f
\ NI% % >h h x O P D.F. Packer j General Manager Plant Operations DFP/TWG/ssf Attachment l l
cc: J.L. Milhoan, NRC Region IV G.L. Florreich J.T. Wheelock - INPO Records Center ,I 4
I R.B. McGehee N.S. Reynolds NRC Resident Inspectors Office n9 ;
Administrator - LRPD (/
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1 9307200258 DR 930715 m ADOCK 05000382 k,"
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kRC FOBM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 15 921
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LICENSEE EVENT REPORT (LER) $$$?M"& E Ens"ts5 EOTlm2,"$^$
AND HECOROS MANAGEMENT BRANCH (MNBR 7714). U.S NUCLEAR REGULATORY COMMEstON. WASHINGTON, DC 205%-00C1, AND TO THE PAPEPWORK REDUOTION PROJECT piAD01Nh OFFICE OF (see feverSe IOT reQuHed number Of digits / Characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20501 FACILfTV NAME (1) DOCKEl NUMBER (7) FAGE (31 l Waterford Steam Electric Station Unit 3 05000 382 10F10 l TITLE (4)
Reactor Trip Caused By Failure of FWCS Feed Flow Square Root Extractor l
EVENT DATE (5) LER NUMBER (6i REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) seoUrN :AL REysow ' AW" N^* N TWM*R MONfH car YEAR YEAR ' " ^ ^"
UMBEA NUMdER 05000 N/A l F ACJUTY NAMf; Doc s NUugtg
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06 15 93 93 002 00 07 15 93 N/A 05000
[~ OPERATING THis REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 1: (Check one or more) (11) l MODE (9) 1 20 402(b) 20.405(c) X 50.73(a)(2)(sv) 73.71 tb)
POWER. 20 405(a)(1)(i) 50 36(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVEL (10) 100 20 405ia)(1)(a, 50.36(c)(2) 50.73(a)(2)(vn) OTHER 20 405Uu(1)(ni) 50 73(a)(2)(i) 50 73(al(2)(vni)(A) I6MW '" ^**d 20 405talt1)0v) 50.73(all2)(u) 50.73(a)(2)(vin)(B) 3NA 20 405(aH1)(v) 50.73(a)(2)(sii) 50.73(a)(2)(x) .
LICENSEE CONTACT FOR THIS LER (12)
NAvt. TutPMONL NUWLH pnduce Ama Loom D.W. Vinci, Operations Superintendent (504) 464-3178 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER CAULE SYSTE V COMPONENT MANUFACTURER gg ,
X JB LC D142 Y SUPPLEMENTAL REPORT EXPECTED (14) EXPECTEo M N'M DA' ^^R Yrs SUBMISSION pt ps wmpice EXPECTED SUBM!SSION DATO no X DATE (15)
ABSTRACT (Limit to 1400 spaces, i e., approximately 15 single-spaced typewritten lines) (16)
On June 15, 1993, at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br />, Waterford 3 was operating in Mode 1 at 100%
power when the reactor tripped due to a high Steam Generator level caused by the failure of the Feedwater Control System (FWCS).
The root cause of this event was the failure of the square root extractor in the feedwater flow circuit for FWCS #1. The failure caused calculated feedwater flow to drop to zero and generated a high demand signal from FWCS #1 which, in turn, caused the #1 Feedwater Regulating Valve to go fully open and overfeed the #1 steam generator.
Corrective action for this event includes, in part, replacement and analysis of failed components, review of alarm set points (two expected alarms were not received during the event), operator training, and reevaluation of Feedwater Control System troubleshooting practices. This event posed no risk to the health and safety of the general public or plant personnel. Similar events include LER's85-041, 87-008,89-013, and 91-013.
