Text

Proposed Tech Specs Section 3.3 Re Instrumentation
	ML20196B881
Person / Time
Site:	Comanche Peak
Issue date:	10/30/1998
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20196B866	List: ML20196B881; TXX-9823, Forwards Response to RAI Re Section 3.3 Instrumentation of Proposed TS Changes.Addl Changes to Converted Specification 3.3.5 to Address Actuation Logic & Logic Relays Will Be Provided in Subsequent Submittal;
References
	NUDOCS 9812010205
	Download: ML20196B881 (400)
	v • d • e

ESFAS Instrumentation B 3.3.2 BASES l

APPLICABLE c. Containment Sorav Containment Pressure (continued) l SAFETY ANALYSES, I LCO, and requirc cr,t-s- Additional redundancy is warranted l APPLICABILITY because thi nction is energize to trip. Containment . l 3

Pressur Hig Diigh liighj must be OPERABLE in --

0-3.3 G 1 l HODES 1 ,

nd 3 when there is sufficient energy in the primary and secondary sides to pressurize the containment following a pipe break. In H0 DES 4, 5, and 6, there is insufficient energy in the primary and secondary sides to pressurize the containment and reach the Containment Pressure-High 3 Gish :igh) setpoints.

i

3. Containment Isolation ;

containment Isolation provides isolation of the containment atmosphere, and all process systems that penetrate containment. l from the environment. This Function is necessary to prevent or limit the release of radioactivity to the environment in the event of a large break LOCA. j J

There are two separate Containment Isolation signals, Phase A and Phase B. Phase A isolation isolates all automatically ,

isolable process lines, except component cooling water (CCW) to !

the reactor coolant pumps, at a relatively low containment ;

pressure indicative of primary or secondary system leaks. For l these types of events, forced circulation cooling using the l i

reactor coolant pumps (RCPs) and SGs is the preferred (but not required) method of decay heat removal. Since CCW is required to support RCP operation, not isolating CCW on the low pressure j Phase A signal enhances unit safety by allowing operators to !

use forced RCS circulation to cool the unit. Isolating CCW on i the low pressure signal may force the use of feed and bleed cooling, which could prove more difficult to control. i l

Phase A containment isolation is actuated automatically by SI, or manually via the automatic actuation logic. All process ;

l lines penetrating containment, with the exception of CCW, are isolated. CCW is not isolated at this time to permit continued '

operation of the RCPs with cooling water flow to the thermal barrier heat exchangers-end, motor air eH)+1 coolers,, and upper _andilower; bearing coolers. All process lines not 9812010205 98112f PDR ADOCK 05000445 P PDR (continued)

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.- ~ . . - - _. .- -_- - . - _- .-. -

ESFAS Instrumentation ,

B 3.3.2 BASES 4

J and cause a cooldown of the primary system. The Steam Line Isolation Function is required in MODES 2 and 3 unless all MSIVs andithejylassociatedr ^ ;

Jet o.3,3 3 1 ll <

" isphitiongahes are clos Ais 4

_ I o-2-07 l

theegger%'Lt!DM(t3ag;M NX1aot ;

retyttpe.RttLW1EEEBL.WSIn MODES 4, 5. and 6, there is insufficient energy in the RCS and SGs to experience an SLB 1 or other accident releasing significant quantities of energy.

1

c. Steam Line Isolation-Containment Pressure-Hiah 2 l r

This Function actuates closure of the MSIVs in the event of l

a LOCA or an SLB inside containment to maintain at least one unfaulted SG as a heat sink for the reactor, and to limit the mass and energy release to containment. The l

transmitters (d/p cells) are located outside containment with the sensing line (high pressure side of the transmitter) located inside containment. Containment Pressure-High 2 provides no input to any control i functions. Thus, three OPERABLE channels are sufficient to satisfy protective requirements with two-out of three

' logic. ::cw;n r. for enhanced reli;bility, this Function w;s designed with four thenn;12 end ; two-cut-of four legie: The transmitters and electronics are located outside of containment. Thus, they will not experience any adverse environmental conditions, and the Trip Setpoint reflects only steady state instrument uncertainties.

Containment Pressure-High 2 must be OPERABLE in MODES 1, 2, and 3, when there is sufficient energy in 1

l the primary and secondary side to pressurize the containment following a pipe break. This would cause a significant increase in the containment pressure, thus allowing detection and closure of the MSIVs. The Steam Line Isolation Function remains OPERABLE in MODES 2 and 3 unless all MSIVs are closed andideactjyated. In l o-3.3 s-1 M00E 3 1helincrease3 nicontainment[ptessutO following;a PiPelbreaKhould:pecuripverla;telatiye]y2ongtime Period;such;that;manuallactionicouldleasonab]yibe; expected to;proyide'; protection:and,ESFAS1 Fun _ction14Je~need; hot:be OPERABLE 2 In MODES 47 5 and 6, there is not enough energy in the primary and secondary sides to pressurize the containment to the Containment Pressure-High 2 setpoint.

- (continued)

CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-87 10B088

ESFAS Instrumentation B 3.3.2 i BASES

d. Steam Line Isolation-Steam Line Pressure (1) Steam Line Pressure-Low Steam Line Pressure-Low provides closure of the l MSIVs in the event of an SLB to maintain at least one i unfaulted SG as a heat sink for the reactor, and to limit the mass and energy release to containment.

This Function provides closure of the MSIVs in the event of a feed line break to ensure a supply of steam ,

for the turbine driven AFW pump. Steam Line l Pressure-Low was discussed previously under SI :

Function 1.e.l. l Steam Line Pressure-Low Function must be OPERABLE in t

H0 DES 1, 2. and 3 (above P 11), with any main steam l l valve open, when a secondary side break or stuck open valve could result in the rapid depressurization of f the steam lines. This signal may be manually l blocked by the operator below the P 11 setpoint.

0 3.3 63 ILnotiblockedibeloKP317 thelunctioq1most(be l OfERABLE;*Selow P 11[.7,nblocked, an inside

containment SB will be terminated by automatic actuation via Containment Pressure-High 2. Stuck valve transients and outside containment SLBs will be terminated by the Steam Line Pressure-Negative

> Rate-High signal for Steam Line Isolation (1) Steam Line Pressure-Low (continued) below P 11 when SI has been manually blocked.

The Steam Line Isolation Function is required in MODES 2 and 3 unless all MSIVs are clogs ;

g activat:ey. Inis function is not requiredl o be opt.KAt$LL in MODES 4, 5, and 6 because there is insufficient energy in the secondary side of the unit to hcvc cn cccidcat. beloficoncernj (2) Steam Line Pressure-Necative Rate-Hiah Steam Line Pressure-Negative Rate-High provides closure of the MSIVs for an SLB when less than the P 11 j setpoint to maintain at least one unfaulted SG as 4 l

l I

(continued)

CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-88 10B088

ESFAS Instrumentation B 3.3.2 3

BASES l

condM(onsthe; actuation 3ogicilslab]e;toyithstandiboth ; an isept1DEnv2hEcontr0DFEtem24hicitWLthenfrequts '

aljigtRcktgMpctustjanaandia _is%g}elfRtWR1n i I

theJahnsfusesM3! addles 12!aamolect912!sttiss acesinguagglGWhDRetamMhmWalglREggelIluRQte !

rs!s!NelLRLJ!Nta!Dagge;tegumanists3!th,ggd6gtt_W3 brae !

W I i

The transmitters (d/p cells) are located inside ]

containment. However, the events that this Function I protects against cannot cause a severe environment in !

containment. Therefore, the Trip Setpoint reflects only {

steady state instrument uncertainties. !

c. Turbine Trio and Feedwater Isolation-Safety Iniection I

Turbine Trip and Feedwater Isolation are also initiated by 1 all Functions that initiate SI. The Feedwater Isolation Function requirements for these Functions are the same as the requirements for their SI function. Therefore, the requirements are not repeated in Table 3.3.21. Instead Function 1, SI, is referenced for all initiating functions and requirements. ;

1 Turbine Trip and Feedwater Isolation Functions must be OPERABLE in MODES 1 and end , cept when all HFIVs. l MFRVfusin;feedwagtontro nya1Wes,ana associateo Lypse

<TrfliEh are closedddfdideactivatethorssolatedJy;a closed;manuahvalye when the MFW System is in operation.

end the turbin; ;;ncreter ;;y bc in epcretion. InMODEfj, 4, 5, and 6, the "Pl Syste; ;nd th; turbinc ;;ncr;ter ;rc not in ;crvice and this Function is not required to be OPERABLE.

(continued)

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ESFAS Instrumentetion B 3.3.2 BASES

. SI:

. Containment Spray: j Phase A Isolation:

. Phase B Isolation; and

. SemifAutomatic Switchover to Containment Sump.

This action addresses the train orientation of the SSPS and the master and slave relays. If one train is inoperable, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months are allowed to restore the train to OPERABLE status. The specified Completion Time is reasonable considering that there is another train OPERABLE, and the low probability of an event occurring during this interval. If the train cannot be restored to OPERABLE status, the unit must be placed in a H0DE in which the LCO does not apply. This is done by placing the unit in at least H0DE 3 within an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months total time) and in MODE 5 within an additional 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months (42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months total time). The Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

The Required Actions are modified a Note that alle one train to be bypassed for up to ours for surveillance N 0-3.3 G-1 testing, provided the other tr is OPERABLE. This allowance is based on the reliability analysis assumption of WCAP 10271-P-A (Ref. 6) that 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is the average time required to perform channel surveillance.

