ML20133K467
| ML20133K467 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/02/1985 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20133K468 | List: |
| References | |
| NUDOCS 8508120242 | |
| Download: ML20133K467 (2) | |
Text
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s SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFFICE ?$4 CotuualA, SOUTH CAROLINA 29218 August 2, 1985 o.w.omO=.a.
VICE Pat $ DENr NuCLaan oesnatcNs
.Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington', DC 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Type C Testing
Dear Mr. Denton:
In letters from Mr. O. W. Dixon, Jr., to Mr. H. R. Denton dated October 8,1982 and April 26, 1984, South Carolina Electric and Gas Company (SCE&G) requested revisions to Table 3.6-1, " Containment Isolation Valves." As a result of further evaluations and subsequent discussions with NRC Staf f, SCE&G hereby requests the previous submittals be amended as shown on the attached marked up Technical Specification pages.
Valves 8090 A and B are being deleted from Table 3.6-1 as a result of a modification to the plant to remove these valves from service.
Footnotes are
- being added to eight valves to indicate that they are not Type C tested on the basis that they do not meet the 10CFR Part 50, Appendix J criteria for Type C t es ting.
For pressurized water reactors, valves requiring Type C testing per Appendix J fall into any of the three following categories:
- 1) provide a direct connection between the inside and outside atmospheres of the primary reactor containment under normal operation; 2) are required to close automatically upon receipt of a containment isolation signal; or 3) are required to operate intermittently under post accident conditions. These eight valves do not fall into any of these categories and therefore should not be required to be tested according to the Appendix J, Type C requirements.
Enclosed as Attachment B is SCE&G's proposed no significant hazards determination. This change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee. The fee for processing this amendment has been submitted previously with the October 8,1982 submittal.
If you should have any questions, please advise.
Very truly yours, J
y
- r. / ^
- 0. W. Di o,
AMM/0WD/c sw Attachments cc: (See page 2) 8508120242 850802 PDR ADOCK 05000395 P
l Mr. Harold R. Denton August 2,1985 Page 2 cc:
V. C. Summer C. A. Price T. C. Nichols, Jr./O. W. Dixon, Jr.
C. L. Ligon (NSRC)
E. H. Crews, Jr.
K. E. Nodland E. C. Roberts R. A. St ough W. A. Willians, Jr.
G. O. Percival D. A. Nauman C. W. Hehl J. Nelson Grace J. B. Knotts, Jr.
Group Managers H. G. Shealy O. S. Bradham NPCF File
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