NHC FDHM 306 (5 921
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NUMBER NUVBER Waterford Steam Electric Station 05000 382 02 OF 10 Unit 3 93 002 00 i TLnT pr more space a re,1wrea. use eamriones copses of NHC form tbtVy (17)
REPORTABLE OCCURRENCE On June 15, 1993, at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br />, Waterford 3 was operating in Mode 1 at 100%
power when the reactor (EIIS Identifier AB) tripped due to a high level in Steam Generator (SG) #1. The high steam generator level was caused by the failure of the Feedwater Control System (FWCS; EIIS Identifier JB).
The reactor trip was reported to the NRC via the Emergency Notification System as required by 10CFR50.72(b)(2)(ii). As an unplanned actuation of the Reactor Protection System (RPS; EIIS Identifier JC), this event is reportable as an LER in accordance with 10CFR50.73(a)(2)(iv).
INITIAL CONDITIONS Plant Power 100%
Plant Operating Mode Made 1: Power Operation Procedures Being Performed Specific None to this Event Technical Specification LCO's in None Effect Specific to this Event Major Equipment Out of Service None Specific to this Event t
EVENT SEQUENCE At approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on June 15,1993, an INP0 evaluator informed the Control Room staff that Main Feedwater Regulating Valve (MFRV; EIIS Identifier JB-FCV) #1 was slowly oscillating over a range of approximately 1 to 1.5 inches. The operators observed the FWCS #1 master controller output oscillating between 60% and 80% and notified I&C Maintenance personnel of the ;
condition.
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03 OF 10 Unit 3 93 002 00 ux1m m.,...,w.a .==.. ,e e am on i
Upon arriving in the Control Room, an I&C foreman requested that the Control t
Room Supervisor (CRS) place the FWCS #1 master controller in manual for troubleshooting purposes. After discussing the troubleshooting process with the 1&C Supervisor and noting that SG #1 level and feedwater flow were very steady, the CRS and the I&C foreman agreed that additional data could be obtained from the FWCS cabinet prior to placing the controller in manual.
In the course of checking the #1 FWCS Main Valve Position Signal (MVPS), the i signal was seen to increase to 10 VDC, indicating that the #1 MFRV was receiving a signal to fully open. The I&C foreman confirmed that the #1 main feedwater regulating valve was fully open and informed the Control Room staff.
The operators confirmed the MFRV position and observed one Steam Generator (SG) #1 level indicator rising and the other steady at 66% level. Also, the Steam /Feedwater Flow Signal Deviation annunciator was not in alarm. This alarm is computer driven and annunciates at a preset deviation between the ,
Main Steam flow and the associated feedwater flow. The operators confirmed the rising level in #1 SG, placed the #1 MFRV controller in manual, and started to close the valve when the reactor tripped on high SG level.
When the reactor tripped at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br />, operators performed the immediate i actions for a reactor trip in accordance with Emergency Operating Procedure OP-902-000, " Emergency Entry Procedure."
At 1612 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.13366e-4 months <br />, operators entered Emergency Operating Procedure (E0P) OP-902-005, " Loss of Offsite Power," due to the loss of one of the four non-safety !
busses. When the generator tripped following the reactor trip, one of the busses failed to automatically transfer from the Unit Auxiliary Transformer '
(UAT: EIIS Identifier EA) to the Startup Transformer (SUT; Ells Identifier EA) because of a failed fuse in the voltage sensing circuit for the synch check relay. The failed fuse prevented the synch check relay from confirming that RCronvaiu s e
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SEQulNT A Fh510N NUMBER NUMBER Waterford Steam Electric Station 05000 382 ,,
04 0F 10 Unit 3 93 002 00
,ex, in m av.;. 1.ww. .mw. cv.w un w m o n the output voltage for the associated SUT and the bus were in sync and prevented the automatic bus transfer. The failed fuse was identified just prior to the reactor trip by electricians who were in the process of troubleshooting a related problem. A manual transfer was performed and the bus was re-energized at 1716 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.52938e-4 months <br />.
