ML20045D297

LER 93-012-00:on 930519,isolation Occurred When Rhr/Lpci Pump B Started in Shutdown Cooling Mode & Inboard & Outboard Isolation Valves Closed.Caused by Pressure Transient.Test Program Developed to Obtain Necessary data.W/930618 Ltr

ML20045D297
Person / Time
Site:	FitzPatrick
Issue date:	06/18/1993
From:	Mcguire P, Harry Salmon POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JAFP-93-0345, JAFP-93-345, LER-93-012-01, LER-93-12-1, NUDOCS 9306280189
Download: ML20045D297 (4)

Text

'

James A.FitzP; trick

. Nuclear Power Plant P.O. Box 41

, Lycoming. New York 13093

. 315 342-3840 '

4 NewWrkPbwer Harry P. Salmon, Jr.

& Aufhorty i nesioentuanager .

June 18, 1993 -

JAFP-93-0345 i

United States Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, D.C. 20555 i

SUBJECT:

DOCKET NO. 50-333 .

LICENSEE EVENT REPORT: 93-012 Shutdown Cooling Isolation  :

Dear Sir:

This report is submitted in accordance with 10CFR50.73 (a) (2) (iv) . F Questions concerning this report may be addressed to i Mr. Paul McGuire at (315).349-6362. t Very truly yours, i

HARRY P. SALMON, J .

HPS: :tld Enclosure cc: USNRC, Region i USNRC Resident Inspector INPO Records Center

^

9306280189~9306is-

-PDR S

ADOCM 05000333 I

PDR

. . _ ~ . _ . .

NRC FORM 366 t'.S. NUCLEAR REGULATO Y COMMISSIO APPROVED BY oms No. 3150-0104 (5 92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH

" "^ " kL '" E LICENBEE EVENT REPORT (LER) $MD (MMEN S REGARDiNG bug E$h5 N TE""$[)

THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, (See reverse for required runber of digits / characters for each block) WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503, FACILITY kAE (1) DOCKET NUMBER (2) PAGE (3)

James A. FitzPatrick Nuclear Power Plant 05000333 01 OF 03 TITLE (4)

Shutdown Cooling Isolation EVENT DATE (5) LER MtMBER (6) REPORT DATE (7) OTHER FACillTIES INVOLVED (8)

MC3TH SEQUENTIAL REVISION MY YW TEM MONTH DAY YEAR 05000 NUMBER NUMBER 05 FACitin NAME CKET BE 19 93 93 012 00 g gg OPERATING p TH IS REPORT IS SUBMITTED PURSUANT TO THE RIOUIREMENTS OF 10 CFR i: (Check one or more) (11)

MCDE (9) 20.402(b) 20.405(c) X 50.73(a)(2)(iv) 73.71(b)

PCuta 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) 000 LEVEL (10) 20.405(a)(1)(lt) 50.36(c)(2) 50.73(a)(2)(vil) OTHER 20.405(a)(1)(lii) 50.73(a)(2)(1) 50.73(a)(2)(vill)(A) (Specify in ac w 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) 20.405(a)(1)(v) 50.73(a)(2)(lii) 50.73(a)(2)(x) NRC Form 366A)

LICENSEE CON 1hCT FOR THIS LER (1?)

NAME TELEPHONE NUMBER (Include Area Code)

Mr. Paul J. McGuire, Senior Licensing Engineer (315) 349-6362 CEMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPOWENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER 0 S SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR Y SUBMISSION X (ES If yes, conplete EXPECIED SUDMISSION DATE). NO 12 1 93 DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

EIIS Codes are in []

The plant was shutdown and being cooled down for a maintenance outage. At 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> on 5/19/93, Residual Heat Removal / Low Pressure Coolant Injection (RHR/LPCI) [BO] Pump B was started in the shutdown cooling mode and the inboard and outboard shutdown cooling suction isolation valves closed upon initial startup of the pump. The isolation was caused by a pressure transient.

The second attempt to place the RHR system into shutdown cooling was successful. There have been seven (7) LERs written over the past three years concerning RHR Shutdown Cooling Isolations. This LER is an interin LER until further testing and a root cause analysis can be completed.