D.1. D.2.1. and D.2.2 Condition D applies to:

. Containment Pressure-High 1:

. Pressurizer Pressure-Low: (two, threc. ;nd four loop units);

Steam Line Pressure-Low:

St;;;. Linc Differential Pressurc-lligh; (continued)

CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-108 10/3088

I

! ESFAS Instrumentation

. B 3.3.2 BASES l

i The Required Actions are modified by a Note that allows the

! inoperable channel [orJnothetichannel to be bypassed for up l l

t ours for surveillance testing of other channels. The i hours allowed to restore the channel to OPERABLE status or ;

to place the inoperable channel in the tripped condition, and the 1 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months allowed for testing, are justified in Reference 6. ]

l E.1. E.2.1. and E.2.2 )

l Condition E applies to: j

. Containment Spray Containment Pressure-High 3 0'igh 'ligh)

(twc, thicc, cr.d four leap ur.its); and

. Containment Phase B Isolation Containment Pressure- High 3 ;

11 i v . J, ,L, , 11. J. ,L,i, .

l None of these signals has input to a control function. Thus.

l two out-of three logic is necessary to meet acceptable protective

! requirements. However, a two out of three design would require

! tripping a failed channel. This is undesirable because a single

, failure would then cause spurious containment spray initiation. I f Spurious spray actuation is undesirable because of the cleanup problems presented. Therefore, these channels are designed with l two out-of four logic so that a failed channel may be bypassed rather than tripped. Note that one channel may be bypassed and still satisfy the single failure criterion. Furthermore, with l

one channel bypassed, a single instrumentation channel failure l

will not spuriously initiate containment spray.

To avoid the inadvertent actuation of containment spray and l Phase B containment isolation, the inoperable channel should not be placed in the tripped condition. Instead it is bypassed.

Restoring the channel to OPERABLE status, or placing the

! inoperable channel in the bypass condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , is sufficient to assure that the Function remains OPERABLE and minimizes the time that the Function may be in a partial trip condition (assuming the inoperable channel has failed high). The completion Time is further justified based on the low probability of an event occurring during this interval. Failure to res 6 a the inoperable channel to OPERABLE status, or place it in 6 (continued)

, CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-110 10B088 l

(

ESFAS Instrumentation B 3.3.2 BASES bypassed condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , requires the unit be placed in MODE 3 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and H0DE 4 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. In MODE 4. these Functions are no longer required OPERABLE.

The Required Actions are modified by a Note at allows one ~

additional channel to be bypassed for up t ours for 0 3.3-G 1 l surveillance testing. Placing a second ch 1 in the j bypass condition for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for testing purposes is acceptable based on the results of Reference 6.

F.1. F.2.1. and F.2.2 Condition F applies to: i

)

. Manual Initiation of Steam Line Isolation:

Loss of Offsite Power; and

Auxiliary Fecd.etcr Pu;p Suction Transfer en Section Pr;ssur; L;w. ;nd

. P-4 Interlock.

For the Manual Initiation and the P 4 Interlock Functions, this action addresses the train orientation of the SSPS. For the Loss of Offsite Power Function, this action recognizes the lack of manual trip provision for a failed channel. For th; Ard Syst;;

pu;p suction tr;nsfer chenacis, this ;; tion r;;;g.iccs that placing ; feil;d chenn;l in trip during ep;r; tion is not n;;;sserily ; ;;nscrvativ; ;; tion. Spurious trip of this function ;;;1d slign th; APd Syst;; to ; sour;; that is not

.....- . m., mor... . _ wo. ,ing pu;p suction. If a train or i l

channel is inoperable 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is allowed to return it to OPERABLE status. The specified Completion Time is reasonable considering the nature of these Functions, the available redundancy, and the low probability of an event occurring during this interval. If the Function cannot be returned to OPERABLE status, the unit must be placed in MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (continued)

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ESFAS Instrumentation B 3.3.2 BASES and H0DE 4 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power in an orderly manner and without challenging unit systems. In MODE 4, the unit does not have any analyzed transients or conditions that require the explicit use of the protection functions noted above.

G.I. G.2.1 and G.2.2 Condition G applies to the automatic actuation logic and actuation relays for the Steam Line Isolatior, [. turbinc trip cr.d fcc iater i;clatsen} and AFW actuation Functions.

The action addresses the train orientation of the SSPS and the master and slave relays for these functions. If one train is inoperable, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months are allowed to restore the train to OPERABLE status. The Completion Time for restoring a train to OPERABLE status is reasonable considering that there is another train OPERABLE, and the low probability of an event occurring during this interval. If the train cannot be returned to OPERABLE status, the unit must be brought to MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 4 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

Placing the unit in MODE 4 removes all requirements for .

OPERABILITY of the protection channels and actuation functions.

In this H0DE, the unit does not have analyzed transients or conditions that require the explicit use of the protection functions noted above.

The Required Actions are modift by a Note that allows one train to be bypassed for up to ours for surveillance 0-3.3 G 1 testing provided the other tra is OPERABLE. This allowance is based on the reliability analysis (Ref. 6) assumption that 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is the average time required to perform channel surveillance.

H.1 and H.2 Condition H applies to the automatic actuation logic and actuation relays for the Turbine Trip and Feedwster Isolation Function.

(continued)

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- _ - . _ . - - - . . - - _ - - - - . - - - - - - . - - --.- _.~---

ESFAS Instrumentation B 3.3.2 l

BASES ,

SR 3.3.2.8 SR 3.3.2.8 is the performance of a TADOT. This test is a check of the Manual Actuation Functions and AFW pump start CA 3.3-005 on trip of all MFW pumps.iDe~SgfptyJgjecgjepMfsha31 N

uuteengeRatetBunatFiggactalgasmggspecast !

l a E m 3bpen W D RepkCA G N U JMC4he m;ggangg@ It is performed ;

every B months. Cech " anal A;t ation functi;n is t sted up Q 3.3-G 1 l to. a d includia;. tra a ster rel;y Gils. Insac l insterc;s. tra tat ialais station of the end ivi;; i

,....m..... .... .7 .s . .. .,. The Frequency is adequate, based on industry operating experience and is consistent with the typical refueling cycle. The SR is modified by a Note that excludes verification of setpoints during the TAD 0T for manual initiation Functions. The manual initiation Functions have no associated setpoints.

SR 3.3.2.9 SR 3.3.2.9 is the performance of a CHANNEL CALIBRATION.

A CHANNEL CALIBRATION is performed every 18 months, or approximately at tvery refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The ,

test verifies that the channel responds to measured parameter l within the necessary range and accuracy.

CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit specific setpoint methodology.-The differ a n bet' a n th; current "a f;;nd" alua and th; pr;;ieus tat "a 1;ft" alua est b; acistat with th; drift alicaan s ud in th; atp; int .;thed;10;y.

The Frequency of 18 months is based on the assumption of an 0-3.3 G 1 month calibration interval in the determination of e magnitude of equipment drift in the setpoint methodology.

This SR is modified by a Note stating that this test should include verification that the time constants are adjusted to the prescribed values where applicable. WhenevetIanJD l 1s1 replaced;tnfunctjansid;(3)Ltheinext~tequited, CHANNEL CALIBRAH0DfitheRDsitsiaccomplishedMadnplace3 toss caljbratjonjusticomparesiotherisenstnOlesent_sMthithe tecenti r installe o lament; (continued)

B 3.3-120 10/30/98 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

ESFAS Instrumentation B 3.3.2 I l BASES

.. .. _,_,c - ,-

-w _ .

-_._-..; ..q- : e_ =~.a_r-_ux

- . ry.. g.m- 5mu.-muume .~_u=

-_ . ~. nam ur- g .

M ianst w yor semitaansampassessenusegastmetJtppseseittees ud!K M M _ N X ape g genal 6JumMWMe3kttmadverse.1y atBurlema!!a'SNut".JMessenL~electricatwitamrrdoes notmeerummse:MemddedM!!EMrts3:enditorirepairiare ofithela!!e2tnelandmDle Eppegitic3nsponentsMdentJnedijn ttuf3CAPleay;beLreplacedMthout2MifjeatjorGtettJng EOne example)hete; response; time;couldj:elaffectedfjsleplacing the sensiinglassembhgoffaittansajtter; ESF RESPONSE TIME tests"are verificatica is performed on an

~

0 1.1 4 18monthSTAGGEREDTE3TBASIS. The3estingIMEgin;gj q she1X1sludelat11 east;oneittafelsuchithat"bottEtrainslare testedlig "j; O tileastfonce:per136Laonths] Testing of the final actuation devices, which make up the bulk of the response time, is included in the testing mumitesting of each channel. The final actuation device in one train is tested with each channel. Therefore. staggered testing results in response time verification of these devices every 18 months. The 18 month Frequency is consistent with the typical refueling cycle and is based on unit operating experience, which shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

This SR is modified by a Note that clarifies that the turbine driven AFW pump is tested within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 0 3.3-G 1 reachin 53 psig in the SGs.

l l

l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-121a 10/30/98 l

i i

Remote Shutdown System '

B 3.3.4 BASES- .

l The Frequency of 31 days is based upon operating experience which i demonstrates that channel failure is rare. The CHANNEL CHECK i supplements less formal, but more frequent, checks of channels '

during normal operational use of the displays associated with the l LC0 required channels. l SR 3.3.4.2 SR 3.3.4.2 verifies each required Remote Shutdown System NSP U'3'3 #

l powerJand control circuit and transfer switch performs the

intended function. This verification is performed from the i

remete Hot Shutdown Panel and locally, as appropriate. Operation of the equipment from the remote shutdown panel is not necessary.

l The Surveillance can be satisfied by performance of a continuity check. This will ensure that if the control room becomes inaccessible, the unit can be placed and maintained in MODE 3 l from the remote shutdown panel and the local control stations. ]

The 18 month Frequency is based on the need to perform this l

' Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the l Surveillance were performed with the reactor at power. (However, !

this Surveillance is not required to be performed only during a unit outage.) Operating experience demonstrates that remote shutdown control channels us 11y pass the Surveillance test when performed at th nth Frequency w

SB_ f 3.4.3 ChnNNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. idheneversaisensig; element 11s;teplaceddthe TR-3.3 004 nextirequitgi d;CHlWlE134LIBRAllMMithaltes1_ stance j temperatuteldetectors3BIDLisensors.X4ccomp]Lshed;by'_an l injplace cross:calibrati.on;that; compares 1the;otheMsensing ;

el_ements M th" "recent]ylinstajled 'sensingMementEThe Frequency of nths is based upon operating experience l 0 3.3-G 1 and consistency ith the typical industry refueling cycle.

