05000483/LER-1988-001, :on 880104,reactor Tripped on Low Steam Generator Level Oscillations During Troubleshooting of Faulty Amber Light Condition for Main Feedwater Isolation Valve.Caused by Blown Fuse.Fuse Replaced

:on 880104,reactor Tripped on Low Steam Generator Level Oscillations During Troubleshooting of Faulty Amber Light Condition for Main Feedwater Isolation Valve.Caused by Blown Fuse.Fuse Replaced

ML20148R276
Person / Time
Site:	Callaway
Issue date:	02/03/1988
From:	Blosser J, Hogg J UNION ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-001, LER-88-1, ULNRC-1714, NUDOCS 8802020137
Download: ML20148R276 (6)

LER-1988-001, on 880104,reactor Tripped on Low Steam Generator Level Oscillations During Troubleshooting of Faulty Amber Light Condition for Main Feedwater Isolation Valve.Caused by Blown Fuse.Fuse Replaced

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
4831988001R00 - NRC Website

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1887a ACT riet 9e 7dM weces a e.sa-s e *e's e * *te.a s+g a were re pe..rvea t =ess MS.

On 1/4/88 at 0236 CST, a Reactor Trip occurred as a result of low level in Steam Generator (S/G)

'A'.

The plant was in Mode 1 - Power Operations, at 100 percent reactor power.

The Reactor Coolant System (RCS) tenperature was 589'F (average). RCS pressure was 2234 psig.

The low S/G 1evel occurred during the troubleshooting of the S/G

'A' main feedwater isolation valve (Fk'IV), AE-FV-0039, amber light condition on the Engineering Safety Features (ESP) Status Panel SA066X.

k'hile trouble-shooting the indication circuit for the accumulator pressure switch.

AE-PSL-0039A, the control voltage for AE-FV-0039 was shorted by Instrumentation and Centrol (I&C) technicians causing a blevn fuse. The blown fuse resulted in valve AE-FV-0039 fast closing.

This was followed by flow misnatch on all four steam generators, with an accompanying reactor trip on S/G lo-lo level in S/G 'A' at 0236. The operators recovered from the trip via plant procedures. All of the available wiring details of the circuit were not used.

Technicians replaced the blown fuse and satisfactorily completed the troubleshooting. To prevent recurrence, I&C technicians have been instructed to review design drawings before troubleshooting.

Additional training will be given to I&C technicians on the SA066 cabinet power distribution.

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y e,RC Penn 3044 U 8. NUCLt?/A KE1UL& TORY COMMtssiO4 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION amovio ove so vio-eto.

EXP1RES 8'31/86 f ACitiTY NAa,E (11 DOCKlf NUwetR ul LER NUMSIR 167 PAGE(3) u %.u.6

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Callaway Plant Unit 1 o l5 l0 lo j o l 4l813 81 8 0l 0l1 0 10 01 2 0F Ol4 mn,

.w w ect mst.nm Banis For Reportability On1/4/88at0236 CST,aReactorProtectionSystem(RPS)gactortrip occurred due to the water level in Steam Generator (S/C)

'A' decreasing to the lo-lo level trip setpoint.

This Licensee Event Report is submitted pursuant to 10CFR50.73(a)(2)(iv) to report the automatic actuation of the RPS.

Conditions at Time of Event Mode 1 - Power Operations Reactor Power - 100%

Reactor Coolant System (RCS)( ) - temperat ure (average) - 589'T pressure - 2234 psig Description of Events On 1/4/88, Instrumentation and Control (I&C) Generic Work Request (VR)

G428997 wasissuedtoI&Ctechnicgstotroubleshootandrepairthe Engineering Safety Features (ESP)

StatusPglaccumulatorpressurealarm for the main feedwater isolation valve (FWIV) forS/G'A',AE-FVg39.

The ESF Status Panel, SA066X, is located o accunulatorpressureswitch,AE-PSL-0039A,gheMainControlBoard.

The for valve AE-FV-0039 was tested and found to be within calibration accuracy the previous day. The I&C technicians determined that the problem was in either the logic or relay card in ESF Status Panel SA066A.

An amber 1ight was illuminating for valve AE-FV-0039, which did not coincide with the actual accumulator pressure. The Beta System technical manual (E-094-0063) was used to determine that a jumper could be used to simulate AE-PSL-0039A switch actuation. Drawing #301474, Sheet 13 of 18. showed the AE-FV-0039 inputs to the Beta System to be on Terminal Block 14, terminals 12 and 13.

While troubleshooting AE-PSL-0039A indication in SA066A, a jumper was placed across terminals 12 and 13 on Terminal Block 14 to simulate a closed switch for AE-PSL-0039A. This blew 4' fuse in the adjacent Main Steam Feedwater Isolation System (MSFIS) cabinet resulting in the fast closing of valve AE-FV-0039.

This was followed by a flow mismatch on all four stean generators with an accompanying reactor trip on stean generator lo-lo level in S/G 'A'.

Immediate Actions Taken The licensed orarators recovered fron the reactor trip via plant procedures E0 and ESO l.

