ML20077D153
| ML20077D153 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/22/1983 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20077D154 | List: |
| References | |
| NUDOCS 8307260394 | |
| Download: ML20077D153 (2) | |
Text
_.. -
.9 SOUTH CAROLINA ELECTRIC & GAS COMPANY -
Post orrics 7s4 COLUMBIA. SOUTH CAROLINA 29218 O. W. DixoN, JR.
July 22, 1983 vic pm..**"'
NucteAn OpenarioNS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission
-Washington, D.C.
20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Technical Specifications - RM-Lll License Condition 2.C(21)
Dear.Mr. Denton:
License Condition 2.C(21) of the Virgil C. Summer Nuclear Station Operating License-requires the South Carolina Electric and Gas Company-(SCE&G) to install and calibrate the condensate demineral-izer backwash. effluent monitor RM-Lll prior to startup after the first refueling outage. This letter serves to inform you of the completion of this action and requests appropriate revisions to the Technical. Specifications to reflect-the use of monitor RM-Lll.
~
Changes (a) - (d) on the attached marked up Technical Specifica-tion pages incorporate RM-Lil into the Technical Specifications and define appropriate surveillance requirements.
The proposed i
Action Statement 36 is modeled after Action Statement 33 but recognizes that-this'is a batch sample and that it must meet sampling requirements for the resin as well as the liquid portion.
Because of the expected low activity of this pathway, no requirement for redundant calculation or line valving is necessary.
The change denoted'as (d) defines the appropriate Analog Channel Operational Test for a batch monitor.
This secondary side system has an alarm on its local control panel but not in the control room.
A finding of no significant hazard is justified because the addition of this monitor' represents an increase 'in our radiological monitoring capability.
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4 Mr. Harold R.~Denton July 22, 1983 Page #2 c
l Additionally,~an error in.the Technical Specifications has been corrected on. Table 3.3-12, 1.b, Nuclear (Processed Steam v
Generator) Blowdown Effluent Line RM-L7 or FM-L9 [see change (e) ].
Monitors RM-L7 and RM-L9 control a batch release, not a continuous release as implied by Action Statement 32.
Therefore, action:is changed from 32 to 31 as appropriate.
Because this change does not impact either-accident analyses
'or margins of safety, a finding of no significant hazard is
. jus tified.
These changes have been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety. Review Committee.
A check in the amount of Four Thousand Dollars
($4000.00) is enclosed for processing of this change.
If you require additional information, please contact-us.
Very trul
- yours, O. W.
D'xon,
'/fjc cc:
V..C.
Summer T.
C. Nichols, Jr./O. W.
Dixon, Jr.
E.
H.. Crews, Jr.
E.
C. Roberts H.
N. Cyrus J.
P. O'Reilly I
Group / General Managers O. S. Bradham R. B. Clary C. A.
Price l
A.
R. Koon.
C. L. Ligon (NSRC)
G. J.'Braddick J. C. Miller i
J. L..Skolds J.
B. Knotts, Jr.
H. G.-Shealy NPCF File (Lic./Eng.)
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