SR 3.3.4.4 ,

SR 3.3.4.4 is the pcrier=xc of ; TA00T cvcry 10 maths. This l i

l tcst should verify the OPERASILI"I of the rccctor trip brc;kcrs (RTSs' open ;nd closed indicatica on the rcate ;hutdc.;n p;nci.

l

by ;ctuating the RTSs. The Trcqucxy is based upon opcr; ting l

f (continued) l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-1S1 102088

LOP DG Start Instrumentation B 3.3.5 BASES c

SR 3.3.5.2 SR 3.3.5.2 is the performance of a TADOT. This test is performed cycry 31 day; .e._ gJ ;pl 4jatter,J3o;engry inj$oM33dheQp3pqsj!rliO2:4xtetslandyls.ust 0-3.3 4 ,

peM33rsv$eusiSEDys. The test checks trip devices that provide actuation signals directly, bypassing the analog process control equipment. For thc;c tcst;. the relay Trip Sctpoint; er; verified end adjusted ;; raccs;;ry. The Frequency is based on the known reliability of the relays and controls and ,

the multichannel redundancy available, and has been shown to be acceptable through operating experience.

SR 3.3.5.3 ,

SR 3.3.5.3 is the performance of a CHANNEL CALIBRATION.

L The ;ctpoints ;; wcli es the rc;ponse to a less of voltogc :nd ; l dcgreded voltogc test. :h:11 include a singic point verification l

that the trip occurs within the required ti;;c dclay as shown ifi Rciercacc 1. !

A CHANNEL CALIBRATION is performed ever 18 nths, or apprcximately at every refueling. CHANN CALIBRATION is a complete check of the instrument loop, including the sensor.

The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. o.3.3.a.1 The Frequency o nths is based on operating experience and consistency the typical industry refueling cycle and is justified by the assumption of an E183 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

SR'3:3:5'4 SR.'A 3.5 ;;43sjheL performancef of, the fequi red.fesponse .. time verjfication:(see;also;SR 3;3.2,10)1every118'. months;on:a STAGGERED; TEST; BASIS; onithosef functionsiwith1 time].inits:provided in;thelechnica); Requitenent.s11anual TEEach; verification :shall inc] ude:at2 east'one;traj nisuchithatiboth: trains ~are:Verifiediat least1bnce;perl[361 months.

CPSESMarkup ofNUREG-1431 Bases -!TS3.3 B 3.3-160 10B0/98

1 Containment Purgc and Sxhaust Ventilation Isolation instrumentation j B 3.3.6 l

l l

l BASES (continued) 1 SR 3.3.6.4 i A COT is performed every 92 days on each required channel to ensure the entire channel will perform the intended Function.

The Frequency is based on the staff recommendation for increasing the availability of radiation monitors according to NUREG 1366 i (Ref. 2). This test verifies the capability of the instrumentation to provide the containment purge and exhaust !

system isolation. The setpoint shall be left consistent with the I current unit spccific calibration procedure tolerance. !

SR 3.3.6.5 l

SR 3.3.6.5 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified in one of two ways, Actuation equipment that may be operated in the design mitigation mode is either allowed to function or is placed in a condition where the relay contact operation can be verified without operation of the equipment. Actuation equipment that may not be operated in the design mitigation mode is prevented from operation by the SLAVE RELAY TEST circuit. For this latter case, contact 0 3.3 + 1 operation is verified by a continuity check of the circuit ontaining the slave relay. This test is performed every 19$ days. The Frequency is acceptable based on instrument eliability and industry operating experience.

SR 3.3.6.6 Not_Us.ed.

SR 3.3.5.5 is thc performance of ; TADOT. This test is ; che d ef- the ";nual Actuation functions and is performed cvery 10 months. Such ",;nual Actuation functica is testcd up to. and including, thc m; ster relay coils. In som; instances. the test includes actuation of the cnd device 'i.c.. pump starts, valve cycles. ctc.'.

The test also includcs trip devices that providt ;ctuation signals dircctly to the SSIS. bypassing thc analog process control equipacnt. The SR is modificd by ; Note that cxcludes verification of sctpcints during the TADOT. Thc functions tested havt no sctpcints associated with them.

(continued)

CPSES Markup ofNUREG-1131 Bases -ITS 3.3 B 3.3-171 103088

1 l Containment l'urg; end Exh;u;t Ventilation 1 solation Instrumentation B 3.3.6 i

BASES (continued) l

! TPc frequcacy i; b;;;d on th; kne'.;n reli;bility of th; ranction er.d the r;dund; rey ;v;ilabic. and he; b;;n ;h;.;, to b; ;;;;ptabic threugh operatin; cap;ri;n;;. l SR 3.3.6.7 A CHANNEL CALIBRATION is performed every months, or approximately at every refueling. CHANN CALIBRATION is a l Q 3.3 G-1 l complete check of the instrument loop, including the sensor.

The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Frequency is based on operating experience and is consistent with the typical industry refueling cycle.

SR'3:3:6:8 l

! $13i61821slMperfomancelofLtheitequjred!gsponseltine verificatielevery;3s;]ux!th5MESPGGEREDJESEBASISXthese containmentivergilatieasolatten;functimsyjtttjmeiltaits l

PrMideOnithe1TgchnicaEgequirements"#anualglEachJetification

shallits!cludeatlleestleneIttajisuchithat1bothltrains: ste vetifiediataeast;orice3etxmonthsIIUThelresponseitime 1ncludes PressurJzer;ptes.sure30W;"signaEthroughiclosurelof;the l

containment;ptessure]telifli solation 3alves]

l REFERENCES 1. 10 CFR 100.11.

! 2. NUREG 1366. July 22,1993.

l l

L t

l-t 4

(continued)

CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-172 10/30/98 i

CREFS Actuation Instrumentatior.

B 3.3.7

! BASES l

APPLICABILITY The CREFS Functions must be OPERABLE in MODES 1, 2. 3, 4, 5,~;6 [ cad durin;; C0" ALTE"ATIO5] and movement of l CP-3.3 009 irradiated fuel assemblies. The Functions must also be OPERABLE in MODE juu1Ji nFrequired for a waste gas T o.3.3.s.1 l decay tank rupture nt, to ensure a habitable environment for the control room operators.

f ACTIONS The most common cause of channel inoperability is outright failure or drift of the bistable or process module sufficient to exceed the tolerance allowed by the unit specific calibration procedures. Typically, the drift is found to be small and results in a delay of actuation rather than a total loss of function. This determination is generally made during the performance of a COT, when the process instrumentation is set up for adjustment to bring it within specification. If the Trip Setpoint is less conservative than the tolerance specified by the calibration procedure, the channel must be declared inoperable immediately and the appropriate Condition entered.

A Note has been added to the ACTIONS indicating that separate ,

Condition entry is allowed for each Function. The Conditions of l this Specification may be entered independently for each Function l listed in Table 3.3.71 in the accompanying LCO. The Completion Time (s) of the inoperable channel (s)/ train (s) of a Function will be tracked separately for each Function starting from the time ,

i the Condition was entered for that Function. J A.1"and7A:2 CP 3.3 ED Condition A applies to the actuation logic train Function of the CREFS, the radiation monitor channel Functions, and the manual channel Functions.

If one train is inoperable, or one radiation monitor channel is inoperable in one or more Functions, 7 days are permitted to restore it to OPERABLE status. The 7 day Completion Time is the same as is allowed if one train of the mechanical portion of the system is inoperable. The basis for this Completion Time is the same as provided in LC0 3.7.10. If the channel / train cannot be restored to OPERABLE status, ene-the~affectedjCREFS train must be placed in the emergency rcdiction p ctcction; recirculation mode of operation. This accomplishes the actuation instrumentation Function and places the unit in a conservative mode of operation.

CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3- 176 10/30/98

CREFS Actuation Instrumentation B 3.3.7 BASES s

SR 3.3.7.4 Not1Used!

