ML20072T828
| ML20072T828 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/22/1983 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20072T823 | List: |
| References | |
| NUDOCS 8304080343 | |
| Download: ML20072T828 (14) | |
Text
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HYDROGEtt A?tALY2ERS
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LIMITING CONDIT10ti F01 0PERATION -
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3.6.5.) Two independent containrcent hydrogen analyzers shall be-0PERABLEF. APPLICABILITY: MODES 1'and 2. ACTION:
- With one hydrogen inalf :ce inoperable, restore- the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STANDSY within the next 6 hours.
SURVEILL_ANCE RE1JJREMENLS ,
- 4. 6. 5.1 Each hydrogen analyzer shall be demons'trated .0PERABLE 'a't leas t once per 92 days on a STAGGERED TEST BASIS by performing .a CHANilEL CALIBRATION.
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*Dwie3 ? l 4 any 4given pts fr time ,t by *LeM/41, one- hydr' ogen analyzer may be made,inoperabl'e' f at
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not applicable to this requirement.During this time, Specification ~ 3.0.4 is . d-lCALVERT. CLIFFS 1- UNIT 2' 3/4 6-265 [AmendmentNo 2,
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l -m I V 1/4.6.5 CC!tEUST!BLE CAS CONTROL liYDROJEtt AtlALYZER$ , LIMITING CONDITIO:t FOR OPERATION - 3.6.5.1 Two independent contair. cent hydrogen analyzers shall be OPERABLE *. APPticABILITY: MODES 1 and 2. ACTION: ' With one hydrogen analyzer inoparable, restore the inoperabic analyzer to OPEPABLE status witnin 30 days or be in at least HOT STAN08Y within the next 6 hours. SURVEILLANCE REQUIREMENTS # e we
- 4. 6. 5.1 Each hycrogen analyzer shall be de.uns'trated OPERABLE 'at leas t once per 92 days on a STAGGERED TEST BASIS by performing a CHANtiEL CALIBRATf 0tl.
*ik.qwpaj k%iuJW39fC, one hydrogen analyzer may be made inoperable, at.
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'E" MINIMUM TOTAL N0. CilANNELS CHANNELS APPLICABLE '
P FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
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~? 1. . Manual Reactor Trip 2 1 2 1, 2 and
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- 2. - Power Level -- liigh ,
4 2 .3(f) 1, 2 2f
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- 5. Containment Pressure - High 4' 2 3 1, 2 2f g
- 6. Steam Generator Pressure - Low 4/SG 2(b)/SG 3/SG 1, 2 2f- @
t0 4
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'[ 8. Axial Flux Offset 4 ,
2(c) 3 1 2f 9 3. Thermal targin/ Low Pressure '4 2(a) 3 1,2(e) 2f
- b. Steam Generator Pressure
. Difference,- High 4 2(a) 3 1, 2 (e) 2f 10.. Loss of TI!$fr.;
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, TOTAL NO. CllANNELS CHANNELS APPLICABLE
- F FilNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE H0 DES ACTION-1 - 1. _ Manual I Reactor Trip - 2_ 1 2 .1, 2 and
- 1 -
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C . O c.. TABLE 4.3-1 9 E REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9 O CHANNEL MODES IN WHICH M CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE
- 5 FUtiCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED h 1. Manual Reactor Trip li. A. ii.A. . S/U(i) li . A . ,
- 2. Power Level - High
~
- a. Nuclear Power S D(2),tl(3),Q(5) M 1, 2
- b. AT Power S D(4),R H 1
- 3. Reactor Coolant Flcw - Lcw S R H 1, 2 h E
- 4. Pressurizer Pressure - High 5 R H 1, 2 q w a D Containment Pressure - High H 1, 2 4
- 5. S R
" D E 6. Steam Generator Pressure - Low 5 R H 1, 2 I
- 7. Steam Generator Water Level - Low 5 R H 1, 2 3
- 8. Axial Flux Offset S R H 1 4 21 9.a. Thermal !!argin/Lew Pressure S R H 1, 2 9 b. Steam Generator Pressure Difference -
E High S R 11 1, 2 S' LCAb 5 ,. 10. Loss of To. Licc--::ydreslic fistd n [- 5 .ressurc - Lcx N.A. N.A. S/U(1) N.A. a
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- ClIANNEL H0 DES IN WillCH
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CilAfiNEL FUNCTIONAL SURVEILLANCE E CILAH!iEL TEST- ' REQUIRED CllECK CAllBRATION JU!iCTIONAL UNIT fl. A. fi. A. S/U(1) H.A. , g 1. Manual Reactor Trip L G 2. Power Level - liigh i -- , . , , S. 0(2) ,f1(3),Q(5) M .1, . 2 . ~ [ a.: Nuclear Power
- b. t.T. Power .- 5 D(4),R M 1
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- 4. Pressurizer' Pressure - High- .S R
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- LIMI IsG SAFETY-iYSTEC SETTil;GS -
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M - LT6e Thermel Margin /Lew Fressure trio tctroints Include allowances for j ; et;.i::eet res;crce tir-e ntasurt.U.: un:critintics, processing errcr and a
; ; furtt.er ailcear.ce cf c0 pria to cc pensate for the tine celay as:cciatec witn
. : f rt vidin; ef fet: ice icr-ir.t tien of tr,e Occurrenct that exhihitt the cost V ' ' '
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.I gzj y t r i e 5 t t .s D.. g r- T r a r i s n t J r c. en t i c t. Trip Function ( AsciptQ The ASGIFIF utilizes stean,g(.nerator recssure inputs to the TM/LP.
