ML20126E281
| ML20126E281 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/16/1992 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20126E273 | List: |
| References | |
| NUDOCS 9212290080 | |
| Download: ML20126E281 (9) | |
Text
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' to TXX 92613 p
10fATION SYSTEM _$
BASES TECHNICAL SPECIFICATION,(3/4.1.2) 1-i hj2gWK05000445 oso 921216 P
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CPSES - TECMMICAL SPECIFICATIONS ( TS )
AMENDHENT / REVISION 15
. to TXX-92613 DETAILED DESCRIPTION Page 1 Page 2 of 3 Prefix Page (ai amended)
Group Description B3/4 1-3 3
Updates RWST volumes for Modes 5 & 6 to clarify margin versus unuseable volume.
Update The unuscble volume in HODE 5 & 6 is based on the high point in the suction piping to the Centrifugal Charging Pumps. The volume above the unusable plus rsquired is margin in the Technical Specification volume (not " system configuration").
Based on the Unit 2 calculation, the Unit 2 Centrifugal Charging Pump suction piping is more limiting than Unit 1.
The unuseable volume and margin are adjusted accordingly.
Change Request Number
- TS-92-36.1 Commitment Register Number :
Related SER :
SSER :
SER/SSER Impact
- No B3/4 1-3 3
Changes BAST volumes for gravity feed to clarify s
margin.
Update The volume above the unusable plus required is margin. There is no " system configuration" associated with this me. lin.
Change Request Number
- TS 92-36.2 Commitment Register Number :
Related SER :
SSER :
SER/SSER Impact
- No l
l O --
- Enclo'sureL1 to TXX-92613 Page 3 of,3 1
R$ACTIV:
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S C N 'Cu 3<5TEMS
-BASE 5 g
BORATION 5<5TEMS (Continued)
- i Wit : e RC5 temperature below 200'F, one Boron injection System is-accettacie itncut 5 %gle failure consideration on the basis _of the stacle-reactivity condition of the reactor and the additional-restrictions preniciting-
- /
CORE ALTERATIONS and positive reactivity changes in the event the single Boren Injection System becomes inoperable.
The limitation for a maximum of two charging pumps to be OPERABLE' aridL the' requirement to verify one enarging pump to be inoperable below 350 F predices assurance that a mass addition pressure. transient can be relieved by the operation of a single PORV.
The limitation for minimum solution temperature of the borated water sources.
are suf ficient to prevent boric acid crystallization with the highest allo aole boron concentration.
The boron cacacility required ceiow 200*F is sufficient to provide a SHUT 00WN MARGIN of 17..\\k/k af ter xenon decay and cooldown from 200*F to 140*F, Tnis concition requires either 1,100 gallons of 7000 ppm' borated water # rom the beric acid storage tanks or 7,113 gallons of 2000 ppm borated water frem the RWST.
As listed below, the required indicated levels f:' the boric acid storage-tanks and tre RWST include allowances for required /ans'ytical-volume, unusaole olume, measurement uncertainties (which include inst-:, ment ~ error and tank v
tolerances, as applicable), ;,::: ;^:fi p ;ti r m n n at $ and other recuired volume.
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18493 Tank PODE5 Ind,"
Unusable Required Measurement (wwe@0ther Level volume Volume-Uncertainty LGeaLi.cc(gal _)
(gal)-
(gal)
(gal T C '
RW5T 5,6
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.l. N 7,113 4% of scan Eu A 1,2,3,4 95%
45,49 70,702 4% of_ span
- N/A -357,535"'
Boric 5,6 10%
3,221 1.100-6% of-span
'N/A=
N/A Acid 5,6 20%
3,221-1.,100--
6% of. span-3,679
-N/A
-Storage (gravity _ feed) 6% of span N/A.
Tank _
1,2,3,4 50%
3,221 15,700 N/A The OPERABILITY _of one Boron Injection System during REFUELING ensures that tnis system is ava'ilable for reactivity control while.in MODE 6.
"Accitional volume required to meet Specification 3.5.4 COMANCHE DEAK - UNIT 1 B 3/4 1-3
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REFUELING WATER STORAGE TANK a
BASES TECHNICAL SPECIFICATION (3/4.5;4) k.
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AMENDMENT- /: REVISION 13 DETAILED DESCRIPTION LPage;li 4u Prefix Page (n-gnM)
Stegg Descrintion 83/4'5 2,-
3 Corrects the actual-number in the Bases ~Section 3/4.5,4 for_the required water volume of.the Refueling-Water Storage _ Tank ~(RWST) from 428.437-- gallons:to j
428.237_ gallons.
Revision-This change will correct-the information in the bases-
- n section to make the numbers-for the required _ water-volume in the RWST= reflect the numbers-in the Technical Specifications-Bases Section 3/4.1.2.
Change Request' Number
- -TS 92 35.
Commitment Register' Number :_
,i Related SER :
SSER :
SER/SSER Impact
- No r
9 4
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. to TXX-42613 Par;e 3 of 3 EMEcGENC
- RE :: CLING 5 STEMS BASES EC:5 SLE5 5' EMS (Continued) to be inoceratie celow 350 F provides assurance that a mass addition ;ressure transier.t can ce relieved by the operation of a single PORV, The requirement to remove power from certain valve operators is in accaro-ante with Brancn Technical Position IC5B-19 for valves that fail to meet single failure considerations.
Power is removed via key-lock switches on the control board.
The Surveillance Requirements provided to ensure OPERABILITY of eacn
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component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.
Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECC5 flows will be maintained in the event of a LOCA.
