ML20211N254
| ML20211N254 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/11/1986 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20211N257 | List: |
| References | |
| NUDOCS 8612180171 | |
| Download: ML20211N254 (2) | |
Text
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29218 Nuclear Operations SCE&G
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December 11,1986 Mr. Harold R. Denton, Director Office 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
" Borated Water Sources"
Dear Mr. Denton:
This proposed change is to the Limiting Condition For Operations (LCO) requirements of Section 3.1.2.5, " Borated Water Source - Shutdown," and Section 3.1.2.6, " Borated Water Sources - Operating," and other related Sections 3.5.1, 3.5.5, B3/4.1.2, B3/4.5.4, and B3/4.6.2.2. The changes, as shown in Attachment I, revise the Refueling Water Storage Tank (RWST) boron concentration levels from a minimum of 2000 ppm to a minimum of 2300 ppm in Sections 3.1.2.5, 3.1.2.6 and B3/4.1.2, and from between 2000 ppm and 2100 ppm to between 2300 ppm and 2500 ppm in Section 3.5.5; revise the accumulator boron concentration levels from between 1900 ppm and 2100 ppm to between 2200 ppm and 2500 ppm in Section 3.5.1; and revise the pH value from between 8.5 and 11.0 to 7.8 and 11.0 for the solution recirculated within containment after a LOCA in Sections B3/4.5.4 and B3/4.6.2.2. The purpose of these changes is to increase current margin to a post-LOCA shutdown requirement (i.e., the reactor will remain subcritical in the cold condition following a large break LOCA assuming complete mixing of the RWST, Reactor Coolant System (RCS) and Emergency Core Cooling System (ECCS) water and other sources of water that may eventually reside in the sump post-LOCA with all control rods assumed to be out) in order to have increased assurance of conformance for Cycle 4 and future cycles at Virgil C. Summer Nuclear Station. A detailed Safety Evaluation has been performed, Attachment III, which determined that the proposed changes to the present Technical Specification limits will have no adverse impact on the plants safety analysis or result in a significant reduction in the margin of safety.
Attachment II to this letter is SCE&G'S "No Significant Hazards Determination." This change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee.
Please find enclosed the application fee of $150.00 required by 10CFR170.
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Mr. Harold R.Denton December 11, 1986 Page 2 The statements and matters set forth in this submittal are true and correct to the best of my knowledge, information and belief.
If you should have any questions, please advise.
tr h ours, A. Nauman HID/ DAN:jez Enclosures c:
- 0. W. Dixon, Jr./T. C. Nichols, Jr.
C. L. Ligon (NSRC)
E. H. Crews, Jr.
R. M. Campbell, Jr.
E. C. Roberts K. E. Nodland O. S. Bradham R. A. Stough D. R. Moore G. O. Percival J. G. Connelly, Jr.
R. L. Prevatte W. A. Williams, Jr.
J. B. Knotts, Jr.
J. N. Grace H. G. Shealy Group Managers NPCF W. R. Baehr File C. A. Price l
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