ML20207M486
| ML20207M486 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/08/1987 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20207M491 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8701130191 | |
| Download: ML20207M486 (2) | |
Text
10 Cft?. SO e
a s
na Electric & Gas Company n
Columbia, sC 29218 Nuclear Operations (803) 748-3513 SCE&G
~*
January 8,1987 Mr. Harold R. Denton, Director OfTice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington,DC 20555
Subject:
Virgil C. Summer Nuclear Station Doc cet No. 50/395 Operatin r License No.NPF-12 Technica Specification Change
" Reactor Trip System Instrumentation Trip Setpoint" Table 2.2-1
Dear Mr. Denton:
This proposed change to the Licensee's Technical Specification is being submitted because of an approved modification to meet Regulatory Guide 1.97 Revision 3 requirements for Post Accident Neutron MonitoringInstrumentation. This modification is currently scheduled for implementation during the third refueling outage, Spring of1987 and will replace the present non-post accident qualified Source Range (SR) BF3 detectors and Intermediate Range (IR) Compensated Ion Chamber detectors with IE, post accident qualified fission chamber detectors.
Instrument ranges and scales of the existing detectors versus the replacement detectors are as follows:
Detector BF3 Fission Chamber SR 100 - 106 cps 100 - 106 cps
- IR 10 10-3 amps 10 2x102% Indication
- NOTE: The IR scale changes from amps to percent indication.
This proposed change is administrative in that no setpoints are being changed. The setpoint and allowable values are being converted from current (amps) to the equivalent %
indication.
This proposed administrative change is to Section 2, Table 2.2-1," Reactor Trip System Instrumentation Trip Setpoints", Item 19A, Intermediate Range Neutron Flux, P-6 and page B2-5 of the Bases, Intermediate and Source Range, Neutron Flux. This change, as shown in Attachment I, converts the Trip Setpoint and the Allowable Value (Table 2.2-1) from current (amps) to the equivalent % indication. The change in the Bases deletes the reference to "a current level equivalent" and provides further clarification on the purpose of the P-6 setpoint.
Attachment II to this letter is SCE&G's "No Significant Hazards Determination". This chan;ge has been reviewed and approved by both the Plant Safety Review Committee and the 1Vuelear Safety Review Committee.
Please find enclosed the application fee of $150.00 as required by 10 CFR 170.
[ (l 8701130191 87010s m
PDR ADOCK 05000395 (4k P
PDR g
iso.w
e Mr. Harold Denton Page Two January 8,1987 Ifyou should have any questions, please advise, ry trul yourO s
aqAa RJB: DAN:bjh Enclosures c:
O. W. Dixon, Jr./f. C. Nichols, Jr.
E. C. Roberts O. S. Bradham J. G. Connelly, Jr.
D. R. Moore W. A. Williams,Jr.
J. N. Grace Group Managers W. R. Baehr C. A. Price C. L. Ligon (NSRC)
R. M. Campbell K. E. Nodland R. A.Stough G. O. Percival R. L. Prevstte J. B. Knotts, Jr.
H. G. Shealy NPCF File