ML20084A992

AO 3-2-6:on 730519,within Minutes After Starting High Head Safety Injection Pump 23,accumulator Level Observed Not Changing & Pump Discharge Pressure Decreased to Existing Rcs.Caused by Personnel Error

ML20084A992
Person / Time
Site:	Indian Point
Issue date:	05/29/1973
From:	Caldwell W CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
References
AO-3-2-6, NUDOCS 8304060060
Download: ML20084A992 (2)

Text

Wilh:m E. C:tdwell, Jr.

vn h+s o., e Conschdated idison Company of New York. Inc.

4 Irvo g Place. ! Jew York, fJ Y 10003 leh'phor o (212) 460-5181 May 29, 1973 Re: Indian Point Unit No. 2 AEC Docket No. 50-247 Facility Opera ' License DPR-26 '9

/ Y D Mr. John F. O' Leary, Director

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Directorate of Licensing 'i

'bIJJ U. S. Atomic Energy Commission 3U4 M 1078A I j

Washington, D. C. 20545 Yx $f

'A nis ' ;r . l Dear Mr. O' Leary The following report of Abnormal Occurrence No. 3-2-6 is provided pursuant to the requirements of Section 6.6.1.D of the Technical Specificati.ons to Facility Operating License No. DPR-26.

On May 19, at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, No. 23 Iligh Head Safety Inj ection Pump was started in order to add water to the Safety Injection System Accumulators. Within a few minutes after starting the pump, and after first observing normal pumping characteristics, it was noted that the accumulator level was not changing and that the pumps discharge pressure had decreased to that exist-ing in the Reacter Coolant System. Safety Injection Pump No. 23 was thereupon shut down.

Investigation revealed that a motor-operated valve, (MOV) 1810, in the common suction line from the Refueling Water Storage Tank to the fligh IIcad Pumps was closed. The motor operated valve was opened and a re-start of the pump was attempted with-out success. Apparently, the pump had seized as a result of having been operated without a source of water. Safety Injection Pump No. 23 was then replaced with an identical pump which was tcsted satisfactorily.

Investigation into the cause of the improper valve lineup revealed that several key operations personnel had assumed that MOV 1810 was in its normal position, i.e., open and deenergized as required by the Technical Specifications which gegod oEoSShl E a 3521' * ")

COPY SENT TEGION .

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Mr. John F. O' Leary May 29, 1973 define prerequisite conditions for reactor criticality, and did not obtain verification of the valve status prior to starting the pump. In fact, the valve was shut in order to facilitate maintenance work which had been performed on the system. The occurrence, therefore, was the direct result of standard operating procedures not being followed by the operating personnel prior to starting this high head pump.

Safety implications attendant to the occurrence are non-existent. This evaluation is based on the fact that the Unit No. 2 reactor had not yet been brought to initial criticality, and completion of the required precriticality check-off list would have assured the proper position of MOV 1810 before reactor startup even if pump failure had not occurred. Further-more, the subject check-off list is required to be completed prior to reactor startup at any time, regardless of the reason for shutdown, or its duration. For this reason, we consider it extremely unlikely that the Unit No. 2 reactor would ever be brought to operating status while MOV 1810 is in the closed position. We wish to note that Technical Specification 3.3.A.1 specifically requires that MOV 1810 be in the open, deenergized position while the reactor is in service.

Very truly yours

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01210 FR DC NEWYORK NY 40105-21742P EDT PMS JAMES P OREILLY DIRECTOR A I REWLATORY OPERATIONS REGION 1

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RE: INDIAN POINT UNIT NO 2 F ACILITY OPERATING LICENSE DPR-26 4 '.

DEAR MR OREILLY O

IN ACCORDANCE WITH THE REQUIREMENTS OF TECHNICAL SPECIFICATION

'. 6.6.1.B 0F FACILITY OPER ATIN LICENSE DPR WE WISH TO INFORM YOU OF AN ABNORMAL OCCURRENCE WHICH WAS IDENTIFIED S

ON MAY 19 1973 AT APPROXIMATELY 0215 HOURS-sr.m uing @

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C WITH THE UNIT NO 2 REACTOR IN A SHUTDCWN CONDITION, AND THE RE ACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE AT 413 PSIG AMD 225 F , RESPECTIVE LY, N O 22 HICH HEAD SAFETY INJECTION PUMP WAS STARTED INORDER TO ADD VATER TO THE SIS ACCUMULATORS- '

l" WITHIN A FEV MINUTES AFTER STARTING THE PUMP-I*

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AND AFTER FIRST OBSERVING NORMAL PUMPING. CHARACTERISTICS, IT WAS l NOTED THAT ACCUMULATOR LEVEL WAS NO CHANGING, AMD THAT THE PUMP i '