The reactor trip recovery process was complicated somewhat when the #1 Temperature Control Valve (TCV) did not close when the Moisture Separator Reheater (MSR; ElIS Identifier SB) heater controls were reset following the trip, thus creating the potential for excessive reactor cooldown. In accordance with OP-902-000, operators made several (unsuccessful) attempts to remotely close or isolate the TCV. The valve was closed manually by an operator at 1610.
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Unit 3 93 00 ^-
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CONSEQUENCES
~
Metering fuse blows No signal to synch ;
1400 check relay; automatic bus transfer disabled 1500 Control Room Caused by blown metering lu1tiate personnel notice 7KV fuse troubleshooting MW-hour reading low.
1530 Control Room informed Signal swing about 20% Initiate of MFRV oscillation troubleshooting 1540 CRS opts to maintain No apparent need for When control system 1550 SG #1 master immediate transfer, failed, MFRV #1 went controller in fully open automatic
~
1&C taking readings MVPS increased to 10 VDr. MFRV #1 is fully 1603 on FWCS al open. Control Rm staff notified 1604 Operator notes Operator questions conflicting SG #1 level indication /
level indication: delays corrective red pen rising / green action pen steady 1604 Operator confirms Delays placement of rising level in SG #1 master controller to manual 1604 MFRV #1 controller At this time SG #1 is Reactor trip ,
placed in manual and already overfed and 1 close closing valve does not !
stop level rise 1604 Reactor Trip Tripped on High SG #1 level NRC FCWlV 366A (S 92)
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NUMBER NUMBER Waterford Steam Electric Station 05000 382 ~ ~
06 OF 10 Unit 3 93 002 00 1m,,, J.c.,,- ... ~ -,aw<cu, - ,on 6
1604 Turbine trip / Electrical supply to 1 With loss of metering Generator trip and 2 busses should fuse, no voltage transfer from UAT to SVT sensed by synch check relay, 3Al bus does not transfer 1604 3Al bus does not Loss of RCPs IA and transfer 2A; loss of Circ Water pumps A & C; , ,
loss of Condensate Pumps A&C MSR TCV #1 does not Can result in close when MSRs reset excessive cooldown rate 1610 Operator manually Cooldown rate closes TCV #1 stabilized 1617 Enter OP-902-005 Loss of Offsite Power entered due to loss of i 3Al bus 1716 Energized 3Al bus Manual transfer 1730 Exit OP-902-005, Exit Emergency Operating enter OP-10-001 procedures, enter normal operations CAUSAL FACTORS The root cause of this event was equipment failure, specifically, the intermittent failure of the square root extractor in the feedwater flow circuit for FWCS #1. This caused calculated feedwater flow to drop to zero 1
and generated a high demand signal from FWCS #1. This in turn caused the FWRV
- 1 to go fully open and overfeed the #1 steam generator. Suspect components were replaced and subjected to further analysis and troubleshooting. The Feedwater Flow Square Root Extractor failed completely during subsequent testing but the actual cause of the failure was not determined. The modules were sent to the vendor and indications are that a transistor failed in an amplifier in the square root extractor module.
NRC FORM 36BA (S 92)
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, som esos NUMBER NUMBER OF Waterford Steam Electric Station 05000 382 ~ ~
07 10 Unit 3 93 002 00
,m nw. u c. a v.a . .x.~. ce.w ~nc F- *w o n A number of contributing causes of this event have been identified:
First, equipment anomalies may have caused a delay in the operator's analysis tf the situation. The pen for one of the steam generator level indications stuck and required the operator to confirm the rising steam generator level by checking redundant indications. Also, two alarms, the #1 SG Steam /Feedwater Flow Signal Deviation alarm and the #1 SG Level HI/LO alarm did not annunciate.
In hindsight, more timely manual operator action may have mitigated the event.
Sufficient indication was available to justify placing the #l FWRV master controller in manual immediately upon noticing that the valve was fully open.