NRC FORM 366 (5 92)

NRCFb-366A u.s. uuCLtAR REGA.ATOY NMISSION APPROVED BT OMB NO. 3150-0104 (5 92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THl$ INFORMATION COLLECTION REQUEST: 50.0 HRS.

LICENBEE EVENT REPORT (LER) [E INF N N A REC DS MANAGE BRAN TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDCET, WASHINGTON, DC 20503.

FACIllTY MAME (1) DOCKET WLMBER (2) (ER NLMBER (6? PAGE (3)

James A. FitzPatrick Nuclear SEQUENTIAL REVISION YEAR Power Plant 05000333 93 0 02 OF 03 012 TEXT (if more space is reautred, use additional cooles of NRC Form 366A) (17)

EIIS Codes are in []

Svent Description The plant was shutdown and being cooled down for a maintenance outage. At 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> on Hay 19, 1993, while entering the shutdown cooling mode of the Residual Heat Removal / Low Pressure Coolant Injection (RHR/LPCI) [BO]

system, the B RHR pump was started. The RHR shutdown cooling inboard and outboard suction isolation valves closed, and the pump tripped. The valves closed due to an isolation signal (high reactor pressure, >75 psig). The isolation signal was caused by a pressure transient generated following pump start as system shutdown cooling flow to the reactor was being initiated.

The second attempt to place the system into the shutdown cooling mode was )

successful. I l

Cause of Event The root cause of the pressure transient is unknown. Since 1990, there have been seven (7) LERs written on RHR Shutdown Cooling Isolations. The l cause of these events may be the way the system is presently placed in I service, or the layout of the instrument line to the reactor high pressure

(>75 psig) isolation, or the need to vent and backfill the reactor high pressure switches. A test program will be developed to determined the root cause and appropriate corrective action to prevent further recurrence of these events.

Analysis of Event This event is not safety significant because the plant was shutdown and shutdown cooling was restored. Shutdown cooling isolation occurred when 02PS-128A or B contacts open due to high reactor pressure. The pressure switch instrument lines are connected to the "B" recircu3ation [AD] pump suction piping. The RHR/LPCI system shutdown cooling section line is connected to the Recirculation Loop B pump suction line. The purpose of the auto isolation is to protect the low pressure RHR piping from overpressurization events. The contacts are set to open on high (increasing) reactor pressure between 50 and 75 psig. The actual reactor pressure was less than 10 psig.

NRC FORM 366A (5-92)

. - . - ., - = . . . - _

l ~

l NRC FC M 366A U.S. NUCLEAR REGJLATOY CoppI!SSIO APPROVED BY Ole NO. 3150-0104 I (5 9J) EXPIRES 5/31/95 i I

ESTIMATED BURDEN PER RESPONSE 10 COMPLY WITH 1 THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDlWG BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMAT10N AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB 771'), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150 0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON, DC 20503.

FACILITY NADE (1) 00CKFT IRAqart (?) (ER IRAert (6? PAE (3)

James A. FitzPatrick Nuclear YEAR SE TIAL REV Power Plant 05000333 og 03 OF 03 93 012 TEXT (if more space is reautred. use additionet cocies of NRC Form 366A) (17)

This event is reportable under 10CFR50.73 (a) (2) (iv) , an event that resulted in automatic actuation of an Engineered Safety Feature.

l Corrective Actions l

1. Shutdown cooling was placed in service after resetting the isolation logic.

2. A test program will be developed to obtain the necessary data to perform a root cause-analysis and determine the need to develop additional corrective actions. The results of these tests will be reported in a followup LER by December 1, 1993.

3. The operating procedure will be revised to require that the RHR shutdown cooling suction piping be filled and vented using the condensate transfer system prior to opening the suction valves anytime shutdown cooling mode of RHR is secured for more than twenty-four hours. This will be completed by July 1, 1993.

4. The operating procedure will be revised to vent the pressure switch j instrument lines for 02PS-128A and B prior to the first initiation of j shutdown cooling following power operation. This will be completed by l July 1, 1993.

l  !

Additional Information Failed Components: None Previous Similar Events: LERs91-011, 90-013,90-016, 90-020,92-046 and 93-005 describes additional shutdown cooling isolations.

n NRC FORM 366A (5-92)

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