• DISCHARGE PRESSURE HAD DECREASED TO THAT EXISTING IN THE REACTOR COOLANT SYSTEM. S AFETY INECTION PUMP N0'23 VAS THEREUPON SHUT DO,WN-INVESTIGATION REVEALED THAT A MOTOR -OPERATED VALVE , NO 1810,- 1

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IN THE COMMON SUCTION LINE FROM THE FEFUELING EATER STORAGE. ~ ,_

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TANK TO THE SIS PUMPS WAS CLOSED APO }THIS, RESULTED .IN .THE ~ ' , .,

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o o n THE MOTOR-OPER ATED V ALVE VAS OPENED AND A RE-START OF THE PUMP WAS ATTEMPTED WITHOUT SUCCESS-APPARENTLY, THE PUMP SEIZED AS A RESULT OF HAVING BEEN OPERATED VITHOUT A SOURCE OF VATER. SAFETY INJECTION PUMP NO 23 2AS 4

REPLACED WITH A SPARE AND, AFTER HAVING BEE N S ATISFACTCRILY TESTED,

_, WAS RETURNED TO SERVICE ON'MAY 21, 1973 O

AN INVESTIGATION AS TO THE CAUSE OF NO 23 SAFETY INJECTION PUMP BEING OPERATED WITH AN IMPROPER VALVE LIhEUP IS PRESENTLY BEING CONDUCTED. AT THIS POINT IN TIME, IT APPE ARS O

THAT A MAJOR CONTRIBUTING F ACTOR IS THAT SEVERAL KEY OPER ATIONS PERSONNE L ASSUMED THAT MOV 1810 .WAS IN ITS NORMAL POSITION-1E OPEN AND DEENERGIZED, AND DID NOT ACTUALLY OBTAN VERIFICATION 9,

OF ITS STATUS PRIOR TO STARTING THE PUMP. A REPORT 0N THE sr-w m 3

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RESULTS OF THIS IN'IESTIGATION , AND ANY MEASURES TAKEN TO '

PHEVENT RECURRENCE, WILL BE FROVIDED WITHIN TEN (10) DAYS AS REQUI

' RED BY THE F ACILITY LICENSE.

~-l MR ELDON BRUNNE4 OF YOUR OFFICE WAS NOTIFIED OF THIS INCIDEUT BY MR JOHN MAKEPE ACE , CHIEF ENGINEER, UNIT NO 2, BY TELEPHONE ON MAY 19, 1973 IN ADDITION, AND IN ACCORDANCE WITH l

THE TE CHMICA L SPECIFICATION 6.2, THE CHAIRMAN OF OUR NUCLEAR rACILITITES S AFETY COMMITTEE WA5 NOTIFIED OF THE OCCURRENCE THE SAME DAY J

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io.....~,,...., ~nus nim ..s Licensce: Consolidated Edison Cor.:pany 3 11 . D. Thornburg, e.:a Docket No.- 50-247 Chic!, FSM B

.Bnor al occurrence: TWX dated 5/21/73 K j r o . .. .;, 4

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'E Central Files (1) c.ra '~~ ~ ~ ~ ~The attached report from the subject licensee is Recul atorv St andards :3)

Dir. of I,1 censing (13, i forwarded in accordance with RO Ffanual Chapter 1000, toi...-...,c.o anus ai-.ans The action taken by the licensee is considered

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eart appropriate. Followup will be performed during the next inspection Es anpropriate. Copics of F =O M (*e e me .nd vain a& M AA RS the report have been forwarded to the PDR, Local

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/)L ~~ PDR, NSIC, DTIE and State representatives. The

,E. J. Brunner, RO:I licensee will submit a 10 day written report to PHU8*4 MLL DATE 5/29/73 Licensing.

USE OT.etR SDL FOR ADClisO884 REMAasLS . cro: 107 o - e46-est b

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