ML20205D761
| ML20205D761 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/06/1986 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| IEB-80-24, NUDOCS 8608180168 | |
| Download: ML20205D761 (3) | |
Text
.. _
- e n.',mv I
,' we= i l1 c~n-,en,
l s
ROCHESTER GAS AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TELEPMONE anca coor 7,a 546 2700 f
August 6,1986 U.S Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Service Water Leak Inside Containment R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with the requirements of IE Bulletin No. 80-24
" Prevention of Damage Due to Water Leakage Inside Containment",
the attached 14 days written report is hereby submitted.
i V
truly yours, Y.
Roger W. Kober RWK/cc xc:
U.S. Nuclear R55ulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 l
8608180168 860806 1
[DR ADOCK 05000244 gh )
\\
y PDR l
SERVICE WATER LEAK INSIDE CONTAINMENT On July 29, 1986 Ginna Station was operating at hot shutdown I
following a manual reactor trip at 0351 hours0.00406 days <br />0.0975 hours <br />5.803571e-4 weeks <br />1.335555e-4 months <br />, containment atmosphere was' sampled and a containment entry planned.
At 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />, PT-2.7 " Service Water System" test was initiated, and at 1012 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.85066e-4 months <br />, the Containment Vessel "A" Sump Pump actuation alarmed and subsequently the actuation interval decreased significantly from normal.
This sump is located at the bottom of the reactor i
vessel cavity area and is the lowest elevation of the Containment i
Vessel.
An investigation for determination of the cause of leakage inside l
containment was immediately initiated.
No significant increases or changes were observed on 1) radiation monitors R-11 and R-12, (Containment Air Particulate Monitor and Containment Radiogas Monitor respectively), 2) containment dewpoint, 3) Reactor l
Coolant System Leakage, 4) actuation of the Containment Vessels j
Recirculation Fan Coolers Condensate Collection System dump j
valves to Sump "A".
A Service Water Leak was suspected.
An Operator, and Health Physics Technician made the containment entry at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> to investigate and identify the source of the leak.
Inspection of the 1B Containment Vessel (CV) Recirculation Fan Cooler revealed that a 1/8" diameter threaded motor cooler drain plug had become displaced during PT-2.7.
Operations personnel initiated the sequence for service water isolation to "B"
CV Recirculation Fan Coolers using maintenance procedure M-11.34.2
" Containment Recirculation Fan Cooler Maintenance".
The "B" CV Recirculation Fan motor was stopped by pulling-to-stop the fan motor switch and rendering it inoperable at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.
t The leak in the fan motor cooler was stopped at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> by closing the manual inlet and outlet service water valves.
4 l
I
/.o The drain plug was replaced and the remaining three plugs in the cooler were inspected per maintenance procedure M-11.34.2.
Drain plugs in the three other CV Recirculation Fan Coolers were also inspected.
Inspection resul,s revealed no additional drain plug replacements were necessary.
At the completion of the repair work, the "B" CV Recirculation Fan Cooler was restored to service at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />.
The leakage to the Sump "A" was calculated to be A500 gallons based on the Waste Holdup Tank level increase, the receiving tank of Sump "A" discharge water.
As a preventive measure, a Maintenance Work Request (MWR #86-2901) was initiated to replace all fan motor cooler drain plugs during the next Refueling Outage.
Also, PT-2.7 was reviewed and changes made to minimize the possibility of recurrence of drain plug j
displacement during testing.
The NRC was notified via telephone and the NRC Resident Inspector was also notified and appraised of the situation.
t l
_ _ _ - _. - ____j