ML19343B274
| ML19343B274 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/12/1980 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19343B275 | List: |
| References | |
| NUDOCS 8012160655 | |
| Download: ML19343B274 (2) | |
Text
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' [i j ont First National Plaza. Chicrgo, Illinois Commonwealth Edison g
Address R; ply to: Post Offica Box 767 g
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- Chicago, Illinois 60690 December 12, 1980 l
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p Mr. B. J. Youngblood, Chief qG Licensing Branch No. 1 Q
2 Division of Licensing
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U.S. Nuclear Regulatory Commission g
Washington, DC 20555 x
Subject:
LaSalle County Station Unit 1 In-Scrvice Inspection and Test Plan and Baseline Inspection Report NRC Docket Nos. 50-373 and 50-374 References (a):
L. O. De1 George letter to 0. D. Parr dated March 15, 1979 (b):
S. S. Pawlicki memorandum to B. J. Youngblood dated August 18, 1980
Dear Mr. Youngblood:
Enclosed for your review are three (3) copies of the subject In-Service Inspection Plan, In-Service Test Plan and Baseline Inspection Report.
These materials supplement those provided for your review by Reference (a).
In the case of the In-Service Inspection (Weld) Plan, the program defined is responsive to questions posed by your Staf f in Reference (b) and discussed in a telecon conducted on the week of September 8, 1980.
With one exception, it is our judgement that the program defined fully satisfies the applicable requirements of 10 CFR 50 the exception relates to the exemption request mde under ASME Code Section IWB-1220(b) and involves the basis for calculating
" normal makeup capability".
Although this item does not effect pre-service inspection requirements and therefore, should not effect Unit 1 fuel loading Commonwealth Edison has not yet finalized its position relative to the criteria established by the NRC for this exemption.
This issue is also being reviewed on our operating BWR units at Dresden, and will be addressed generically by Commonwealth l
Edison for all effected BWR olants.
l In the case of the In-Service test (Pump / Valve) Plan, the program defined is responsive to questions posed by your Staff with h
the exception that the recently defined testing for valves at the S
interface of high and low pressure systems in accordance with a i
draft SRP revision has not been fully addressed.
The valves to i
which this criteria apply are currently being evaluated and will be addressed prior to fuel loading.
In this regard, the NRC committed
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to providing final guidance on this subject in December, 1980.
No W4 801216o/o55 g
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1 Mr. B. J. Youngblood, Chief December 12, 1980 Page 2 further guidance has been received as yet.
In the event you have any questions regarding the attacned materials, please direct them to this office.
Very truly yours, L. O. DelGeorge Nuclear Licensing Administrator Attachment cc:
RIII Resident Inspector - LSCS 8868A s
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