)

en e e , ,

ou ....,., se

2. i L, _ - _ , - _ _ - _ . - , _ uneven net av vre,

.~ ys. s i vi a us , ~ va u smam m-m a smes.

vL. uneven asm smsm "EL'Y TEST is the cr,crgizir,y o' the estcr rC'cy vcrifying Cent;Ct epCreti;n :nd ; 1;W Volt;9C ;;ntinuity ChC;k of thC -1;VC rClay C;il. 'Jpen ;3tCr rClay Cent;Ct opCration. ; 1;W volt;9C l 2_ 2_2- 1_A m, .L. _ ,-..- _ , . . . __2, vL2. ..., ___ 2_

sJ suJswwww bv b i rs d5uww awsuJ hvs4 . sessa Tvswuys sa in;ufficiCat IG pick up thC -lev; rClay, but leryC Cneugh tG

-- -_i_ t. _2__.1 _.iL - - 1 2 _. 2 & . . vL2. &-_A 2_ _- s ; . . . _ _ . .

gewesevs ed b ubw J s yE su a yu we I uvT I b 5 s tu a wJ . s sI s d bsJw ad ywa a vs ssTsu w wwa J es evneerne r_-_..---.. ----_A. Lim us uvy J... __ _

vu o esow-msn Trev, ses naev.e uns s.

vt_

ss~ s wyuwa ~J 2. uwusywouiw bOSCd On in0truWCist TCliGbility Gnd industry Op; rating CxpCTICGCC.

SR 3.3.7.5 N.o.t. .t Used.

.~

en e e 7 e 2. sL. -- s-__-___ _s . et nur nerav vrev TL- et nur su w.w.s.s so wa rs ywi s vi mui ~s we u smu s num a e s.s i . asm si.n v i.

nrtav vret 2. AL. -----2.f__ t AL. .1-.. _ _1 ...- e- s - A n66ns abwa sa bus wa rsa y s & e s sy vs warb euuww sLawyd. vvis buw b OpCIOIiOn i3 vCIIfiCd in OnC Of IWC WOy3. CIuCIiOn CQuih7CnI LL s _.L. ----LJ 2_ sL. A- 2__ _262-.s2-_ unne 2. 2sL-_

wi nu w muy us vyssu6ww in wim ww w s yn e m s w s yu w s vi s s uvvw se w s 6s ssi OllCWCd IC funCIiOn GI i3 plOCCd in C COndIIIOn WrCIC IhC IClCy Cent Ct ep; ration Cars bC VCrifiCd Without epCration of thC

--.2-_- A a A...A2-_ -_.2-_- A AL.A _ - . . -A L. ----.A_J 2. AL.

squ s ymwi s h , nw wuu b a vi s syv s y-wn e, wa su w muy a rv w us vyssu6su su wiss J - . 2 -_ _2s2_.L2-_ unnr 2. ---..-xA c--- -_.._ L2-_ L.. sL. etnur wwdsya m a 6 s yss w s via s avvb sa ys w y vs s bww a a vm wyw a u w s vs i WJ vsas wwnyb nreau vver _2_ _. . a s r_ AL2_ 1.As _ ____ -- A._A -_-- A2__ 2.

nuwns suws wsowusw. s vi wusa s u w wws wusw. wvissuww vyssuwsvu so

. .- 2 22 J L.. - - - r 2 _. 2 L . . L-L c sL- 2-.2s -- L.2_2__ sL_

ywa au a w ss wJ u . hvi s b s s nu a bJ ws swwr% vs 64rw wsawuew wvr s bu I s s E B 33 bsas

,1.... -1... TL2, s_.s 2. _-r-J . . . _ _ . . rnoi J.... TL-asuww asuuy. susa usaw sw yss a vs www w wwi g Ls6J wuys. sass r_-..---.. 2_ ._--L.L1. L._ J -- 2_,s.--x _ 12 .L 212 6. . ._J s a wquws swJ sd wwwsybuwis uvaww wa s a s sa ws umwi s h a w a s uu s s a by ussw indu3try spCreting CxpCriCnCC.

SR 3.3.7.6 SR 3.3.7.6 is the performance of a TADOT. This test is a check the Manual Actuation Functions and is performed _-. 0 3.3-G-1 every 8 nths. Each Manual Actuation Function is tested up to. and including. the master relay coils. In some instances, the test includes actuation of the end device.

The test also includes trip devices that provide actuation signals directly to the Solid State Protection System, bypassing the analog process control equipment. The Frequency is based on the known reliability of the Function and the redundancy available. and has been shown to be acceptable through operating experience. The SR is modified by a Note that excludes verification of setpoints during the TADOT. The Functions tested have no setpoints associated with them.

CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-180 10/3W98

CREFS Actuation Instrumentation B 3.3.7 BASES SR 3.3.7.7

' A CHANNEL CALIBRATION is performed every r approximately at every refueling. CHANNEL CALIBRATION is a M complete check of the instrument loop, including the sensor.

The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.

The Frequency is based on operating experience and is consistent with the typical industry refueling cy-'"

REFERENCES Pone.l.HSAR;.Section.6.4] .

c.

I~

CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3181 10/30/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-A GEN APPLICABILITY: DC, CP, WC, CA REQUEST: Generic Administrative Changes Comment: Provide one DOC for each LCO to justify CTS changes that involve reformatting or word differences without any change in meaning or operation of the plant.

FLOG RESPONSE:

As discussed in the transmittal letter and the " Methodology For Mark-Up of Current TS" in the back of Enclosure 2, the CTS has been marked up to reflect the substance of NUREG-1431, Revision 1. In general, only technical changes have been identified. However, some non-technical changes have also been included when the changes cannot easily be determined to be non-technical by a reviewer, or if an explanation is required to demonstrate that the change is non-technical. DOC 1-63-A was created and added to the top of the page for each CTS Section 3.3 Specification. DOC 1-63-A states:

"All reformatting, renumbering, and editorial rewording is in accordance with the Westinghouse Standard Technical Specifications, NUREG-1431. During the development certain wording preferences or English language conventions were adopted.

As a result, the Technical Specifications (TS) should be more readily readable, and therefore understandable, by plant operators and other users. During the reformatting, renumbering, and rewording process, no technical changes (either actual or interpretational) to the TS were made unless they were identified and justified".

ATTACHED PAGES:

Enct2 3/4 3-1,3/4 3-16,3/4 3-47,3/4 3-50 and 3/4 3-53 Enci 3A 14 1

Enci 38 10a

3/4.3 INSTRUMENTATION 1 63-A I Q 1 A GEN 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION l 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.3 1. 1 ACTION:f:;

As shown in Table 3.31.

SURVEILLANCE REOUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be deconstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.31.

0 3.3 55 4.3.1.2 The se,;;ir4 REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstreted verified to be within its limit at 1 D1 58-A" ""

least once per 18 months [onXSTMIGEREDlTESLBASIS'._*t. Cech test shall include t ic;st ere train ;uch th;t both trains ;re tcsted at least encc pr 35 ;;;;nths and era chennel gr function such th;t 011 cht.nrels ;rc tested et ler.st encc recry l tire'; 10 ;;;;r.ths wherc !? is the total nu d er of redund:nt chennels in ; ';gcific Rc;;ter tri;; function es she.;n in the

" Tot:1 !?;. Of Ch;n cis" celu;;;n of Tobic 3.31. u-02-LGQ

SePatateACTIQN; entry 1slallowediforleachlunctiony d 01'A"!ts U;..Neutronland E16; detectors;are;excludedLfrom' response; time:testi;ng.' 41-02-LG a CPSES Markup ofCTS 3N.3 3M 3-1 10/3088

INSTRUMENTATION 1-63 A 0 1-A GEN 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION

' 20UA m 3.3.2 The Engineered Safety Features Actuation System (ESFAS) .

instrumentation channels and interlocks shown in Table 3.3-2 shall be OPERABLE "2m e,

.;ith thcir Trip Sctpoints .ct and consistent with the A11cWahleivalues shown in the Trip Sctp; int coham-ef Table 3.3-3.

APPLICABILITY: As shown in Table 3.3 2 ACILQN: ".**

e.s..:.s e- u. n.. .u.

eeene

.. - , ~ ,..

....b.

..._ .~. - .

bub. a.v...

Ts..,....

...bs. . ss v..:-

. .y es b ro . . ' "

2 M W trip icss con civativc then th; V luc sh/.;. in the Trip Setpoint coluen .,,

but rcic conscrvativc . , . _ _ .,

ther, the, ,value L, . , .o. s

.L. u. u ..m t...._..

. 2._.

. .~ n....L,,. ...m . . . . . . . . .. v. ... .. ,. mus .b

2.s - u . ...,..

sb .kN . VLbyV. se 2. I.sb WVI .J s J bb. .sb .. I. : s.r .1 sL% b. v. _. JIf .MLbyv..sc .s - 2 . . b.W.us.

s - , .L e s..J_s

b. 1 f J.b.s L. .. .er e. ~A e T , A.

.. ~ . .s m.- - - -

bob. s J. v ,v. .- T...bs. . men v. .m J, y. em b ev . ' ' '

....b.

2-04 LG lc 3 cor.,crvative then th; value ,he'.;n in the Alic'.;;bic "alue coluan of T;bic 3.3 3. dcclerc the cher.nci inopcrable end pply th; opplicabic ACTI0',' state cat regttirs. cats of Tobic 3.3 2 c. until the channel is -.a.s..

..>.s on.....,

restored

s. s.... .a .

bw nnen a n,, e vu n v m ba. gbubud .= sblu.

u. b J ww b yv . . u k uwgudbbw ww. .a s J bb. .s b v e.s. 2 1....

..c. a. sb.L, sb.L.b us t. .y w b b yv .s.sb .u ub.

c. With ESFAS instrumentation channel or interlock inoperable. take the ACTION shown in Table 3.3-2.

