ML20211K821

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Special Rept:On 860521,valid Failure Occurred on Div 2 Diesel Generator During Performance of Tech Spec Surveillance 4.8.1.1.2.Caused by Failure of Jacket Water Thermostatic Control Valve to Open
ML20211K821
Person / Time
Site: Perry, 05000000
Issue date: 06/18/1986
From: Edelman M
CLEVELAND ELECTRIC ILLUMINATING CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20211K815 List:
References
PY-CEI-OIE-0213, PY-CEI-OIE-213, NUDOCS 8606300277
Download: ML20211K821 (2)


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YL THE CLEVEL AND ELECTRIC ILLUMIN ATING COMP ANY ILLUMINATING BLDG - 55 PUBLICSQUARE P O Box 5000 - CLEVELAND. Ohio 44101 - TELEPitONE (216) 622-9600 Serving The Best Location in the Nation IIIIIY ~ ~"I MURRAY R. EDELMAN

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&.g Nucuan June 18, 1986 PY-CE1/01E-0213 L

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FILE 7[e v" Mr. James G. Keppler Director, Region 111 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Glen Ellyn, IL 60137 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Special Report - Valid Test Failure Division 2 Diesel Generator

Dear Mr. Keppler:

Attached is a Speciel Report concerning a valid test failure of the Division 2 diesel generator. This report satisfies the conditions of Technical Specifications 4.8.1.1.2 and 6.9.2.

Please feel free to contact me should you have any further questions.

Very trul s,

Murray R. Edelman Senior Vice President Nuclear Group MRE:nje Attachment cc:

Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Com:nission Washington, D.C.

20555 Jay Silberg, Esq.

John Stefano (2)

J. Grobe 8606300277 060625 PDR ADOCK 05000440 PDR o 3 39-3 S

I Attc hnert PY-CEI/01E-0213 L PN i

SPECIAL REPORT DIVISION 2 DIESEL GENERATOR VALID FAILURE On May 21, 1986 a valid failure occurred on the Division 2 Diesel Generator while performing Technical Specification Surveillance 4.8.1.1.2.

This is the first valid failure to occur on the Perry Unit 1, Division 2 Diesel Generator.

As of May 21, 1986, the Division 2 Diesel Generator had undergone three valid tests, including this one valid failure.

The failure occurred while the Division 2 Diesel Generator was running in the fully loaded condition.

During the surveillance test, the jacket water thermostatic control valve failed to open and provide proper cooling for the Division 2 Diesel Generator.

Fifteen minutes into the test, the following alarms were received: 1) trip bearing temperature high - valid 2) trip jacket water temperature high - spurious, apparently due to interaction with faulty vibration sensor; 3) trip vibration high - invalid, due to defective sensor.

The Division 2 Diesel Generator did not trip automatically, and had to be shutdown manually. To correct these malfunctions the following components were replaced: 1) jacket water thermostatic control valve - f ailed component; 2) bearing temperature trip sensor - fusible link activated 3) vibration trip sensor - defective sensor; 4) and the shutdown logic control board - an apparently defective component which is still under investigative testing. The Division 2 Diesel Generator was restarted and verified operable by performing the Division 2 Diesel Generator Start and Load Surveillance tests. The Division 2 Diesel Generator was declared inoperable on May 21, 1986 at 2059 and was subsequently declared operable on May 30, 1986 at 2239 for a total out of service time of 9 days, I hour and 40 minutes.

The surveillance testing interval will remain at once every 31 days, which is in accordance with Technical Specification Table 4.8.1.1.2-1.

