ML20080N371
| ML20080N371 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/09/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| References | |
| RO-SPR-84-001, RO-SPR-84-1, NUDOCS 8402220227 | |
| Download: ML20080N371 (2) | |
Text
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1 SOUTH CAROLINA ELECTRIC & GAS COMPANY
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Post oppica tee COLuweiA. south CAROLINA 29218 h
O. W. DixON, JR.
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February 9, 1984 vece
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NUCL.As OP.mAfions U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Virgil C.
Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Special Report (SPR 84-001)
Dear Sirs Please find attached a Special Report for the Virgil C.
Summer Nuclear Station.
This Report is required by Technical Specification 6.9.2 as a result of entry into Action Statement (a) of Technical Specification 3.7.10, " Fire Rated Assemblies,"
on January 10, 1984.
Should there be any questions, please call us at your convenience.
r trul
- yours, ixon, Jr.
RBJ:OWD/fic
Attachment:
cc:
V. C.
Summer D.
A.
Lavigne T.
C. Nichols, Jr./O.
W.
Dixon, Jr.
J.
F. Heilman E.
H. Crews, Jr.
C.
L. Ligon (NSRC)
E.
C. Roberts K.
E.
Nodland W. A. Williams, Jr.
D.
J. Richards D.
A. Nauman W.
C. Hehl J..P.JO'Reilly J.
B.
Knotts, Jr.
Group Managers INPO Records Center O.
S. Bradham NPCF C. A.
Price File 8402220227 840209 0FFICI AT, COPY PDR ADOCK 05000395 S
PDR afgn f
I DESIGNATED ORIGINAL Certificd By_
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NRC Document Control Desk Special Report (SPR 84-001)
February 9,1984 Page #2 EVENT DESCRIPTION On' January 10, 1984, the Licensee voluntarily entered Action Statement (a) of Technical Specification 3.7.10, " Fire Rated Assemblies," by opening the fire doors to the Chilled Water Pump Rooms.
The original Chilled Water Pump installation was of the self-cooling (water) design, and the HVAC to the area was originally installed as non-essential (Non-Nuclear Safety Related).
Chilled Water Pumps "A" and "C" were changed out by a design modification to air cooled pumps.
In the preliminary stages of the design change the potential need for additional area cooling to support operation of the replacement pumps was considered; however, the analytical work to fully document the issue was not completed.
Further calculations and documentation are now being accomplished with a scheduled completion date of March 30, 1984.
Additionally, Nuclear Engineering is reviewing the equipment qualification report for the motors in conjunction with area heat loads to determine the installed qualified life of the motors.
This evaluation is scheduled to be completed by March 30, 1984.
A preliminary engineering evaluation determined that by opening the doors of the rooms to the Intermediate Building
-- on loss of HVAC to the room -- enough cross ventilation would occur to ensure adequate cooling from an essential source.
This resulted in the establishment of a fire watch in accordance with Technical Specification 3.7.10.
ACTION TO BE TAKEN A supplementary report will be submitted upon completion of the analysis addressing action taken.
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