Separate ACTIONientryfis1 allowed;forleachfunction

. -1 01 A '

1 1

I 1

CPSESMarkup of CTS 3M.3 3M 3-16 10/30/98

INSTRUMENTATION 1 63.A 0 1-A GEN 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS 4

_ LIMITING CONDITION FOR OPERATION '

3.3.3.1 The radiation monitoring instrumentation channels for plant operations ,3.gL42 shown in Table 3.3-4 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-4.

ACTION: Note: : Separate [act1on Lentrylislallowed, forleach , function: 1 01-X -

a. With a radiation monitoring channel Alarm / Trip Setpoint for plant 13-02.-M '

operatiens exceeding the value shown in Table 3.3 4, adjust the Sctpcint to within the li;;;it within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel

< inoperable.

b. With one or more radiation monitoring channels for plant operations '

i

' inoperable, take the ACTION shown in Table 3.3 4.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable 3 06 A -

toltheJCSfLe~akageDetectionJystem.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by performance of a CHANNEL CHECK,

b. At least once per 18 months by performance of a CHANNEL CALIBRATION, and

c. At least once per 92 M-days by performance of a DICITAL CHANNEL 3-09 LS:

OPERATIONAL TEST.

3M 3-47 S/1S/97 CPSES Markup ofCTS 3/4.3

INSTRUMENTATION 1-63 A l 0 1-A GEN REMOTE SHUTDOWN INSTRUMENTATION L !

LIMITING CONDITION FOR OPERATION ,

3.3.3.2.1 The Remote Shutdown monitoring instrumentation ch;nncis fgictionsjshown grgy t in Table 3.3 5 shall be OPERABLE.

3.3.3.2.2 The recote shutdown transfer switches and controls of system 7 03 LG components rcquired for 1) reactivity centr:1, 2) "CS pre;;urc ;;ntrol. 3) dc;;y 0 7 08a hc;t ic ~;;1. 4) "CS inv;ntory mentrol. and 5) :spprt sy;tc;; requircd for the c.b;;; function; shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:MNog;efj Separatf ACTIONiegtrfds31]gf,or;eachlunctiotCar!dD ired;HSij ;10141

~

3 Econtrol.1

a. With the number of OPERABLE remote shutdown monitoring channels less than the "ini;;;u; Ch;nr.cis 0"CPXLC :: required by Table 3.3 5, restore 17 04-LSi the inoperable channel (s) to OPERABLE status within 7 30 days, or:be jniHOTiSTANDBOltMnithe~ nest 6Lhoursland be in HOT SHUTDOWN within 97-05'Ad the next 12 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. 'dith th; nu;bcr of OPE"XL rcr.;tc ;hutdow, i.enitoring chenacis ic;; yy.08@ l th;n the Total Nu;bcr of Chenacis as required by Tebic 3.3 5, within 50 )

days restcrc the inegrabic chenac1(:) to 0"ET"L :tetus cr. pursu nt I to S gcification 5.0.2 :ab;it ; Sg cial "; prt that defincs the ;;rrective action to be taken.

c. With one or more Remote Shutdown transfer switches, power, or control r7 048151 circuits inoperable, restore the inoperable switch (s)/ circuit (s) to OPERABLE status within 7 30 days, or be in H0T STANDBY within the next 37 02sM M 12 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and]IOLSilf]DOWN3jtMnjtheJollojwi6' hours,

d. The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.2.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE

a. At least once per 31 days by performance of a CHANNEL CHECKlofleach 17-09 m requ. ired; instr,umentichannelithatiis;normally;energi_ zed, and

b. At least once per 18 months by performance of a CHANNEL CALIBRATION.*

d l CPSES Markup of CTS 3N.3 3M 3-S0 10/3088 l

l

-. ~ - _ - - _-. _ - . . - . - -- . - . _ _

T INSTRUMENTATI0h 1 63 A 0 1-A GEN ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The accident monitoring instrumentation chenaci; fjections shown in Table l 3.3-6 shall be OPERABLE.

62 l APPLICABILIT(: MODES 1, 2, and 3.

e l

ACTION:

a. As shown in Table 3.3 6.

I

b. The provisions of Specification 3.0.4 are not applicable.

l

@EM Separate; condition" entry 11s~allogedloteaciffunction? 41-01-A M 1

SURVEILLANCE REOUIREMENTS <

i 4.3.3.3 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:

i

a. At least once per 31 days by performance of a CHANNEL CHECKBfor, f46v4 ,

eacterestredliftstammrJ!a!!neXt!!Eisl!Legimneal]renergtM11.

CP 3.3 ED and i

b. At least once per 18 months by performance of a CHANNEL CALIBRATION.* i l

t l

l 8 09 LG Q 3.3 20

Contain.. cat Arc; R; diction ("igh R;ngc) C".'"" L CALISRATIC" m;y censist of an i

l ciectronic c;libration ;f the ch;naci, not including th; dctcctor. for ren;;

icede; ebevc 10 R/h end ; en; point calibr;ti;n chcck ;f the itcctor Scis 10 R/h with en in:t:11cd er portsbic ;;=: ;;urcc.

CPSESMarkup of CTS 3M.3 3M 3-53 10/30/98 1

I l

CHANGE NUMBER EliC DESCRIPTION and ESFAS sensor response time testing to be performed per WCAP-13632 P A Revision 2. " Elimination of Pressure Sensor Response Time Testing Requirements," or other similar methodologies. This change is consistent with traveler ,

TSTF-111, which revises the Bases for ITS SR 3.3.1.16 and SR 3.3.2.10 to allow the elimination of pressure sensor i response time testing.

CPSES has not yet provided a plant-specific submittal describing the manner in WCAP 13632-P A or a similar l methodology will be applied. Therefore, until a plant-specific submittal is approved by the NRC, CPSES will continue to response time test all Reactor Trip System and l ESFAS sensors. The proposed changes to the wording in the Technical Specifications remain applicable, regardless of l the implementation of the sensor response time elimination.

I 1-59 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B).

i 1-60 -

Not used.

1 61 M This change reflects a revision to CPSES current ACTION ,

Statement 6. If the requirements of current ACTION Statement 6 are not met, LC0 3.0.3 would be entered which would allow 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to exit the LC0 applicability by entering MODE 2. In accordance with the ISTS, this ACTION l Statement is revised to state that if the ACTION requirements are not met, the plant must be taken below I the P 7 interlock setpoint (the LC0 applicability) within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Thus, this change is more restrictive, by I

one hour, than the current TS.

1163 A AlXreformatting&enumberinggand'adjtorjal iTE!D towardjng;jslinzascordance:with:the;uestighguse Standardleghnjgallspecificationsfl.NUREG3431EDurjng the developmenteettaipotdjng:preferenees;olr English language: conventions;wete:adoptedHAs?,alesultEthe TechnjealiSpecificajjonsMTS)fghouldibe"apreleadily teadabjeranditherefore;understandattleaiplantlopetators and;other3 sets]I!DetigithelreformattiqEteRattering; andyewordjgprocessXno;technica13haggsge1MMctual orL1_nterprgtatjogamtpithe TSyete made3nte_ss theper -

identified;ancustitiedt li64 A The2efueljf!g';1gteryalfTADOTsifotifunctional;. Units 1[1 0 1 23 1 i

aKJ71,1nlCI)][able3311; hay (beenfregiseCtolinclude exist 13g1Notel[1.0 E Setpoint jerificationlisinot CPSES Description of Changes to CTS 3M.3 14 10B0/98

Page 10a Gf 22 CONVERSION CONPARISON TABLE - CURRENT TS 3/4.3 APPLICABILITY TECH SPEC CHANGE DIABLO COMANCHE WOLF CREEK CALLAWAY NUNBER DESCRIPTION CANYON PEAK u

f yes yes All 2reformatting.irenumberingJand, editorial; wording is;in ,accordance with;the yes Yes 1-63 A Westinghouse;5tandard.TechnicaliSpecificationsnMUREG-14314 \

~

~ Luda,,,1 yes Yes Yes Yes 1t46 Notes;are;added to; Tables;4;3t11and,A3 2;to, enc}ude;setpointaverffjcations R 0123 I A dur.ingJAcorspfunctional; units ethet:Anot;heye.setpointsiassocjated,witti themi No No Yes yes 1-65 ExplanatientofqIT5;. treatmentt ofssevents1avoitelays;with;extendedisurveillance A frequencyl yes yes Yes Yes 1:66 Thistchange,wouldidelettitha feferenceite;3peC1f100tjen;4;3113;and;!;3.2!111n E 0-3.3s l LS_45 theiallowedJhypassJetes containedain3stteffLCT5JCIIRp*mesmantsathus pemittinemetatine nseded ifprerestoration;efishenneparei.;runction; yes No ND leo 1-67 yhis change:Jewises; CTS. ACTION 2 513iandAte proeideispecificjshutdown N requi rements.to iexitJppl i cabil i ty,11n211eu.0f; applying _CT5; LCO,3.0.3 FJhi s l 0 3.3-44 5 change,.is more, restrictive by;one;hourathen;the CT5; Yesh;/ see3also No No No 1 68 Thistchange; deletes;DCPf.9,;CT5;Iable;43-1.neteJ8);uhich;islapplicableito,the i

LS-54 sourceyengeaThepification;cannottbe perfomedijn,pEIDE;3%4*jand;5*,1since CNi the poweriandlintermediatel range;chenne)s art not, required 4 to:be_operableA11 1-69 N N00E24 1:69 This, change; applies new note;(20)1to.DCPP,CT5 s 2 Table.4.3;ILfunction,6 A source yesmsee;also No No No N range;neutronflux( CNi 1.68-LS-54 Yes Yes Yes Yes 2 01 The Engineered Safety Features Actuation System Instrumentation [ ] Allowable A Values are moved to ITS Table 3.3.2-1.

