ML20101C574
| ML20101C574 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/14/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20101C581 | List: |
| References | |
| NUDOCS 8412210132 | |
| Download: ML20101C574 (3) | |
Text
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SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFFsCE 764 COLuusiA. south CAROUNA 29218
- 0. W.DMON,JR.
nuc$'id"o'Ea'Ir~[Cus December 14, 1984 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 Fuel Handling Building Ventilation System
Dear Mr. Denton:
3 South Carolina Electric and Gas Company (SCE&G) hereby requests a revision to the Virgil C. Summer Nuclear Station Technical Specification 3/4.9.11, " Spent Fuel Pool Ventilation System."
This proposed change modifies the statement of applicability and the surveillance requirement as shown on Attachment I to make the Technical Specification require certain surveillance testing only when the system is being used in an Engineered Safety Features (ESP) function.
The Spent Fuel Pool Ventilation System at the Virgil C.
Summer Nuclear Station has two (2) distinct functions.
These functions consist of being an ESF system to mitigate the offsite radiological consequences of a fuel handling accident and providing a filtration / ventilation system for the fuel handling building, hot machine shop and excess liquid radwaste area during normal plant operation.
The usual operating function of providing filtration for the above listed areas represents a portion of SCE&G's commitment to ALARA, and is not required to meet 10CFR100 criteria.
The proposed change recognizes that during periods of normal plant operation, the testing requirements are most properly outlined by Regulatory Guide 1.140, " Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of l
Light-Water-Cooled Nuclear Power Plants."
The requested revision l
to the Technical Specifications does not decrease the protection of the public in the event of a design basis fuel handling j
accident because the Technical Specifications continue to insure that the rigorous testing requirements of Regulatory Guide 1.52, 4
k Revision 2, March 1978, " Design, Testing and Maintenance Criteria
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for Post Accident
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=Mr. Harold R. Denton.
Fuel Handling Building JVentilation' System i.
December 14,fl984 Page #2
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J Engineere'd-Safety-Festure Atmosphere Cleanup System Air
' Filtration and Adsorption-Units of Lf ?ht-Water-Cooled Nuclear
-Power -. Plants," as committed to by SCEsG,. are completed prior to and during'use of the system for-its.ESF function, j
[
SCEEG has determined that a fin' ding of no significant hazards ~
is appropriate.
This request will not involve a significant t-
^
increase in the probability or_censequences of-an1 accident previously. evaluated because.the system. design will not change
- and will continue to be tested for operability before it is F
relied upon as an ESF_ system.
The proposed amendment will not create.the_ possibility of a new or different kind of accident i
from any accident previously evaluated because the system will Rbe tested to ensure that -it continues _to perform its ESF function as originally intended.
Furthermore, the amendment will not involve a significant reduction in a margin of safety 4
because SCEEG will continue to demonstrate operability of the system by performing -the required surveillance activities before allowing it to serve ascan ESF system.
F This amendment request does not change the types of. effluents -
or significantly increase the amounts of any effluents-that Lcould be released offsite.-
The filters will remain in place and-will operate in accordance.with-Technical Specification 3.'11.2.4 throughout all plant modes.
-In addition, they will-be tested for. operability prior to performing an ESF_ function.
~'
Therefore, in the event' of a-postulated fuel handling-F accident, the amount of effluents that could be released to
. the environment does' not change.fhaxn the present licensing basis analysis.
The individual or cumulative occupational i.
- radiation exposure is. not
- increased because the request does not-change the resulting exposure after a postulated fuel handling accident.and because there is not any significant F
occcupational exposure associated with the filtration system during normal plant' operation.
y This change has been reviewed and approved by both the Plant Safety Review 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 reque s t. -
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Mr. ' Harold R. ' Denton Fuel Handling Building
- Ventilation System December 14,.1984 Page #3
)
If'you have~any questions, please advise.
.Very truly yours, O. W. Dixon, Jr.
AMM/OWD/gj 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.
Stough W. A. Williams, Jr.
G. Percival-D.
A.
Nauman C. W.
Hehl J. P. O' Reilly J.
B.
Knotts, Jr.
Group Managers H. G.
Shealy O.
S.
Bradham NPCF File i
A 6
L 1