ML20087N926
| ML20087N926 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/30/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8404050210 | |
| Download: ML20087N926 (3) | |
Text
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. SOUTH CAROLINA ELECTRIC & GAS COMPANY POSr OFFICE 764
' COLUMBIA. south CAROLINA 29218
- o' W. DixON, JR, v.Ca paesio Nr March 30, 1984 NUCLEAR OPanarioNS '
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 Condition 2.C.15
Dear'Mr.1Denton:
South Carolina' Electric and Gas ~ Company (SCE&G), in a November 6, 1981-letter to the Staff, committed to install power lockout devices in the control room for the Residual Heat Removal System (RHRS) suction' isolation valves prior to
. startup af ter the.first ' refueling.
This commitment was made to satisfy NRC concerns relating to Branch Technical Position
~
RSB 5-1 and.was subsequently incorporated as License Condition 2.C.15.
l Based on further review of this commitment, SCE&G has determined that this design modification may violate 10CFR PART 50,: APPENDIX'R. ' A fire in the Control Building could conceivably cause both RHRS suction isolation valves to open while the Reactor Coolant System-(RCS) is at a pressure
' greater than the RHRS design pressure,.which could result in a LOCA outside containment.
Presently, the circuit breakers are administratively locked open at the motor control centers
?
during-normal operation.
Accordingly, an amendment'to the Operating License is requested which would delete the requirement to implement this design modification.. As requested by the Staff, the following
!information~is provided in support of this License Amendment.
- As shown on FSAR Figure 1.2-15, the Main Control Room is located ~on
- the.463' elevation of the Control Building.
The
-breaker for valve 8701A is powered from Motor Control Center XMClDA2X. This Motor Control Center;is located in the switchgear
- room on the-463' elevation of the-Intermediate Building (see FSAR Figure-l.2-13).
Due to the close proximity to the Main Control Room,, an. operator could be-dispatched from the Main i
\\
Control' Room and perform the necessary actions to unlock and close-this breaker in approximately five minutes.
The valve 1*
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- Mr. Harold 1R. Dent'on,,
OperatinglLicense Condit' ion 21C.15
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- March-30, 1984~
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1 ican then be operated from the Control Room.
The. breaker:forivalve'8701B is; powered from Motor Control ir Center XMC1DA2Y which isilocated inLthe-switchgear room on the
'412'5 elevation of-the Auxiliary Building (see FSAR Figure 1.2-4). JThe breakers forfvalves-8702A and 8702B are powered in
, from. Motor? Control-Center XMClDBZY which is. located on the
"{
463' L elevation of.- the Auxiliary Building.(see FSAR Figure 1.2-6).
It is estimated,that approximately ten minutes would M
be' required for;an operator to proceed from the Main Control
+ Room ~.to thelabove describedibreaker-' locations land to perform
+
- =thefnecessary actions to unlock and close the breakers-allowingythe' valves to-be operatedifrom the Control Room.
P
? Thel additional timetthat :is required to operate these breakers L
flocally.is insignificant-compared with-the time available to P
perform the-necessary actions when proceeding to cold shutdown and21sinot1 operationally: limiting..
>.~
It - should sbelnoted - that during normal' plant operations there -
g
- arejauxiliaryfoperators stationed at various~1ocations pthroughout the plant including the Auxiliary.and Intermediate
~
(Buildings.cfIfithesenpersonnel werefutilized.to perform the d
d
- above required, actions, the estimated times;could be re uce.
u T'e most directiroute-for an operatorLto proceed to-the hJ i-
-differentJ breaker locations-would notL require passing through I"
Jan~ area iniwhich~hiah-radiation or:other: adverse-environmental
~
conditions would.normally occur. ~In-addition, there are r
Lother1 diverse < routes: t'o these locations ' which do not require-
- proceeding 1through adverse conditions.
~ Because;these valves can be operated.from the Main.' Control HRoom after:the; breakers have-been locally operated, and-because of the' minimal timeLrequired,to unlock and close these (breakers,cSCEEG-has determined that'a finding of no L
'significant1hazardsJis appropriate.. This License Amendment.
- has been. reviewed and approved by both the Plant Safety Review
. Committee'and'the Nuclear Safety' Review: Committee.
A check in L
J'
- the 1 amount of 'Four Thousand ~ Dollars ~ ($4000.00) -is provided to
- pro'ess1thi~s amendment.
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' Mr. Harold R.
Denton
=-
Operating. License' Condition 2.C.15
-March.30, 1984
. Page'#3
'L Should you have' any questions or comments, please advise.
Very tru y yours, O. W.
i n, J AMP /OWD/gj-cc: v. C.
Summer-T.
C. Nichols, Jr'./O. W. Dixon, ut.
E.
H.- Crews, Jr.
- E. C.. Roberts W.~ A.: Williams,.Jr.
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Nauman J.,P. O'Reilly Group Managers 7 0.. S. Bradham C. A.JPrice C. L'.:Ligon (NSRC)
K.-E.1Nodland R.' -- ~ A. Stough
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Percival C. W. Hehl J. B..Knotts,-Jr.
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