05000321/LER-1980-061-01, /01T-0:on 800622,while Preparing to Run RHR Sys Per HNP-1-6006,operator Discovered Loop B Min Flow Manual Valves E11-F0l8 B & D Closed.Caused by Operator Closing Valves to Prevent Reactor Water from Going to Torus

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/01T-0:on 800622,while Preparing to Run RHR Sys Per HNP-1-6006,operator Discovered Loop B Min Flow Manual Valves E11-F0l8 B & D Closed.Caused by Operator Closing Valves to Prevent Reactor Water from Going to Torus
ML19329F990
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/01/1980
From: Baxley S
GEORGIA POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19329F981 List:
References
LER-80-061-01T, LER-80-61-1T, NUDOCS 8007110442
Download: ML19329F990 (3)


LER-1980-061, /01T-0:on 800622,while Preparing to Run RHR Sys Per HNP-1-6006,operator Discovered Loop B Min Flow Manual Valves E11-F0l8 B & D Closed.Caused by Operator Closing Valves to Prevent Reactor Water from Going to Torus
Event date:
Report date:
3211980061R01 - NRC Website

text

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]lWhile preparing to run the RHR system ner HUP-1-6006 t h ej g ;kage inspection Preventive Maintenance), an operator discovered.that g; B" RHR loop minimum flow manual valves Ell-F018 !) & D were closed.

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NARRATIVE

REPORT Georgia Power' Company Plant E.

I. Itatch Baxley, Ga. 31513 Reportable Occurrence Report No. 50-321/1980-061 On 5-24-80, an orderly shutdown was initiated on Unit 1, the purpose being: going to cold shutdown to repair lEll-F015A & F050A.

On 5-25-80, the unit was in shutdown and "D" RHR pumn was on with.the "B" RilR loop in the shutdown cooling mode.

The "A" RHR loop was cleared and drained for maintenance to repair lEll-F015A & F050A.

On 5-26-80, the manual iso-lation valve (lEll-F018D) was closed to prevent reactor water from going to the torus'through the pump minimum flow line.

Apparently, the MOV minimum flow isolation valve (lEll-F007B) was leaking by slightly.

On 6-4-80,'the "A" loop of RHR was restored and operability was proved per HNP-1-3160 and HNP-1-3162.

Later that morn-ing, the "A" loop of.RHR was placed in shutdown cooling mode and the "B" loep of RHR was taken out of shutdown cooling mode.

- The "B loop of RHR was then utilized for torus cool-
- ing.

It was then discovered that the RHR minimum flow MOV (lEll-F0078) would not close with it's control switch.

The valve was closed manually and a maintenance request was -sub-mitted.

(Maintenance repaired lEll-F007B on 6-9-80 by ad-justing it's packing and replacing a closed torque switch.)

The "A" loop minimum flow isolation valves (1 Ell-F018 A & C) were' closed to prevent reactor water from going to the torus

- through the "A" RHR loop minimum flow line while this loop was in the shutdown. cooling mode.

On 6-5-80, the "B" loop of RHR was placed-in service in the shutdown. cooling mode.

The "A" loop of RHR was taken out of-service in order 1to perform a LLRT on lEll-F015A & F050A

- and so that said LLRT could be documented.

The "B" loop minimum. flow valves _(lEll-F018 B & D) were closed to prevent reactor. water _from going to the torus through the RHR minimum flow line while this loop was'in shutdown cooling node.

On-6-8-80,.the "A" loop of.RHR was.placed in service in the

~

- shutdown' cooling. node.

The "B"' loop of RHR was taken out of the shutdown cooling mode and placed in the standby con-dition.

0n.6-9-80.and 6-10-80, operability was performed on "B"

loop L

RilR: per HNP-1-3.162.and liNP-1-3160.

Page:1 of 2

Reportable Occurrence Report No. 50-321/1980-061 page 2 On 6-12-80, the "A" loop of RHR was taken out of the shutdown cooling mode and placed in the standby con-dition.

Reactor water was allowed to heat up as pre-.

parations were being made for reactor startup.

On 6-22-80, while performing HNp-1-6006 (RHR System Ell Leakage Inspection Preventive t.laintenance), an operator found lEll-F018 B & D in the closed position.

The operator was checking the pumps and valve lineup prior to pump start when he discovered these two va.lves closed.

These are normally locked open valves.

The two valves were placed in the locked open position and proper valve lineup for the major flow paths and mini-mum flows of the ECCS systems was verified on both Units 1 and 2.

A standir.g order was issued on repositioning valves on ECCS systems stating that if a valve must be changed from normal position, clearances shall be taken on such valve te document the change in posision.

The ECCS procedures are to be revised ~to reflect the standing order.

The procedures will be revised by 9-1-80.

The standing order will remain in effect until procedures have been evised.