CPSES Conversion Comparison Tame - CTS 3N.3 103088

l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-LS GEN APPLICABILITY: CA, CP, DC, WC REQUEST: Genenc LS DOCS Comment: For each proposed less restrictive change discussion include a clear statement i of the CTS requirement, the CTS reference, a statement of the proposed ITS requirement. l and the proposed ITS reference. For an example of this problem, refer to the first paragraph of LS-17.

Based on 8/14/98 meeting comment responses will be addressed in individual LS NSHC.

FLOG RESPONSE: No specific response will be given to the comment; however, this RAI number will be used for tracking purposes where NSHCs in Enclosure 4 were revised outside of a specific comment (e.g., the response to Comment Number 8-04-LS-17 addresses the NSHC cited in the ,

comment). See attached revisions. l l

ATTACHED PAGES: l l l Enci 4 LS-19 page 45 i LS-24 page 54 !

LS-27 page 58 LS-39 page 61 LS-40 page 63 I i

i e

I

IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-19 10 CFR 50.92 EVALUATION FOR l TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE prnm REMEKTS WITHIN THE TECHNICAL SPECIFICATIONS Mrgesed change _uonidTextendithe*alJgwedJutageltimelassociatedhth tuurAte; safety 3njectianmejneneetemlgourrasatm@edanicuCrent 16 min"?$sT% Tim 51 sequencer is an essential suwvi 6 4;t= t; La tne offsite circuit and the Diesel generator ,

associated with a given safeguards electric bus. Furthermore, the sequencer is on '

the primarily success path for most major AC electrically powered safety systems I

powered from the associated safeguards bus. Therefore, loss of an SI sequencer affects every major ESF system in the train. The proposed change would increase the time allowed to restore an inoperable sequencer from 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . This 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months completion time provides a period of time to correct the problem commensurate with the importance of maintaining sequencer operability. This time period also ensures that the probability of an accident requiring sequencer operability occurring during periods when the sequencer is inoperable is minimal.

The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been l performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted l below:

i "The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves a no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant

! hazards consideration standards:

l

! 1. Does the change involve a significant increase in the probability or l consequences of an accident previously evaluated?

Overa11' protection system performance will remain within the bounds of the previously performed accident analyses since no hardware changes are proposed.

!' The same instrumentation is being used. The proposed change will not modify any system interface and could not increase the likelihood of an accident since these events are independent of this change. The proposed activity will not change, degrade or prevent actions or alter any assumptions previously 1 made in evaluating the radiological consequences of an accident described in CPSES No Significant Ha:.ards Consideration - CTS 3N.3 45 10B088

l IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 24 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN DIE TECHNICAL SPECIFICATIONS

]pngeseAchangeMd; the Surveillance frequenc3 rim the o 2 6-a I performance oT ; C,"!!:'". ^"L m W (C0T)1for the radiation monitoring l l instrumentation channels h sfd O nt;r Q rom once per 31 days to once per

! 92 days. This change-is consistent with NUREG 1431. Rev. 1. The COT is performed l

to ensure the entire channel will perform the intended function. This test verifies the capability of the instrumentation to provide the Control Room Emergency Filtration System and Containment Vent Isolation actuation. The frequency is based on the known reliability of the monitoring equipment and has been shown to be acceptable through operating experience.

The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been 1

performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted l below-f l

"The Commission may make a final determination, pursuant to the procedures in l 50.91, that a proposed amendment to an operating license for a facility I licensed under 50.21(b) or 50.22 or for a testing facility involves no ,

significant hazards consideration. if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an i accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated: or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

Overall protection system performance will remain within the bounds of the i previously performed accident analyses since no hardware changes are proposed. l The relaxation in the frequency at which Channel Operability Tests are j i

performed is based on the known reliability of the monitoring equipment and has been shown to be acceptable through operating experience. The proposed i change will not affect the probability of any event initiators nor will the l proposed change affect the ability of any safety-related equipment to perform l its intended function. There will be no degradation in the performance of nor l an increase in the number of challenges imposed on safety related equipment !

i i

CPSESNo Significant Ha:ards Consideration - CTS 3M.3 S4 10B088 l

. -. l

XV. SPECIFIC NO SIGN 1FICANT HAZARDS CONSIDERAT10NS NSHC LS 27 10 CFR 50.92 EVALUATION 1 FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN lliE TECHNICAL SPECIFICATIONS N

This proposed change applieshion required to be taken if the w.3,g required channels of a function of the Post Accident Monitoring System (PAHS) '

instrumentation are inoperable. For those situations where one of two f required channels was inoperable, the proposed change would extend the requirement to restore the inoperable channel to operable status from 7 days to 30 days. This proposed change would also delete the requirement to be in HOT SHlHDOWN when a single channel cannot be restored to OPERABLE within the required time, but would add the requirement to submit a Special Report to the NRC. For those situations l where two required channels were inoperable, the proposed change would extend the completion time for restoration of at least one of the inoperable channels to OPERABLE from 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to 7 days. M se changes'affectucurrentfiecnnicai f,1 cations J abl.el3:3-62 Action Statements;32,and 33)

During tnis 30 day allowed outage time for one required channel, indication of a particular function, using only PAMS qualified instrumentation, would remain l l

available. In addition, per the CPSES licensing basis, the core exit temperature thermocouple temperature indication provides an alternate indication to the hot leg ;

temperature. Similarly, the steam generator (main steamline) pressure indication, with the use of tables of saturated water / steam properties, is an alternate indication of the cold leg temperature. Both the " primary" and " alternate" indications are listed in the plant Technical Specifications. Note that for the T.

and T m functions, two of two channels of the alternate indication are required to be operable during the 30 day period.

The 30 day period is based on operating experience and takes into account the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring the PAMS instrumentation during this interval.

The 7 day allowed outage time for two required channels is based on the relatively low probability of an event requiring PAMS instrument operation and the availability of alternate means to obtain the required information. Continuous operation for an l unlimited time with two required channels in a Function is not acceptable because the alternate indications may not fully meet all performance qualification requirements applied to the PAMS instrumentation. Therefore, requiring the restoration of one inoperable channel of the function limits the risk that the PAHS function will be in a degraded condition should an accident occur.

If one of two required channels is inoperable and can not be restored within the required completion time, the requirement to shut down the plant is replaced with a requirement to submit a special report to the NRC. Among other regulatory matters, the report must describe the compensatory actions to be taken in order to monitor the parameter affected by the inoperable channel if an accident were to occur which requires the PAMS. Because the PAMS has no safety function during normal operations CPSES No Significant Ha:ards Consideration - CTS 3N.3 58 10B0/98

IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 39 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Applicability Not [a] and ACTION Statements [5 and 9] for Functional Units a2c-a

[1 .

J JgP 9. and 20] of current TS Table 3.3-1 are modified to provide an a tei.muve to opening the reactor trip breakers (RTBs) while still assuring that the function and intent of opening the RTBs is met. As currently worded, these ACTION Statements result in a feedwater isolation signal (FWIS) when in H0DE 3 with a T , less than [564*F.] A more generic action, which TR 3.3-006 medm;thatCactionibeltakerQojassures the rods are fully inserted and cannot be withdrawn, replaces the specific method of precluding rod withdrawal. The revised Applicability and ACTION Statements still assure rod withdrawal is precluded. This change does not involve any safety impact and is consistent with traveler TSTF 135. The proposed change allows more freedom in how rod withdrawal is precluded and is thus less restrictive. However, the intent of using physical plant characteristics to prevent rod withdrawal is not diminished. The specification now acknowledges that the Rod Control System can be effectively disabled by 0-3.3-122 means other than opening the RTBsKeig.*Zbyldelenergizingla]1 CRDHsZopening the11HBsEorldefenergizing;the;notorlJenerator3HG)Jsets.

This proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted i i

below:

"The Commission may make a final determination. pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant l hazards consideration standards:

> 1. Does the change involve a significant increase in the probability or

' consequences of an accident previously evaluated?

The proposed change does not alter the requirement to preclude rod withdrawal l

using physical plant characteristics. The specification does not allow administrative control or other means which could be conceived as less CPSES No Significant Ha:ards Consideration - CTS 3N.3 61 10B088 i

IV. SPECIFIC NO SlGNIFICANT HAZARDS CONSIDERAT10NS NSHC LS 40 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS The current TS require that the setpoints be verified during the quarterly 0 2 Ls-GEN TADOTs for the Reactor Coolant Pump (RCP) Underfrequency [ ] function. The setn+t M hatalv confirmed dur M tM 10 mnnth calibrations 63erefere;

_ _le31331;j s'reyLsed;to_M2EEtohWsinflanctiona]1Rggts342andil5 l sech;thetisetpointavergicatsspilletan0thelwegerJMAo0Dsmespeed;Erpisits acceptable;because.;cpetattgg3gR$g!celdlaQhqunJhat;theseJelagtetportnts demonstratelsuchlow;,dtift3 i hat tDheitetpointOetelvetifiedionEduting;the;18 montb~ca]1brations'thete;,Wod1Muteoleffectronlsystes performanceland;the' Allowable Val uestfor3these~ Functions 3nicDrrentMable 2;2dl;wouldinot be:chalJenged; t

The proposed TS change has been evaluated and it has been determined that it I involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

l "The Commission may make a final determination, pursuant to the procedures in l 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21 (b) or 50.22 or for a testing facility involves no l

significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated: or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated: or l 3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The setpoint for the RCP Underfrequency [is] selected such that the Allowable Value is not expected to be exceeded during the 18 months between

calibrations. This function is not an initiator for an accident previously analyzed but the function is used to provide a reactor trip signal to mitigate 4

certain accidents. However, because the function is not expected to exceed its Allowable Value based on the 18 month calibration, it is concluded that the proposed change would not involve a significant increase in the consequences l

of any accident previously analyzed.

