ML19208B468
| ML19208B468 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/29/1979 |
| From: | Manry M GEORGIA POWER CO. |
| To: | |
| References | |
| PM-79-801, NUDOCS 7909200372 | |
| Download: ML19208B468 (4) | |
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accrgia Power August 29, 1974 PM-?Q-801 PLANT E.
I.
HATCH Docket No. 60 7?1 Special Renort on RHR Puno Suction Torus Isolation Valve E11-F004B Mr. James P.
O'Reilly Director of Inspection and Enforcement O p' p' D
Region II
'h Suite 3100 bdj 101 Marietta Street Atlanta, Georgia 30302 p[D),- @
T, wUlt;0 L b
Dear Sir:
On May 17, 1979, with the reactor in re fue li ng, a Local Leak Rate Test (LLRT) of the RHR nuno "B"
suction t o rta s isolation valve E11-F0048 was performed per HNP 1 105?.
This test shoued the valve to be leaking in excess of specified criteria frefer to LER 50-321/1070 033).
Following cor-ective action (lapped seat
- eings, laoped
- gate, and adjusted the valve's motor operator see MR
- 1 79-2423),
the valve was satisfactorily retested on July 26, 1979.
On August 12,
- 1070, the " B loop of the RHR svstam was placed in service in the shutdown cooling mode of operation, and the
. reactor vessel level was observed to staat dropoing.
Investication showed that if the E11-F065n valve was closed, then the reactor vessel water level vould stabilize.
- Thus, the E11-F0049 and/or the E11-F0309 valves were leaking.
On August 13, 1079, the "B"
RHR pumo was run torus to torus in an attempt to flush the seat of the E11-F00hB valve;
- however, this had no a p p re c i.a b l e effect on the leakage.
On August 14,
- 1979, the E11-F0309 (relief valve) was removed and bench-tested satisfactorily.
- Thus, the E11-F004R valve was determined to be leaking.
The LLRT performed on the E11-F00hB valve on July 26,
- 1079, was performed in the direction that it would have to prevent leakage post-LOCA, f.e.,
fron the inside of primary containcient outward; the 1.eaka.ge now exisiting for the E11-F00h9 valve is in the occosite direction, i.n.,
back towards contat.nnent.
This leakage oath f"om the reactor vessel to the nucoression chamber / torus) oniv exists when the "B"
RHR oump is in the shutdown cooling m o(i e of operation.
Thut. it was decided that the leakage or the valve represented no condition that would oreclude normal ocaration.
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he decision w19 then nad.
to peaform a
new LLRT on the 311-F0039 valve in order to ensure that the crimary containment l a t e r,"i t y of the valve still existed.
Thus, on August 14, 1970, a LLRT of the valve was performed.
The a e s u '. t s of this test showed the valve to be Icaking less than the accentance criteria soecified by the Technical Specification a ntf: 10CFR50 accendix J
(.60La overall l e a'c a g e for all tvoe 9 and type C LLRTs, and the leakage of the valve shall b'e 109 enou'dh such that the seal. water inventory of the valve is sufficient for 30 days - the seal water inventorv for the E11-F00hB valve is the torus).
- However, the valve leak rate was judged to be excessive by plant personnel and a
deviation "coort
(#1 70 126) was waitten saying that the E11-F00h8 valve had failed the LLRT.
It was determined by the Plant 9eview Board that a
Licensee Event Reco"t was not requiaed since the applicable Technical Specification and 10CFR50 apoendix J
aceeotance criteria had been satisfied; houever, it was decided that a special reoort be written due to the sequence of events.
F o l. l ow i n st maintenance on the valve (tightened fou" bolts on the valve's notor ooerator - MR #1-70 h741),
a satisfactory LLRT was performed on August 16, 107o.
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