ML20211P203
| ML20211P203 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/17/1986 |
| From: | Sylvester E Office of Nuclear Reactor Regulation |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| References | |
| GL-84-11, NUDOCS 8607230035 | |
| Download: ML20211P203 (1) | |
Text
July 17,1986 Docket No. 50-325 DISTRIBUTION
$ Docket FileMr NRC PDR Mr. E. E. Utley Local PDR Senior Executive Vice President Plant File Power Supply and Engineering & Construction RBernero Carolina Power & Light Company NThompson Post Office Box 1551 SNorris Raleigh, North Carolina 27602 ESylvester EJordan
Dear Mr. Utley:
BGrimes JPartlow
SUBJECT:
SAFETY EVALUATION OF INTERGRANULAR STRESS ACRS(10)
CORROSION CRACKING (IGSCC) PROGRAM OGC Re:
Brunswick Steam Electric Plant, Unit 1 In our letter dated October 11, 1985, we informed you that the improvements, replacement, inspection and repairs to reactor coolant piping systems during the November 1984 mid-cycle outage and the Refuel 4 outage at Brunswick Steam Electric Plant, Unit 1, meet the guidelines in our Generic Letter 84-11 and are acceptable.
In the October 11, 1985 letter, we stated that the detailed Safety Evaluation of the IGSCC Program supporting our conclusions would be transmitted separately. Accordingly, the subject Safety Evaluation is enclosed for your use.
Because of uncertainties 'about the long term behavior of the piping, we request that your plans for inspection and/or modification to the recirculation and any other service sensitive austenitic stainless steel piping systems operating over 200 F during the current operating cycle be submitted for our review and comment at least three months before the start of the next outage.
Sincerely, Original signed by t
Ernest D. Sylvester, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosure:
As Stated
- SEE PREVIOUS PAGE FOR CONCURRENCE L3L:PD#2 M DBL de/
2 D
PD#
- ESylvester D l S
is:rs
//l 86 7/W'/86
[//86 8607230035 860717 PDR ADOCK 05000325 G