CPSES No Significant Ha:.ards Consideration - CTS 3N.3 63 10B0/98

l 1

l

\ ADDITIONAL INFORMATION COVER SHEET i

ADDITIONAL INFORMATION NO: O 3-LS GEN APPLICABILITY: DC, CP, WC, CA f l

REQUEST: TSTF-135 changes l i

Comment: TSTF-135 was rejected except for the traveler changes identified by the l following justifications: DOC 3 which deletes STS Condition V for two inoperable trains; !

DOC 4 which makes changes STS T3.3.1-1 Note (b); DOC 5 which deletes Source Range {

Flux for Applicabilities in T3.3.1-1 with Note (f); and DOC 7 which deletes intermediate Range Flux for Applicabilities in T3.3.1-1 with Note (e). Revise the submittal to delete all other TSTF-135 proposed changes.

FLOG RESPONSE: This traveler was discussed during meetings with the NRC staff during the week of August 10,1998. The attached pages represent changes, including revised DOCS and JFDs, that we believe are acceptable to NRC. These changes are marked with the change code "TR-3.3-006" since the majority of these mark-ups were self-identified and pre-date the RAl. Mark-ups are based on TSTF-135 Rev. 3.

ATTACHED PAGES:

Enct 2 3/4 3-5,3/4 3-7,3/4 3-8 and 3/4 3-15 Enci 3A 9 and 13 Enci 4 31 and 61 EnctSA Traveler Status Sheet, 3.3-1, 3.3-2, 3.3-5, 3.3-16, 3.3-17, 3.3-21, and 3.3-22 EnctSB B 3.3-7, B 3.3-8, B 3.3-9, B 3.3-13, B 3.3-14, B 3.3-34, B 3.3-35, B 3.3-37, B 3.3-38, B 3.3-43, B 3.3-44, B 3.3-48 and B 3.3-49 Encl 6A 11d,13 and 14a Enci 6B 18, and 22 l

I I

I

TABLE 3.3-1 (Continued)

TABLE NOTATIONS

Only if the rccctor trip tr ckcrs hcppen to bc in the closcd position cad the ".ontrol Rod Drive System is capable of rod 1-55 LS a-3.3 006 w al;og3nern cLentrio11rodggryinut1%11y

Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

Below the P 10 (Low Setpoint Power Range Neutron Flux Interlock)

Setpoint.

d Above the P-7 (At Power) Setpoint

Deleted.

' Abcvc thc P S (3 icop ' low pcr;issive' Sctpcint. 11-57.LGc.'

8 Abovc the P 7 cad bclow the P S Sctpcints. 21-57-LGSi h

Scictchyeithefi6l(Inter 9edjate; Range Neutrortflux'Irlterlock) e107iLSMi setpoint:

Above the P-9 (Reactor trip and Turbine trip Interlock) Setpoints.

8 Including AnyJTBibypassibreakersIrackedjjgandiclosedifor; o bypassing g3 34;ggi )

a'RTBJ 1

I i

CPSESMarkup of CTS 3N.3 3N 3-5 10B088

- --. - . - . _ _ _ . . . - - . - - ~ - . - - - - - _ . . - _ . - ~ - . . -.

TABLE 3.3 1 (Continued)

ACTION STATEMENTS (Continued) i l

b. Above the ." S 'Intcc.cdicts ";ng; Ncution Elux Interixk) j Ectpcint but below 10% of "fE0 EE""AL "0L'C". Within i 241hoursgrestore the inoperable channel to OPERABLE ~1-07aLS u

~

status prior to isra;ing I;lE""AL "0"E" orfreduce I

TIEltmL"SnERylkss> PK1er9pcreaseAElgmL ,

PDEDo abeyageLMyemmLmnER; 1 i

ACTimi3.13 With:the3gidieGpt,$heggielsREIMBLEgtmo3ess3l mea st4743g

~

lloqu1W$l!ginels 3tmged%Igpl3tsuspendjeppWW$ensalppolving posittue'ammet1Wtta0settetens2mulvt#tn123mawayeduce MElWEL15EL3mHesgtherfP-6:

With the number of OPERABLE channels one less than the Hmtmum

$43h ACTION 4 -

Requiredichannels 0"E"2LE requiracat iemediately; suspend ri-es-M m all operations involving positive reactivity changes.

+1-08 M % l ACTION 14;15 With nojsourceirange; neutron: flux; channels; operable; insediatelropenithe RTBs? i ACTION 5 - With the number of OPERABLE channels one less than the MWmum ;1433%

Required; Channels 0"E"2LE requir;xnt, restore inoperable

,chana=' *n OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months o nitiate 41 38 R wa '

Cactiontto within the acxt b;@ egn .~ .acter mp

~

br a t rs en; susg as ;;; . g ration; involving p;;itive .

re;;tivity chx;;; full.VIinsert"allirodslandjplacetthe Rod h{Uo06 )

Cnntrol; system;1nrcond_ttionlincapable3Lfadiwithdrawal within;theinext3ourg ACTION 6 - With the number of OPERABLE channels one less than the W yt:43 gn4 Nu;bcr of Required; Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

b. The ",ini;;; Ch;nacis 0"E"# LE r;quir; x at is x t; 1;43-A Ma houcv;r, $teGthe inoperable channel or another channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for 1 66 5 surveillance testing gr Epcific; tion 4.3.1.1 0 3.3.1 new. OtherwiseZreducelTHERNALfPOWER,1Qess;t_han1P t 2 72Within >1 61~-Mi N theinextL6thours!

ACTION 7 - With less than the M4meum_ Requited _ Number of Channels ;1 52 LG d

~

OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by ob: rv; tion of the s1-43;A M4 l ess;ciated g raissiv; anuncistor windcu's) that the interlock !

is in its required state for the existing plant condition, or ,1;12 -M ~ c"

~

apply Eg;ific; tion 3.0.3. belin;at:leastLHOTJSTANDBYlwithin

thenext[6]ioursl.:

8 3M 3 7 10/30/98 CPSES Markup of CTS 3N.3 l

__._ - .- . . . _ _ . _ _ _ _ _ _ _ . ~ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ - _ . - _ _ . _ _ .

I TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued!

l ACTION $13 Wfthl.:lessithanitheTJtqtquired; Channels 10PERABLEPJrithin;1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ,

datersM4hatzthe: MJacklis2in11tsJrequiredMifor ythe 1-12-M / .

existwment;gendsponsmbe;tn 1EDE;2MtMnjan adj[tieJ g & Re g g; j ACTION 8 - With the number of OPERABLE channels one less than the M4n4 mum gg l- RegMeegChannels 0"E"#LE r;;;ir;;;.-t, pres!gE]hp3dinRest!to MMjet be in at least HOT STANDBY MS45N '

within M 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s: however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification l 4.3.1.1 or maintenance, provided the other channel is OPERABLE. ;

l <

l ACTION 9 - With the number of OPERABLE channels one less than the gg 43.A : 3 M4Mous Required Channels 0"E"XLE requir;;;nt, restore the inoperable channel to OPERABLE status within 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months sy 1

- tr' , m55 3.3LS

ca nitiatetactionth; rr ^ M p 1)yijnsert"allirods;and

br;;icr; within theplace r.;xt7the hour.

Rod C 006 l

l c-www.mant:a condi tantincapable:ot l rod ~wtthdrawal ;

within'.tht3aitxtiheurJ3 ,

ACTION 10 ;- With the number of OPERABLE channels less than the Tct:1 Nur.bcr 2143.gy4 i ef I! equi g Channels!

4 l a; operation may continue provided the inoperable channels are placed in the tripped condition within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months st hogeyerZanIinpper,41e%1cp.iflujd;o1Mpressureittip channelmetypypassed toriupitolhouts3for *.1 11;LS-3 sutve111anceltesting:en othet channelszoc new !!aduceJJERML2N!ERitolless_than:Pi91withinJ0; hours ;

ACTIONJ0;1 Withithe]gumberloL0PERABLE channels 3essithan;the; Required Channels:Lepeteriantayanttinue;provided; a] thGnapereby4pnneware placedlialthe; tripped 1.n.ts conditionNith X Q eu f loE 0 3.3 02 I

b1 ReduceIINER@L" PRto.f]essithanlP-9J WithinJ0 Lhours]

ACTION 11- With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or d;;1;r; the br;;icr inep;r:ble ;nd ;pply ACTION 0 be;1nlat31 east 3 [ 5TAlWB_Y_;within the]iext;6thours. The #1 14iA W1

! breaker shall not be bypassed while one of the diverse trip l features is inoperable except for the time required for

performing maintenance to restore the breaker to OPERABLE status, during which time ACTION 8 applies.

t l

l CPSESMarkup of CTS 3N.3 3M 3-8 10BOM8 l

y- ,

TABLE 4.3 1 (Continued) ;

TABLE NOTATIONS (Continued)

(8) The MODES specified for these channels in Table 4.3 2 are more l

restrictive and therefore applicable.

(9) Quarterly andjprjor@chMjsurveillances in MODEST, 3*, 'gg*y .

