ML20038B032
| ML20038B032 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/19/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TAC-48122, NUDOCS 8111240622 | |
| Download: ML20038B032 (2) | |
Text
l Insconsin Electnc vous couesu<
231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 November 19, 1981 tFi NK
<s Mr. Harold R.
Denton, Director q3 s
Office of Nuclear Reactor Regulation
{g j{
y -)
U.
S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 S NOV2 41981=- 3 p.A nctu amWo"
~
Attention:
Mr.
R.
A. Clark, Chief co"" C"
.f Operating Reactors Branch 3
\\
Gentlemen:
- U IhI DOCKET MO. 50-266 STEAM GENERATOR INSPECTION PLAN AND OPERATING INTERVAL POINT BEACH NUCLEAR PLANT, UNIT 1 On L vember 13, 1981, Wisconsin Electric Power Company submitted Licensee Event Report No. 81-017/OlT which presented the results of the hydrostatic leak check and eddy current inspection of the Point Beach Nuclear Plant Unit 1 steam generators conducted during the fall 1981 refueling outage.
These inspections revealed only four eddy current indications in the "A" steam generator and three indications in the "B" steam generator which were not present during the July 1981 inspection.
Based upon these favorable results, we expect to return Point Beach Unit 1 to power on or about December 6, 1981 at a maximum hot leg temperature of 575 F, except for relatively brief intervals for testing purposes as discussed below.
This is the same temperature limitation in effect since the July 1981 inspection outage.
Based on the apparent marked reduction in steam generator tube corrosion rate, we believe it i 7propriate to operate Unit 1 until the normal fall 1982 refueli.., autage before the next steam generator inspection.
At that time, we will conduct a 2,000 psid primary-to-secondary and an 800 psid secondary-to-primary hydrostatic leak uheck.
In addition, we will conduct a complete eddy current inspection of essentially 100% of the hot leg tubes of both stean generators to the first support plate along with a normal Technical Specification based inspection of the steam generator tubes.
During this operating cycle we will continue to operate in accordance with the additional limitations imposed by the Confirmatory Order of November 30, 1979, as modified.
8111240622 81111W PDR ADOCK 05000266
/
ol O
PDR g,fg
Mr. Harold R.
Denton November 19, 1981 During the current outage, we have completed instal-lation of a leading edge flow meter in a common header of the main feedwater line of Point Beach Unit 1.
The leading edge flow meter has the potential to permit more accurate determination of steam generator feedwater flow rate and should, therefore, result in more accurate calorimetric calculations of primary-to-secoadary heat balance and determination of the primary system flow rate.
Following the completion of check out and testing of the electronics associated with the leading edge flow meter, we are planning to conduct calorimetric tests with this new system at various power levels up to 100% power.
It is expected that these tests will begin in January 1982.
The testing periods will be up to several days in length so that equilibrium testing conditions can be reached and accurate core thermal output, reactor AT, steam generator feedwater flow rate and other parameter determinations can be made.
Following this testing, we wil? continue operation at a maximum hot leg temperature of 575 F while the results of the testing are evaluated.
Depending on the evaluation of the leading edge flow meter testing and operational experience, we may consider modifying the Unit 1 operating temperature limits to a higher, or perhaps lower, temperature limit.
Our decision in this matter would be providca to you in writing prior to any increase in operatint temperature.
At that tirie, we would also re-evaluate the desirability of an inspection outage prior to the fall 1982 refueling outage and would advise you accordingly.
As stated previously, we expect to return to power on December 6, 3981.
We would be pleased to respond to any questions you may have regarding our operating plans for Point Beach Unit 1.
Very truly yours,
,5 Q&U d O
C.
W.
Fay, Director Nuclear Power Department Copy to: NRC Resident Inspector 1
Mr.
C.
F. Riederer (PSCW)
Mr. Peter Anderson (WED)
.