Finally, equipment failure resulted in the failure of one of the non-safety busses to transfer from the Unit Auxiliary to the Startup transformer. The failed fuse in the metering circuit for bus Al voltage removed the voltage signal to the sync check relay and prevented the automatic bus transfer.
NON-CAUSAL FACTORS The failure of the TCV #1 to close was identified as a non-causal factor. The cause of this failure has not been determined.
i NRC FORM 3664 (5-02#
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (S s2L EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COM*LY W.TH TH LICENSEE EVENT REPORT (LER) Ela v *TTnEs *$$Nls Ril$ICEDOP5E7's's TEXT CONTINUATION 1"E'cI,^"$'5"'w!Z"yMy"""
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080 ' M Unit 3 93 002 00 u n m .u.c.ar. w .a. .. m .<.c.o .r wcr.,,,x m on ACTIONS TO PREVENT RECURRENCE To address the root cause, failed components in the FWCS were replaced and i sent to the vendor for analysis. Because the vendor's analysis identified a failed transistor in the square root extractor module, Waterford 3 will evaluate the need for periodic replacement of these modules in the FWCS and the Steam Bypass Control System.
Second, Feedwater Control System troubleshooting practices will be reevaluated in light of this event. Specifically, it may be appropriate to place the Main Feedwater controllers in manual prior to manipulating the Feedwater Control System digital displays for troubleshooting purposes, i Waterford 3 will take a number of actions to address the contributing causes of this event:
- 1. With regard to control room indications, the SG #1 level indications have been repaired. Neither the Steam /Feedwater flow deviation alarm nor the high steam generator level alarms annunciated as expected during this event, possibly as a result of less than optimal set points. These conlitions will be examined and corrective actions taken as appropriate.
- 2. The performance of the Steam /Feedwater flow deviation alarm in the Waterford 3 Control Room simulator will be validated against actual I plant performance.
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- 3. This event will be reviewed with all Operations Department personnel.
The review will emphasize philosophy and decision making concerning when direct observation of control board parameters is appropriate, when controllers should be placed in manual, and finally, when the reactor should be manually tripped.
NRC FORM 36EA (S-92) j
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NUVBER NUMBER UF Waterford Steam Electric Station 05000 382 ~
09 10 Unit 3 93 002 ~ 00 s u,1a mn v.c. ,, ,.v..a. .a. .aan ees mc w nw ts n 4 Waterford 3 will review and update the FWCS lesson plan to insure that the plan includes appropriate detail regarding interfaces between Process Analog Control (PAC), the FWCS, the Plant Monitoring Computer, and control board indications.
- 5. The failed metering fuse was sent to the vendor for analysis. Waterford 3 will take appropriate corrective action pending the results of the analysis.
The corrective actions described above will be complete by November 17. 1993.
Finally, the cause of the problem with the TCV #1 valve will be investigated i and corrective action taken as appropriate.
SAFETY SIGNIFICANCE Because the Reactor Protection System generated a reactor trip as required for the high steam generator level condition, this event posed no risk to the +
health and safety of the general public or plant personnel.
SIMILAR OCCURRENCES LER 85-041 reported a reactor trip that occurred due to low level in Steam Generator #2. The level deviation was caused by the failure of the steam flow ,
square root extractor in FWCS #2. The cause of the square root extractor failure could not be determined and the module was replaced. LER 87-008 reported a reactor trip that occurred due to a high level in SG #1. Although troubleshooting did not conclusively identify the cause of the trip, the feedwater flow square root extractor was replaced to eliminate one possible cause of the FWCS failure. Subsequent testing of the suspect square root extractor did not identify any problems.
NEC FORM Sf44 (5 92)
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YEAR NUMBER NUVDER OF Waterford Steam Electric Station 05000 382 ~ ~
10 10 Unit 3 93 002 00 TEXT pr mee mece a weered. me codeurs cornes o' ArRC form J6fAi (17)
LER's89-013 and 91-013 reported reactor trips that occurred as a result of steam generator level abnormalities. Failed PAC cards in the FWCS caused both trips.
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