ML20080T106
| ML20080T106 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/12/1983 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20080T110 | List: |
| References | |
| 8012PPC, LAP-83-476, NUDOCS 8310200166 | |
| Download: ML20080T106 (2) | |
Text
--
c r
CD&L Carolina Power & Light Company SERIAL: LAP-83-476 OCT 121983 Director of Nuclear. Reactor Regulation-Attention:.Mr. D. B. Vassallo, Chief Operating-Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission
' Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 PROCEDURE FOR ADMINISTRATIVE CONTROL OF INSERVICE INSPECTION ACTIVITIES ENGINEERING PROCEDURE: ENP-16
Dear Mr. Vassallo:
Carolina Power & Light Company understands that the Nuclear Regulatory Commission is currently evaluating the Brunswick Steam Electric Plant's (3SEP) Inservice Inspection Program. The BSEP Inservice Inspection Program was originally submitted on September 5, 1978 and since then has undergone considerable revision and upgrade. In order to facilitate your review, please find enclosed in Attachment 1 Engineering Procedure No. 16 (ENP-16), Revision 13,' entitled, " Procedure for Administrative Control of Inservice Inspection Activities." This document entirely supersedes the 1978 submittal.-
The above procedure is the reference document used to implement the Inservice Inspection and Post Maintenance Testing Programs for ASME Class 1, 2 i
and 3 systems and con.ponents. It also defines the methodology used by the l
_ repair and re;>lacement program. Additionally,~ the procedure denotes the code required examinations and testing, and also states BSEP's policies governing implementation of the code requirements. References are provided to specific implementing procedures where the detailed testing requirements are found i
(i.e., test parameters, reference conditions, acceptance criteria, etc.).
- a $.
Some spaces have been intentionally left blank to facilitate future revisions.
a.
b
' Specific requests for relief from code requirements are listed in
.{G the following sections:
4:g:
1)
II.D Weld Inspection Program, pages 28-34
[' @
2)
IV.H Valve Testing Program, pages 189-200 3)
.V.F Pumps Testing Progra:n, page's 208-211 g
5
!4) VI.I Visual Inspection Program, pages 251-252 7
6.0 411 Fayetteville Street
- P. O. Box 1551
- Raleigh, N. C. 27602 P
c.
_m J
D. B. Vassallo Attachment 2 provides the status of the individual code relief requests and indicates where some NRC action is required. These relief requests are made pursuant to 10 CFR 50.55a(g)(5)(tv).
The Inservice Inspection Procedure is a document which in continuously updated to reflect plant specific conditions and any future relief requests from code requirements will be forwarded for your review pursuant to 10 CFR 50.55a(g)(5). Thus, it is CP&L's understanding that the
- NRC intends to review in detail the present program and that future program compliance will be verified by the regional NRC inspectors. Future revisions to the BSEP Inservice Inspection Program will only be provided to the NRC upon your specific request.
Should you have any questions concerning this submittal, please do not hesitate to contact us.
Yours very trul,
U.
to.
n P. W. Howe Vice President Bruiswick Nuclear Project PPC/ccc (8012PPC)
Enclosure cc:
Mr. D. O. Myers (NRC-BSEP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. S. D. MacKay (NRC)