ML20042C705
| ML20042C705 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/18/1982 |
| From: | Lentine F COMMONWEALTH EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 4389N, NUDOCS 8206220369 | |
| Download: ML20042C705 (2) | |
Text
-_
Commonwealth Edison x
[
> one First Natiortl Pim, ch c]o. tilinois t
7 Addr;ss R ply to: Post Offier; Box 767 Chicago, Illinois 60690 j
June 18, 1982 Mr. Darrell G.
Eisenhut, Director Division o f Licensing U.S.
Nuclear Regulatory Commission t1ashington, DC 20555
Subject:
Zion Station Unit 1 Steam Generator Inspection and Repair NRC Docket No. 50-295 References (a):
March 10, 1982, letter from D.
G.
Eisenhut to L. O.
De lGeo rg e.
(b):
May 3, 1982, letter from F.
G.
Lentine to D.
G.
Eisenhut.
(c):
May 21, 1982, letter from F.
G.
Lentine to H. R.
Denton.
Dear Mr. Eisenhu t :
This letter is to document the resolution reached following discussions with members o f your staf f regarding the Zion Unit 1 Steam Generators.
This is to confirm that Commonwealth Edison will perform the following inspections at Unit l's next scheduled refueling outage, in addition to those committed to in reference (b).
1.
At least 25% o f tubes with AVB's will be eddy current examined.
2.
All tubes in the hot leg tubesheet region o f 1D steam generator will be eddy current examined.
3.
Photographs will be taken o f a sample o f tube-to-tubesheet welds in the 1D steam generator selected from those tubes expanded by the slide hammer process.
The minimum sample shall be approximately 10-12 tubes, selected in such a way as to minimize radiation exposure.
0$
206220369 820618 DR ADOCK 05000295 PDR
o D.
G. Eisenhut June 18, 1982 In addition, Commonwealth Edison will comply with the following reporting program to keep the NRC informed of the status of steam generator tube leakage.
It is proposed that the following footnote be added to Technical Specification 3.3.3.E, page 97:
"During Unit 1 Cycle 7 operation, the baseline primary to secondary leak rate for each steam generator shall be determined a f ter reaching equilibrium operating conditions.
Af ter reaching a primary to secondary leak rate for any steam generator of 100 gpd, an increase in the leak rate o f 50 gpd over a 7 day period or 100 gpd over a 30 day period shall be reported to the assigned NRC Project Manager verbally within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a written followup report l
within 14 working days.
The followup report shall contain l
Commonwealth Edison's analysis of the increased leakage and evaluation to assure that an acceptable level of tube integrity will be maintained.
In the event o f a mid-cycle shutdown to repair tube leakage, Commonwealth Edison shall inform the NRC of the actions to be taken and inspections to be performed.
These requirements will no longer be in ef fect once Unit 1 begins the Cycle 7-8 refueling outage, and this footnote will be void as of that date."
Please address any questions regarding this matter to this office.
Very truly yours, k
$N4 l
F.
G.
Lentine Nuclear Licensing Administrator 1m 4389N