ML20112C720
| ML20112C720 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/15/1985 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20112C722 | List: |
| References | |
| NUDOCS 8503220101 | |
| Download: ML20112C720 (3) | |
Text
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SOUTH CAROLINA ELECTRIC 8c GAS COMPANY POST OFFICE 764 CoLUMSIA. SoufH CAROLINA 29218 O
W. DenON. Jm.
Vice PerslOf NT March 15, 1985 NUCLE Am oramatioNs Mr. Harold R. Denton, Director Of fice 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 Administrative Technical Specification Changes
Dear Mr. Denton:
Please find enclosed as Attachments 1 through 6, administrative changes to the Virgil C. Summer Nuclear Station Technical Specifications.
A discussion of each of these proposed changes follows.
As shown on Attachment 1, South Carolina Electric and Gas Company (SCE&G) requests the addressee of the Monthly Operating Report be changed to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission.
This change is necessary to reflect the NRC's current reporting requirements. illustrates the corrections needed in Section 6.5.3, " Technical Review and Control." This change requests the term " Nuclear Engineering" be replaced by " Technical Services." This term accurately reflects the new title of the department charged with design modification authorization. adds Section 3/4.9-12, " Spent Fuel Assembly Storage," to the Index, both for the " Limiting Conditions for Operation and Surveillance Requirements" and for the " Bases" portions of the Technical Specifications.
The change also reflects page numbering corrections needed in Section 5 of the Index. This addition results from an oversite in Amendment 27 in which approval for the new high density storage racks was obtained.
Amendment 27 did not include the Index changes necessitated by the addition of the new section of the Technical Specifications and therefore this proposed amendment is being requested.
As shown on Attachment 4, Table 3.3-2, " Engineered Safety Feature Actuation System Instrumentation," Item 1.c should be changed to read, " Reactor Building Pressure High-l. Also, Table 4.3-2, " Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements," Item 1.c should be changed to read, " Reactor Building Pressure - High 1," and Item 2.c, should be corrected to read " Reactor Building Pressure -- High-3."
The numerical designation of order is consistent with other tables in the Technical y
Specification for Reactor Building Pressure.
Item 2.c in Table 4.3-2 is
'/
correctly identified to be of the third order in Table 3.3-4, " Engineered U
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' Mr.L Harold R.' Denton, Director Administrative Technical '
Specification Changes
. March.15, 1985
- Page #2-
' Safety Feature Actuation System Instrumentation Trip Setpoints," Item 2.c, and system-drawings illustrating the logic of the system.
' Attachment 5 corrects Section 3/4.6.1.4 for the design negative fpressure differential of the reactor building with respect to the outside atmosphere.
- The correct. value of 3.5 psig is currently defined in Sections 3.8.1.3.2.1,
" Reactor Building Liner' and Anchor Design Loads," and 6.2.1.2.2, " External Loading," of the Virgil C. Summer Nuclear Station Final Safety Analysis Report
- (FSAR). Therefore,-SCE&G requests the Technical Specification Bases be revised as indicated to reflect the correct external design pressure. alters Tables. 3.3-6, " Radiation Monitoring Instrumentation," and
' 4.3-3, " Radiation Monitoring Instrumentation Surveillance Requirements," to provide clarification of the required ' channels needed to meet Specification
~
3.4.6.1, " Reactor Coolant System Leakage." As indicated in the Reactor Coolant System Leakage Surveillance Requirements, Section 4.4.6.1, the performance of the monitoring system for gaseous activity in the reactor building must be checked.1 The gaseous channel of RM-A2 is required to perform E this monitoring in modes 1 through 4, and therefore should be included in Tables 3.3-6 and 4.3-3.
-A'. finding of no significant hazards is appropriate for these changes because
. the' changes are' clarifying and administrative ~ in nature.
Y!U This request has been reviewed and approved'Jby both the Plant Safety Review f_
Committee and the Nuclear Safety Review Committee.- A check in the amount of
> $ [)
one hundred fif ty dollars ($150.00). is enclosed to initiate the processing of
}
this request.
If-you have any questions, please advise.
Very truly yours,-
O. W. Dixon, Jr.
l-LAMM/0WD/gj Enclosure cc: :(See page #3) n ~
v L:
(..
- Mr. Harold R. Denton, Director
~ Administrative Technical Specification Changes March 15, 1985 Page #3
' cc:
V. - C.' Summer C. A. Price T. C. Nichols, Jr./0. W. Dixon, Jr.
C. L. Ligon (NSRC)
E. H. Crews, Jr.
K. E. Nodland E. C. Roberts.
R. A. St ough W. A. Williams, Jr.
G. Percival
~
D. A. Nauman C. W. Hehl J. N. Grace J. B. Knotts, Jr.
Group Managers -
H. G. Shealy O. S. Bradham NPCF File T
4 i.
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