ML20126E243

Proposed TS Bases 3/4.5.4 & 3/4.6.2.2 Re Revised,Lowered Ph Range of Solution Recirculated Through Sump Following Design Basis LOCA

ML20126E243
Person / Time
Site:	Summer
Issue date:	12/22/1992
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20126E238	List: ML20126E235 ML20126E243
References
NUDOCS 9212290066
Download: ML20126E243 (5)

Text

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Attachment To Document Control Desk-TSP 900007-0 Page 1 of 1 LISI Of AffECTED PAGES AND HARKED-UP 1ECHNICAL SPECIflCATIONS East Specification Description of Change B 3/4 5-3 3/4.5.4, " Refueling Revises the minimum value of the Water Storage Tank" acceptable pH range of the sump recirculation solution from 7.8 to 7.5.

B 3/4 6-4 3/4.6.2.2, " Spray Revises the minimum value of the Additive System" acceptable pH range of'the sump recirculation solution from 7.8 to 7.5.

2y22[jgho$ 5-P

O EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 11.0 for the solution recirculated I within containment after a LOCA. This pH band minimizes the evolution of lodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

(

SUMMER - UNIT 1 B 3/4 5-3 Amendment No. 61

CONTAINMENT SYSTEMS BASES 3L4.6.2.2 SPRAY ADDITIVE SYSTEM The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the reactor building spray in the event of a LOCA. The limits on NaOH volume and concentration ensure a pH value of between 7.5 and I 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained solution volume limit includes an allowance for solution not usable because of tank discharge line location or other physical characteristics.

These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.

3/4.6,2,3 REACTOR BUllDING COOLING SYSTEM The OPERABILITY of the reactor building cooling system ensures that 1) the reactor building air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the reactor building spray systems during post-LOCA conditions.

The reactor building cooling system and the reactor building spray system are redundant to each other in providing post accident cooling of the reactor building atmosphere. As a result of this redundance in cooling capability, the allowable out of service time requirements for the reactor building cooling system have been appropriately adjusted. However, the allowable out of service time requirements for the reactor building spray system have been maintained consistent with that assigned other inoperable ESF equipment since the reactor building spray system also provides a mechanism for removing iodine from the reactor building atmosphere.

The accident analysis requires the service water booster pump to be passing 4,000 gpm to both RBCU's within 86.5 seconds. This time encompasses the driving of all necessary ser ice water valves to the correct positions, i.e., fully opened or fully closed. Reference Technical Specification Bases B 3/4.3.1 and B 3/4.3.2 for additional details.

3/4.6.3 PARTICULATE 10 DINE CLEANUP SYSTEM lhe OPERABILITY of the containment filter trains ensures that sufficient iodine removal capability will be available in the event of a LOCA. The reduction in containment iodine inventory reduces the resulting site boundary radiation doses associated with containment leakage. The operation of this system and resultant iodine ren. oval capacity are consistent with the assumptions used in the LOCA analyses.

SUMMER - UNIT 1 B 3/4 6-4 Amendment No. 61 67

i EMERGENCY CORE COOLING SYSTEMS

. ' BASES ECCS SUBSYSTEMS (Continued) 7. 5 ,

The limits on con'ained water lune and boron concentration of the RWST also ensure a pH value of between 4 and 11.0 for the solutin recirculated _l within containment af ter a LOCA. This pH band minimizes the evolution of-.

lodine andsystems mechanical minimizes the effect of chloride and caustic stress corrosion on and components.  ;

i r

SUPNER - UNIT' 1 8-3/4 5-3 Amendment No. 61

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CONTAINMENT SYSTEMS 8ASES 3/4.6.2.2 SPRAh ADDITIVE SYSTEM _

7. 5 is added to the reactor building spThe OPERABILITY of the sp NaOH volume and concentration ensur. ray in the event of a LOC The. lsufficient Na0H solution recirculated within containment after a LOCA.e a and, pH valueIf.imits 0 foroftheon between the evolution of iodine and minimizes the effect of chloride corrosion on mechanica) systems and components. s c stress and cau line location or other physical characteristicslimit ank discharinclude sistent with the iodine removal efficiency assum. These assumptions are conge ed in the accident analyses.

3/4.6.2.3 REACTOR BUILDING COOLING SYSTEM 4

1) the reactor building air temperature will be iuff during when normal operated operation, in con and 2) adequate heht removal capacity s

vailable is a post-LOCA conditions. junction with the reactor b'uilding spray systems, l

The reactor building cooling system and the reactor building es are redundant building atmosphere. to each other,in providing post accident cooling of the r the allowable out of service time requirementongfor system have been appropriately adjusted.' However the rea cooling time requirements for the reactor building spray s,ystaanhave a ned been m consistent with that assigned other' inoperable ESF equipment since building reactor sprayatmosphere.

building system also provides a mechanism for removing rom the iodine f l

ing 4,000 spa to both RBCU's within 86.5 seconds.The acc t

driving fully openedof allornecessuy fully closed.service water valves to the correct positionsThis

, i.e.,

t and B3/4.3.2 for additional, details. Reference Technical Specification Bases 83/4.3.1 l

3/4.6.3 PARTICULATE IODINE CLEANUP SYSTEM

( iodine removal capability will be available The .

in the even radiation doses associated with containment leakage. re The operation of this used in the LOCA analyses. system and resultant iodine removal capac i

SUmliR.- UNIT 1 B 3/4 6-4 Amendment No. 67 67