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b en UNFA RECMC CQwNW April 15, 1986

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gp[.) J [.T h {'C Mr. James G. Keppler j-L-

Regional Administrator

] _j Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission L_

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Region III Thg 799 Roosevelt Road

. Glen Ellyn, IL 60137 ULNRC-1294

Dear Mr. Keppler:

DOCKET NUMBER 50-483 CALLAk'AY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SPECIAL REPORT 86-01 REVISION 1 DIESEL GENERATOR FAILURE DURING AN INVALID TEST The enclosed revision to Special Report 86-01 (March 31, 1986, ULNRC-1280) is submitted to provide clarification of the events which occurred as a result of a diesel Fenerator output breaker plunger bolt being out of adjusteent.

d G. L. Randol h Manager, Callaway Plant f$ bin k)EY/TPS/WK/dra Enclosure cc: Distribution attached

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cc distribution for ULNRC-1294 Mr. James G. Keppler Manager, Electric Department Regional Administrator Missouri Public Service Commission Office of Inspection & Enforcement P. O. Box 360 U.S. Nuclear Regulatory Commission Jefferson City, MO 65102 j

t Region III 799 Roosevelt Road Mr. O. Maynard Glen Ellyn, IL 60137 Kansas Gas and Electric Company P. O. Box 208 American Nuclear Insurers Wichita, KS 62701 c/o Dottie Sherman, Library The Exchange Suite 245 Records Center 270 Farmington Avenue Institute of Nuclear Power Operations Farmington, CT 06032 Suite 1500 1100 Circle 75 Parkway Mr. J. H. Smith Atlanta, GA 303?9 Bechtel Power Corporation SNUPPS Project Mr. Paul O'Connor 15740 Shady Grove Road Office of Nuclear Reactor Regulation Gaithersburg, MD 20877-1454 U. S. Nuclear Regulatory Commission Mail Stop P-316 Mr. Nicholas A. Petrick 7920 Norfolk Avenue Executive Director, SNUPPS Bethesda, MD 20014 5 Choke Cherry Road Rockville, MD 20850 Mr. Merlin Williams Supt. of Regulatory Quality &

NRC Resident Inspector Administrative Services D. F. Schnell (400)

Kansas Gas and Electric Company R. J. Schukai (470)

P. O. Box 309 S. E. Miltenberger Burlington, KS 66839 J. F. McLaughlin J. E. Davis (240LER)

(Z40LER) (w/c)

D. W. Capone /R. P. Wendling (470)

F. D. Field (470)

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

G. A. Hughes Z40.01 (QA Record)

J. M. Price D. E. Young M. E. Taylor H. Wuertenbaecher, Jr. (100)

S. L. Auston (470)(NSRB)

J. D. Schnack GLR Chrono 3456-0021.6 3456-0260 240ULNRC G56.37 N. Date (Sandra Auston) (470)

's SPECIAL REPORT 86-01 REVISION 1 DIESEL GENERATOR FAILURE DURING AN INVALID TEST Surveillance Procedure ISP-SA-2413A, Diesel Generator and Sequencer Testing (Train A), was in progress on 3/6/86 to satisfy various 18 month Technical Specification (T/S) surveillance requirements. The plant had entered Mode 5, Cold Shutdown, on 3/4/86. During performance of the

"' A' Train Blackout Without SIS (Safety Injection Signal)" portion of ISP-SA-2413A, the 'A' emergency diesel generator (D/G) was intentionally secured without loading to at least 50% of continuous rating. The D/G was secured to investigate a failure of the load sequencer to properly sequence the required emergency loads onto the 4.16 kV safety-related bus (NB01) energized by 'A' D/G.

Since the successful D/G start was terminated intentionally without loading to at least 50% of continuous rating, it is not considered a valid test or failure in accordance with Regulatory Position C.2.e(4) of Regulatory Guide 1.108, Revision 1, August 1977. The D/G testing frequency established by T/S Table 4.8-1 is therefore not affected by this incident and this Special Report is being submitted as required for all D/G failures, valid or nonvalid, per T/S 4.8.1.1.3.

It is noted that the D/G could have been manually loaded and a valid test completed had the operators not intentionally secured the D/G for troubleshooting of the load sequencer.

Starts of the D/G's have been tracked since the completion of Preoperational Testing on 5/11/84.

