05000483/LER-1984-056, Forwards LER 84-056-00

Forwards LER 84-056-00

ML20100P256
Person / Time
Site:	Callaway
Issue date:	11/20/1984
From:	Miltenberger S UNION ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
ULNRC-981, NUDOCS 8412140086
Download: ML20100P256 (4)

LER-2084-056, Forwards LER 84-056-00

Event date:
Report date:
4832084056R00 - NRC Website

text

'

UNION EtscTaic COMPANY CALLAWAY PLANT MAILING ADDRESS:

P. O. BOX 620 FULTON. MOe 65251 November 20, 1984 U. S. Nuclear Regulatory Commission Document Control Desk Wushington, DC 20555 ULNR;-981 DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 84-056-00 INADVERTENT ENGINEERED SAFETY FEATURES ACTUATIOv9 Gentlemen:

The enclosed Licensee Event Report is submitted pursuant to 10 CFR 50.73(a)(2)(iv) concerning inadvertent Engineered Safety Features actuations.

-yb e ^:

l y

S. E. Miltenberger f-j j f Manager, Callaway Plant MET /WRR/JWK/drs Enclosure cc: Distribution attached oo g Sad 234,g868411Mg S

ys ts il s

. = .~ - . . -- . - . -- ~ -

L. - z . - -. -:

i cc distribution for ULNRC-981 Mr. James G. Keppler Regiona1' Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission

Region III 799 Roosevelt Road Glen Ellyn, IL 60137

) American Nuclear-Insurers c/o Dottie Sherman,. Library The.Exchange Suite 245 270 Farmington Aveune Farmington, CT 06032 i Records Center Institute of Nuclear Power _ Operations y Suite 500 1100 ' i cele 75. Parkway

^

Atlan.1, GA 30339 NRC Resident Inspector Missouri-Public Service Commission 4 ' D. F.-Schnell

! J. F. McLaughlin J. E. Davis (Z40LER)

D. W. Capone /R. P. Wendling F. D. Field R. L. Powers A. C. Passwater/D. E. Shafer/D. J. Walker-G. A. Hughes

-W. R. Robinson (QA Record)

M. E. Taylor J. M. Price i

R. A.~ McAleenan L. K. Robertson (470)(NSRB)

Merlin Williams, Wolf Creek SEM Chrono 3456-0021.6 3456-0260 Z40ULNRC 2 G56.37 N. Date t

IE22 n

lll

e - i esac pen. Jesa y.3, seuCLEAR REGULATORY Con.nnessose LICENSEE EVENT REPORT (LER) TEXT CONTINUATION an.aovsooueao uso-oio.

iman ama PACJufv seasse tu DoCati seuessG A 123 Lan asunseen sea Pae813 vsan  : saowsmrin L -'

m eso=

Callaway Plast Unit 1 o l5 lo j o lo l 4l 8l3 8l4 -.

0 l5 l6 --

0l0 Og2 oF 013 rixru . ee asaruim At 0513 CDT on 10/22/84 and 1527 on 10/23/84, Engineered Safety Features (ESF) were actuated with Reactor Trips occurring shortly thereafter.

High/ low steam generator (S/G) levels obtained while rolling the main turbine initiated the Feedwater Isolations (FWIS), Auxiliary Feedwater Actuations (AFAS), S/G Blowdown Isolations (SGBDIS), and Reactor Trips.

The ESF equipment performed as designed in both cases.

1. At 0054 on 10/22/84 while in Mode 1, the main turbine was rolling at 1800 r.p.m. and the reactor was at a power level of

.approximately 9.5%. At 0132 the operators began increasing Reactor Power to 15%. While waiting to synchronize to the grid, the turbine exhaust hood temperatures and the turbine vibration were increasing. At 0501 the operator was instructed to select "close valves" to shutdown the turbine. Immediately after he selected "close valves" the turbine tripped from high exhaust hood temperatu e.

The operators began reducing Reactor Power and at 0509 broke the condenser vacuum to slow the turbine. The start of both motor-driven Auxiliary Feedwater Pumps caused level variations in the S/Gs and at 0513 a high level in S/G "B" initiated a FWIS, AFAS, and SGBDIS. Reactor Power had been reduced to 4.2%

and Mode 2 had been entered when these actuations occurred.

At 0521, the reactor tripped due to a low S/G "D" level.

Reactor Power had been further reduced to 3.5% when the trip occurred. Emergency Operating Procedures E-0, Reactor Trip or Safety Injection, and ES-0.1, Reactor Trip Recovery, were performed and the plant stabilized. The FWIS was reset to restore feed from the condeneer. While recovering from the incident, a second Reactor Trip signal and FWIS was received at 0553 due to a low level in S/G "D."

2. At 1510 on 10/23/84 while in Mode 1, the reactor was at approximately 15% power and the operators were in the process of rolling the main turbine. At approximately 400 r.p.m.,

increasing, the Condenser Available Interlock (C-9) for the steam dump valves began to cycle on and off causing the steam l dump valves to cycle.

When steam was dumped a C-9 signal was initiated and the steam dumps closed. As sufficient vacuum was regained, thus clearing the C-9 interlock, the steam dumps reopened.

Continued steam dump cycling caused level oscillations in the S/Gs.

I -

..g,,...

3A' T Oft? lb O I X- )

u << - -

7 o

• 6 mac Form 3Bea U.S. muCLEAR RteuLATORY CC LICENSEE EVENT REPORT (LER) TEXT CONTINUATION areaoveo owe no siso-.oios EXPtRES. 4/3iit$

paCatsfy maasE tu 00CEST muassen t33 ggg ,,y,,ggg ,g, paes W

..a. > * * = , *, ' E cf.;;

Callaway Plant Unit 1 0151010 lo l 41813 8I4 -

0 15 l 6 -

010 0l1 0F 011 4 - ame w an wim rixt in -

At 1527 a S/G "B" high level initiated a FWIS, AFAS, and SGBDIS. The main turbine, which was at 1400 r.p.m., also tripped. At 1531, the reactor tripped on a low S/G "C" level caused by the drop in feedwater temperature when the FWIS and AFAS occurred. The operators performed Emergency Operating Procedures E-0 and ES-0.1 and stabilized the plant.

The high exhaust hood temperature which caused the Turbine Trip on 10/22/84 was due to running the main turbine unloaded for an excessive period of time. To prevent recurrence of this incident, a precaution regarding running the main turbine unloaded for longer than one hour was added to Normal Operat.ing Procedure OTN-AC-00001, Main Turbine and Generator Systems, on 10/31/84.

The problem experienced with steam dump cycling on 10/23/84 has been corrected by rolling the main turbine up to speed at 5 to 10% Reactor Power rather than 15%, thus reducing the amount of steam being dumped to the condenser. General Operating Procedure OTG-ZZ-00003, Plant Startup Less Than or Equal to 5% to 20% Power, was revised on 11/5/84 to implement this corrective action. No further corrective action for either incident is deemed necessary.

There was no damage to plant equipment or release of radioactivity as a result of these incidents. At no time did these events pose a threat to the public health or safety.

Previous occurrences: none

m. PO.W Stea