Maintenance of proper flow resistance and pressure drop in the piping system to eacn injection point is necessary to:
(1) prevent total pump flow from exceeding-runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accorcance.'tn the assumptions used in the ECC5-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECC5-LOCA analyses.
3/4.5.a REFUELING WATER STORAGE TANK Tne CPERABILITY of the refueling water storage ti K (RWST) as part of tne ECC5 ensures that a sufficient supply of borated water is available fcr injec-tion by the ECC5 in the event of a LOCA.
The limits on RWST minimum volume and coron concentration ensure that:
(1) sufficient water is available within containment to permit recirculation cooling flow to the core, (2) for snail treax LOCA and steam line breaks, the reactor will remain subtritical in the cola conoition following mixing of the RWST and the RCS water volumes witn all control rods inserted except for the most react!ve control assembly, (3) for
'arge breas.:CAs the reactor will remain subc-itical in the cold ccncition following mixing of the RWST and the RCS water volumes with all shutcown and control rods fully withdrawn, and (4) sufficient time is available for the operator to take manual action and complete switchover of ECCS and containment N
spray suction to the containment sump without emptying the RWST or losing suction.
The required indicated level includes a 4 percent measurement uncertainty, an unusable volume of 45,494 gallons and a required water volume of C i. Q gallons.
g The limits on indicated water volume and boron concentration of tne RW5T also ensure a long-term pH value of between 8.5 and 10.5 for the solution recirculated within containment after a LOCA.
This pH band minimizes tne evolution of iocine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
COMANCHE EEAK - UNIT 1 B 3/4 5-2
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- to'TXX 92613
- ,4 CONDENSATE STORAGE TANK' BASES' TECHNICAL SPECIFICATIONS (3/4.7.1.3) i ~,
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CPSES - TECHNICAL SPECIFICAff0ds ! 'a5 ) to TXX-92613 AMENDHENT-/ REVISION 13
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DETAILED DESCRIPVION Pago 1
. Pace 2 of 3 Prefix Page
-(31 amended)
Sraup DescriptioO B3/4 7-3 3
Revises the values for the Condensate Storage Tank (CST) unusable volume from 12,000 gallons to 12,900 gallons and required usable volume from 250,000 gallons to 249,100 gallons in Section 3/4,7.1.3.-
Revision The calculations used to determine the critical depth-for-vortex formation and the CST usable volume were revised to reflect a more conservative approach utilizing design guidelines derived from actual installations in lieu of an analytical model.
The resultant reduction in usable CST-volume is within the margin used in establishing Technical Specification Section 3,7.1.3 limitations of 53% minimum CST water level and is therefore acceptable.
Change Request Number
- TS-91-19.
Commitment Register Humber :
Related SER :
SSER :
SER/SSER Impact
- No i
,Euclosure 3 to TXX-92613 Page 3 o{ 3 DLANT i<5?Eus BASES 3'4.7.1.2 AUXILIARY FEE 0 WATER SiSTEM ine CPERABIL! n of the Auxiliary Feedwater System ensures that the Deactor Ccolaat System can be cooled do.n to less than 350 F from normal ecerating corcitions in the event of a total loss-of offsite power.
Each electric motor-driven auxiliary feedwater pumo is capable of celi 4er-ing a total feed ater flow of 430 gpm to two steam generators at a pressure of 1221 psig to the entrance of the steam generators.
The steam-driven auxiliary
'eedwater pump is capable of delivering a total feedwater flow of 860 gpm to four steam generators at a pressure of 1221 psig to the entrance of the_ steam generators, This capacity is sufficient to ensure that adequate feed ater flow is availaole to remove decay heat and reduce the Reactor Coolant System temp-erature to less than 350'F '. hen the Residual Heat Removal System may be placed into operation.
The Auxiliary Feedwater System is capable of delivering a total feedwater flow of 430 gpm at a pressure of 1221 psig to the entrance of at least two steam generators wnile allowing for:
(1) any possible spillage through the design worst case break of the main feedwater line; (2) the design worst case single f ailure; and (3) recirculation flow.
This capacity is sufficient to ensure that adeouate feedwater flow is available to remove decay heat anc reduce Reactor Coolan System temoerature to less than 350'F at which point the Residual Heat Removal System may be placed in operation.
The test flow for the steam-criven auxiliary feecwater pump at a preisure of greater tnan or equal to 1450 osid ensures tnis capacility.
The auxiliary feec ater flow path is a passive f':w path based on the fact that valve actuation is not requirec in order to supp' flow to the steam generators.
The automatic valves tested in the flow path are the Feed ater Solit Flow Bypass onich are required to be shut uDon initiation of the Auxiliary Feec ater System to meet the requirements of the accident analysis, Both s*eam su;olies for the turbine-driven auxiliary feecwater cump must ce OPERABLE in order to meet the design bases for the complete range of accident analyses.
The allowed outage time for one inoperable steam source is consistent with the lower procacility of the worst case steam or feedwater line creak accident.
3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offsite power or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at HOT STANDBY followed by a cooldown to 350 F at a rate of 50 F/hr for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
The contained water volume limit includes an allowance for water not usable because of tank discharge line loca-tion or other physical characteristics.
The required indicated lav 1 includes a 3.5-percent measurement uncertainty, an unusable volume of s-ew s llons and a a
required usable volume of C '
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NUREG-0737, Item II.E.1.1 requires o veckup source to the CST which is the CPSES Station Service Water System, whicn can be manually cligned, if required in lieu of CST minimum water volume.
COMANCHE PEAK - UNIT 1 B 3/4 7-2
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