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NRC Perm 306A U S kUCLf u G.tiUL(. TORY COUMt$SION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ursovio ove No. mo-oio4 EXP1RES: 8 31.88 P ActLITY NAME Hi DOCKET NUustR t4i Lin NUustR18)

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l'A*.D Callaway Plant Unit 1 o l5 l 0 j o l 0 }4 l 8 l3 8l8 0 l 0l 1 0l0 013 OF 0 l4 tot sa a w ww.m,we re ass 4w Hn Root Cause l

The I&C technicians involved in the troubleshooting of the abnormal indication for AE-FV-0039 on SA066X, failed to obtain and use all of the available wiring details of the AE-PSL-0039A circuit prior to l

troubleshooting.

Contributing factors to this event were:

(1) The decision to jumper terminals 12 & 13 on Terminal Block 14 was based on their past field experience, review of the ESF status panel Tech Manual, and assumptions that they could not cause any actuations while working on plant status board indication.

The technicians failed to verify their assumptions by review of the E-23AE16 drawing prior to taking action.

(2) The design of the ESF Status Panel indication does not protect the FWIV control circuit from a short or ground fault in the indication circuit.

Corrective Actions and Actions to Prevent Recurrence (1)

I&C technicians replaced the blevn fuse and completed troubleshooting the amber light condition on the ESF status panel. Valve AE-FV-0039 found to be due to a defective relay card (RC-7)( }

light conditio inBetapanel.ggyasThe defective relay card was replaced. The plant was returned to power operations at 0237 on January 5, 1988.

(2) A Request for Resolution (RFR) was written to evaluate isolating the ESF Actuation System status panel indications from the control circuitry I

with additional fuses.

I (3) Technicians involved in the troubleshooting have been counseled for their failure to obtain and use the appropriate wiring details of the circuit for AE-PSL-0039A prior to troubleshooting.

(4)

I&C personnel have been instructed that before troubleshooting, all activities should be verified by a review of the appropriate design I

info rmat ion. Additional training is being given to I&C technicians on O

SA066 cabinets power distribution.

Safety Significance

The safety features included in the plant design performed as required in response to the low S/G 1evel and no detrimental ef fects on plant equipment were noted, i

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NRC Pere 3BSA U $ NUCLE AA KtOULATORY COMMIS$loM LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Anaovto ous wo. mo-oios EXPIRES. S 31,8B PactLITY Naut (1)

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'Pa "R!MP 07*,72 Callaway Plant Unit 1 0 [5 l 0 l 0 l o 14 i 813 81 8 Ol0 l 1 Ol 0 01 4 OF 0 l4 TWIT L ampe geese 4 mensbet ses sawtoner 4AC Are JE4'st (1M Previous Occu_rrences None Footnotes The system and component codes listed below are from IEEE Standards 805-1983 and 803A-1983, respectively.

(1)

System - AB, Component - SG (2) System - AB (3) System - JE (4) System - AE, Component - ISV (5) System - AE, Component - PSL (6) System - RL (7) System - AB, Component - CAB (8)

System - RP, Component - RLY (9)

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0NION E1xcruic s

Catway M January 27, 1988 U. S. Nuclear Regulatory Connission Document Control Desk Washington, DC 20555 ULNRC-1714 Gentlemen:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 88-001-00 REACTOR TRIP ON LOW STEAM GENERATOR LEVEL OSCILLATIONS DURING TROUBLESHOOTING OF A FAULTY AMBER LIGHT CONDITION FOR MAIN FEEDWATER ISOLATION VALVE The enclosed Licensee Event Report is submitted pursuant to 10 CFR 50.73(a)(2)(iv) concerning an unplanned reactor trip on low Steam Generator level. The icw level was due to the fast closing of a Main Feedwater Isolation Valve initiated by a blown fuse during troubleshcoting.

J. D. Blosser Manager, Callaway Plant ds TPS / LAM:jlh Enclosure ec: Distribution attached f[Y Mary A: West PO Bax 620 Fatn MO 65251

4 cc distribution for ULNRC-1714 Mr. A. Bert Davis Mr. Thomas Alexion (2 copies)

Regional Administrator Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Region III 7920 Norfolk Avenue 799 Roosevelt Road Mail Stop P-316 Clen Ellyn, IL 60137 Bethesda, MD 20014 American Nuclear Insurers Mr. O. Maynard c/o Dottie Sherman, Library Wolf Creek Nuclear Operating Corp.

The Exchange Suite 245 P. O. Box 411 270 Farmington Avenue Burlington, KS 66839 Farnington, CT 06032 Mr. Merlin Williams Manager, Electric Departnent Supt. of Regulatory Quality &

Missouri Public Service Commission Administrative Services P. O. Box 360 Wolf Creek Nuclear Operating Corp.

Jefferson City, MO 65102 P. O. Box 411 Burlington, KS 66839 Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, CA 30339 NRC Resident Inspector D. F. Schnell (400)

R. J. Schukai (470)

C. L. Randolph J. F. McLaughlin T. P. Sharkey (Z40LER)

(240LER) (w/c)

W. R. Campbell R. P. Wendling (470)

F. D. Field (480)

A. P. Neuhalfen A. C. Passwater/D. E. Shafer/D. J. Walker (470)

G. A. Hughes Zl70.03 (QA Record)

M. S. Evans J. F. Hogg M. E. Taylor H. Wuertenbaccher, Jr. (100)

S. L. Auston (470)(NSRB) j S. J. Bellers/J. D. Schnack JDB Chrono 3456-0021.6 3456-0260 Z40ULNRC A160.761 N. Date (Sandra Auston) (470) i