ML19341A860
| ML19341A860 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/13/1981 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-80-24, NUDOCS 8101280521 | |
| Download: ML19341A860 (2) | |
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WISCONSIN Electnc eom come%g.itmug" '
2n w. mcmcAN, P 0. BOX 2046. MILWAUKEE. WI 53201
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January 13, 1981 Mr. J.
G.
Keppler, Regional Director Office of Inspection and Enforcement, Region III U.
S. NUCLEAR REGULATORY COPJ1ISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
DOCKET NOS. 50-266 AND 50-301 ADDITIONAL INFORMATION IE BULLETIN 80-24 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 By letter dated January 5, 1981 we provided a response to IE Bulletin 80-24, " Prevention of Damage Due to Water Leakage Inside Containment".
On January 9, 1981 we received a call from Mr. W.
G.
Guldemond, senior resident inspector at the Point Beach Nuclear Plant, requesting that we supplement our response with a discussion of our experience with closed cooling water systems inside containment and any plans we have to provide redundant water level indication in containment.
Accordingly, we are providing the following additional information to our bulletin response.
Point Beach utilizes one closed cooling system (component cooling water) inside containment.
The component cooling water system is described in Section 9.3 of the Point Beach Final Facility Description and Safety Analysis Report.
Monitoring of the component cooling water loop surge tank provides a sensitive indication of any leakage from this system.
We have experienced four in-containment component cooling water leaks in Point Beach Unit 1 and five component cooling water leaks in the Unit 2 containment.
Of these nine leaks, six predated the commercial operation of the respective units.
Four of the leaks involved seat leakage on pressure relief valves, four involved piping flange leaks at cooler or flow orifice interfaces, and one involved packing leakage on a vent valve.
All leaks were promptly repaired.
Although exact amounts of leakage involved are not recorded, there were no significant accumulations of water in containment as a result of these small leaks. 416 M 81 01280 W q
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l 2-January 13, 1981 Mr. J. G. Keppler As a result of the requirements imposed in NUREG-0578, "TMI Lessons Learned Task Force Status Report and Short-Term 4
Recommendations", and the October 30, 1979 clarification of NUREG-0578, we have committed to providing additional water level 4
monitoring instrumentation in containment.
Our letters dated December 31, 1979 and December 23, 1980 discuss our plans and schedule for this modification.
We will be adding one water level indicating system in the reactor vessel keyway in the vicinity i
of the A sump and two water level indication systems to the containment B sump.
These systems will provide redundant contain-ment water level indication from approximately six inches above j
the floor of the keyway to in excess of 90 inches.
These systems will be in addition to the existing sump A level alarm and the discrete sump B water level indications presently installed.
Our scheduled completion date for these modifications, subject to equipment availability and procurement, is January 1, 1982.
We trust this additional information satisfies your questions regarding our January 5 submittal.
Please note that in addition to the in-containment service water loads mentioned in our January 5 letter, the fire protection hose reels installed in containment are supplied, when needed, by service water.
Should you have any additional questions in this regard, please contact us.
I very truly yours, j
n
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%(F Executive Vice President Sol Burstein i
Copies to NRC Resident Inspector Director, Office of Inspection and Enforcement i
Subscribed and sworn to before me this 13th day of January, 1981.
43MWy T
n Notary Phblic, State of Wisconsin A / ) #7 Y.
My commission expires - u '
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