The starting history of the D/G's as of the date of this report is summarized as follows:

Number of Number of Number of Failures During Failures During D/G Valid Tests Valid Tests Invalid Tests h

31 1*

5#

B 27 0

15

  • Reference Special Report 84-02.
  1. Reference Special Reports 85-01, 85-02, 85-07, and 86-01.

$ Reference Special Report 85-05.

The following is a summary of the events applicable to this incident.

The "'A' Train Blackout Without SIS" portion of ISP-SA-2413A began at approximately 2018 on 3/6/86.

Loads shed off bus NB01 as required when the test signal (blackout without SIS) was initiated.

'A' D/G successfully started and attained the required voltage and frequency.

.i SPECIAL REPORT 86-01 K2 VISION 1 Page 2

'A' D/G output breaker closed.

Only 'A' Centrifugal Charging Pump and 'A' Component Cooling Water Pump sequenced onto bus NB01 and were powered by the 'A' D/G.

Testing activities were halted and troubleshooting initiated.

Troubleshooting of the ' A' D/G output breaker identified that the plunger bolt (which actuates certain stationary contacts when the breaker closes) was out of adjustment.

Consequently, the stationary contact did not sustain a signal to the load sequencer.

The condition also prevented synchronizing of the D/G with offsite power by not allowing a synchronizing check relay to pick up.

Note: The stationary contact was momentarily actuated by the plunger bolt due to the force of the breaker closing, causing the Centrifugal Charging Pump (CCP)

(a time zero sequenced load) to start. The stationary contact failed to remain closed due to the plunger bolt being out of adjustment, so the remaining loads failed to sequence onto the bus.

The Component Cooling Water Pump (CCW) was started by a CCP-CCW interlock approximately one second after the start of the CCP. Had the stationary contact remained actuated, this interlock would have been defeated and the CCW pump would have started at sequencer step one (five seconds following start of the sequencer).

Temporary adjustments were made such that the synchronizing check relay picked up.

The D/G was paralleled with offsite power and the loads were transferred off the D/G. The D/G output breaker was opened, and the D/G secured and declared inoperable at approximately 2350 on 3/6/86.

The plunger bolt was found to be out of adjustment by approximately 3/32 of an inch.

It was adjusted within tolerance per Electrical Preventive Maintenance Procedure MPE-ZZ-QS005, Cleaning, Inspection, and Lubricatien of 13.8 kV and 4.16 kV Breakers, at 0210 on 3/7/86.

The "'A' Train Blackout Without SIS" portion of ISP-SA-2413A was again commenced at approximately 2040 on 3/7/86 and completed satisfactorily.

'A' D/G was declared operable at 2222 on 3/7/86.

t SPECIAL REPORT 86-01 REVISION 1 Page 3 Verification of proper adjustment of the plunger bolt for 'A' D/G output breaker was last performed on 5/20/85 during an 18 month preventive maintenance inspection. The cause of the plunger bolt being out of adjustment is unknown. This type of problem has not been a frequently experienced occurrence associated with the D/G output breakers; however, due to the significance of the plunger bolt / stationary contacts function, a preventive maintenance inspection for proper adjustment of the plunger bolt will be evaluated for increased frequency for 'A' and 'B' D/C output breakers.

This incident occurred while the plant was in Mode 5.

In this mode, T/S 3.8.1.2 requires only one diesel generator to be operable.

'B' D/C was operable while 'A' D/G was out of service for testing and inoperable due to the output breaker plunger bolt.

Performance of ISP-SA-2413B, Diesel Generator and Sequencer Testing (Train B), began following completion of ISP-SA-2413A.

On 3/10/86 the load sequencer for for 'B' train functioned satisfactorily when the breaker closed during the "'B' Train Blackout Without SIS" portion of ISP-SA-2413B.

Surveillance tests are currently performed at least once per 31 days for each D/G.

This is in conformance with the schedule of Regulatory Position C.2.d of Regulatory Guide 1.108. Revision 1 August 1977, and Technical Specification Table 4.8-1 which require the l

test interval to be not more than 31 days if the number of failures in the last 100 valid tests is one or zero.

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