!! cliculator, which causer a rqattor trip when the difference in pre:surc
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a ! between the t,to steam generator 6 exc'eeds the trip setpoint. The ASGTFTF is desicned to provide a reactor trip for these Anticipate.d Operational _0ccurrences associated with recendary systcm malfuncticns which re5 ult' in' asymmetric primary loop coolant teT.peretures. The most limiting event is the loss of load to_ene t um gentrc to.r u .( d by a single 14in !tten Isc>lat to'n Yalve closure. The equipment trip setpoint and allowable values are calculated to account-for instrument uncertainties, and will ensure a trip at or before reaching the cnalysis setpoint. - Loss of Icd ine Iond , Load
-{ A Loss of Tu-binc trip causes a direct reactor trip when operating ~ above 15% of RATED THERMAL POWER. This_ trip'provides turbine. protection : reduces-the sevcrity of thc ensuing transient and helps avoid the lifting o'f the twin -
stcom line saf ety volves dur ing;the en:.ulng trah:. lent,' thus extending the service life of these valves. No credit was takenJin the accident analyses
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for operation of this trip. ,lts functional capabilitytet thi 3picificd' trip
; ct ti ,; is req need-tc cn5;n:c thi cicrcl.1 reliabilit.i ef tha leec.ter Tietec-t'.:n !yttem. 'in required to- enhance overall plant eqtaipment ' service : life and -
reliability. ~ ?' ' Rate'of-Chance of Power-Hi'ah .[ a The Rate of- Change of: Power-High trip is provided to' protect-the.' core: during startup cperations'snd its use serves asia backup'.toithe administra-- - tively enforced s tartup.-rate limit. _ Its trip setpoint does not correspond-to. a Sifety- Limit. and no- credit was taken~ in - the accident analyses for.-
'j c;eration -of :this trip. :Its fur.ctienal capibilityDat the..specified trip' settir.g is required tc_ enharice the' overall reliability ofjthe Reactor i Pre tection =Sys te ..
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, LIMITING SAFETY SYSTEM SETTINGS I
l b 3ASES The Thermal Margin /Lew Pressure trip setpoints include allowances for equipment response time, measurement uncertainties, processing error and a further allowance of 40 psia to compensate for the time delay associated with providing offective termination of the occurrence that exhibits the most rapid decrease in margin to the safety limit. l Ap n1etric Steam Generator Transient Protection Trip Function (ASGTPTF1 The ASGTPTF utilizes steam generator pressure inputs to the TM/LD calculator, which causes a reactor trip when the di fference in pressure bet'.seen the two steam generators excoeds the trip setpoint. The ASGTPTF is designed ta provide a reactor trip for those Anticipated Operational Occurrences associated with secondary systen malfunctions which result in aspe,;etric pr mary loop cool ant temperatures. The most limiting even. is the loss uf !cid to one steam generator caused by a sincle Main Steam l Isolation vai n closure. The c;uionent trip setpoint and allowable values are calculated to account for ins trument ur. certainties, and will ensure a tri? at or before reaching tne aral fsis setpoint. Les s o f b i e load Loa A Loss of Tc;d ins trip causes a direct reactor trip when operating above ISS of RATED THERMAL F0WER. This trip provides turbine protection, reduces tne seserity of the ensuing transient and helps avoid the lif ting. of the main steam line safety valves during the ensuing transient, thus extending the service life of these valves. No credit was taken in the accident analyses for operation of this trip. Its functional capability a t-the--wee-iH+tm-setting-it-required -to-ennonce-theverrH reHeMMty-ef-the-Reeeter-Prot etierr-Sys tem. is required to enhance overall plant equipment service life and reliability. t Rate of Change of Power-High f l The Rate of Change of Power-Hich trip is provided to protect the core during startup operations and its use serves as a cackup to the administra-tively enforced startup rate limit. Its t' rip setpoint does not correspond to a Safety Limit and no credit was taken in the accident analyses for operation of this trip. Its functional capability at the specified trip setting is required to ennance the overall reliability of the Reactor Protection System.
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CALVERT CLIFFS - UNIT 2 B 2-7 hiendment No. S, I3, 3I, Ae
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