4', and 5' shall also include verification that permissives P-6 !

and P 10 are in their required state for existing plant MM -

ions by ;b crvation of th gi;;;i siv; ;nnunciator egg (10) Setpoint verification is not applicable.

11 J J l

(11) T,L_

, *T. ,.1 T. M.m AP1

.1 lmAT. T ..m P1 Lit

M.m .F .ww MMPf*

T Pw f" mm AT. T.w.. w P.T. .L.

Mat A 9T.1* J.._.w_._~_,_ms..11.,..

, agh.q.s

.._~_J,..

r Ywa a5J bsis mL_

nmPo vs ww u. i o. ,. ,n.,w

.3 a vs m

. J ___, ___

b L, m_ us www s vwabuyw unsw

__J

.,L._.

s ru. s b

._J_

ba sy

. A. L . t - - r_ _, AL. ____A__ L__.L___

m. b us.. -. . b ., v. b. m . umm sb._ J. r _ W. _..

(12) Deleted.

I l

__- --- J.J L A L,.

I (13) 1 f J.b . L. .bA L. m. L. .J..._L. ..1..m,__

.v bu ,. ..m_ Ab A . J. _., .. . . - _w WJ.

.,w. J -- .wm =mm w,. . b.~

.1-26 LG a~~

t

enufacturcr. en initial di,;ri;;;inater bia; curv; ;h

11 b;

ur;d for ;;;h det;;ter. Subs;qu;nt discri;;;inster bia; curv;;

h: 11 b; obt:ined cv:lu;ted end ; pred to th; initi:1 curv;;.

! J _ _

T (14) T, L, ~_

A f*T T. M.s. fi m .1 t-A T. T..mhit *Mf.'.*17 .wwTwmmPP AnPn AT. .w..T AAt AT.t f*P,T,

, .L. . .1 1 J, ,~,.,~.u..b J _ _ A 1. ,i , u.3.tg y

..__J,.. nnPn A o ,, ,w _, mu_ .._J _..1. __ __J _ u. . . . . , _

.L.

Tha ssJ ksys w u v me . n.. a s vs bers us ruw. vvabuyv u n uss di vu s b ba sy circuits

.,__ ..__J,..

for th; ",; nuel ",w;;;_,tor.L.Trip m u_ nnPn An ,, o.____" unction. o_t__ The ._J. t;;t shall u s .,w whi asy wasw w wa yw . n. . s s ws barw WJ yu .p d w e w u v+w s bE a ge circuit (s).

(15) Local manual shunt trip prior to placing breaker in service.

(16) 'uto;;;; tic undcrvelt;.,; trip. ;1:32 LG E r

l (17) ]helN~45RSMJstlilliggerAqlLrmedJritMnRhours ::122rM M after'rppgigg gogg$dK&&1erMMJ]lReeland intersecteamespuestregistsammanitalBMp;&giursanec mesemmnesma. - - -

gg 3

1 27 LS i L " ~ - ~

l TR 3.3 006

. . . _ . _, m _ m .

_ Jo t[ feq ?g81 dlptjor.,30: enter]ng

_ _ . u.__fl0DE121gt11141houtsjeftigem!rfngJint@0 DEW (18). Includes ~yetjficatjonlofitimelconstantsEMerelappli, cable 7 m23 A M i

r i

I CPSESMarkup of CTS 3M.3 3M 3-15 10/30/98

- _ .- - _-. . ~_ _ _ - --. _ . - - .. - . ._

CHANGE NUMBER HSE DESCRIPTION 1evels greater than the MODE 2 to MODE 1 breakpoint, there l 1s no need to retain the current TS 4.0.4 exception, as l l

! discussed in ITS Section 1.4. as long as the ITS l l Surveillance Notes allow the plant to reach conditions !

appropriate for the performance of the surveillances.

The power level at which the monthly surveillance is performed to compare incore vs. excore AFD and adjustment l

of the NIS as required by Note (3) of current TS Table i 4.3-1 is changed from a 15% RTP to a 50% RTP. This l

change is also precipitated by the conversion to the ITS l format which replaces the current TS 4.0.4 exception with a finite time interval after exceeding a specified power level. With the deletion of the current TS 4.0.4 exception, the specified power level in ITS SR 3.3.1.3 i l

should reflect the applicable safety analysis basis consistent with the [ Applicability and] Required Actions '

of ITS LCO 3.2.3 (AFD) and LOC 3.2.4 (QPTR). As with the changes discussed above, there is no need to retain the current TS 4.0.4 exception as long as the ITS Surveillance Notes allow the plant to reach conditions appropriate for the performance of the surveillances.

These changes are cen;id;.r;d ed;inistr;tive more 1 nstfjgLtjwjin nature in th;t they ;i; ply reflect the o.1 25 incorper; tion of sincejthe current TS 4.0.4 exceptions greJot91mitid".3i nto th; i;pr;V;d '5.

1-26 LG This change moves the details concerning NIS detector calibration to the BASES for ITS SR 3.3.1.11, consistent with NUREG 1431 Rev.1. This information is more appropriately controlled outside of the TS while the calibration requirement itself and its Frequency are unchanged.

1 27 LS 10 Surveillances on the Source Range Neutron Flux trip function are reorganized to reflect plant status in accordance with NUREG 1431 Rev. 1. New Note [(17)]

requires that the quarterly COT be performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reducing power below the respective source range instrumentation Applicabilities, if not performed within the previous [92] days. Since the COT is valid for

[92] days, there is no need to repeat it if one has been performed within the prior [ quarter]. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months allowance permits a normal shutdown to proceed without a delay for testing in MODE 2 and for a short time in MODE 3 'mH1/illfods;a!wgul,1y;teserlted ancPg l@

_ M Coptfpl[syst g is L T_ M.1nceMble!qfjud T l

@thdtaRbEla_fteghich the " =P ' " R ;kers Eg/

epen;d r A u... u .y .unulon no longer provioes l

protection. Since the current CPSES Description of Changes to CTS 3M.3 9 10B0/98

i r

CHANGE NUMBER liSiG DESCRIPTION more appropriately controlled outside of the TS while the underlying requirement to verify proper permissive operation is unchanged.

l 1 53 A Currcnt TS Tcbic 3.3 1 ACTION Stctc cat [2.c] i revi;cd tc bc ccasistcat esith ITS 5",3.2.4.2. cs ll 0 3.3-120 discusssd in CN 4 04 L 12 in 'hc 3/4.2 pcckcgc. Not

, used l 1 54 LS 37 Not applicable to CPSES. See Conversion Comparison Table ;

l (Enclosure 3B).

f 1 55 LS 39 [ Applicability Note [a] and] ACTION Statements [5 and 9] l for Functional Units [1, 6.a.2),19. and 20] of current TS l

Table 3.3-1 are modified to provide an alternative to l

l opening the reactor trip breakers (RTBs) while still l

assuring that the function and intent of opening the RTBs is met. As currently worded, these ACTION Statements result in a feedwater isolation signal (FWIS) when in H0DE 3 with a Tm less than f564*F.1 A more generic n-3.3 006 action, which mquTres.that action _be,taken W

assures the rods are iuilj incerted cnd cm be l, withdrawn replaces the specific method of precluding rod l l withdrawal. The revised Applicability and ACTION l Statements still assure rod withdrawal is precluded. This change does not involve any safety impact and is consistent with traveler TSTF-135.

1 56 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38).

l i 1 57 LG Current TS Table 3.3-1 Functional Units [12.a and 12.b]

are combined per traveler TSTF-169. The Required Channels, ACTION Statement, and Surveillance Requirements are the same for both Functional Units. The only difference between the two is the Applicability which t

could lead to entry into ACTION Statement 6 for Functional

! Unit [12.a]. followed by a power reduction below P-8, exiting the Applicability and required actions for that

Functional Unit, and subsequent re-entry into ACTION Statement 6 for Functional Unit [12.b]. This would involve an improper cumulative A0T of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months before l tripping an inoperable channel, beyond that evaluated in WCAP-10271 and its Supplements. The relationships between these Functional Units and permissives P 7 and P 8 are moved to the ITS 3.3.1 Bases.

1-58 A In the SRs for RTS and ESFAS response time testing, the the active verb is changed from " demonstrated" to i

4

" verified." This change would allow Reactor Trip System CPSES Description of Changes to CTS 3/4.3 13 10/30/98

IV. SPECfFIC NO SIGNIFICANT HAZARDS CONSIDERATZONS NSHC LS-10 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES E AT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Surveillances on the Source Range Neutron Flux trip function are reorganized to reflect plant status in accordance with NUREG 1431 Rev.1. New Note [(17)] requires I that the quarterly COT be performed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reducing power below the respective source range instrumentation Applicabilities, if not performed within the previous [92] days. Since the COT is valid for [92] days, there is no need to repeat it if one has been performed within the prior [ quarter]. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1

! allowance permits a normal shutdown to proceed withnut a delav for testing in l H0DF 7 and h = ^ ~+ + % in MODE 3 until/$Tj:rodslate W ] h Cjnsergea;and. pie TR 3.3 006 l 20dlContr_))$)stealisfrenderfdiincapabl.eloffrod)1thdraWal3fterlihfch 0 the i

"ccctor Tr'o Src;kcr: Orc cacncd ;nt uns trip iuumun av lun w pruviaes l

protection. Since the current TS has no Specification 4.0.4 exception this 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months allowance is less restrictive.

I The proposed TS change has been evaluated and it has been determined that it l

involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

"The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility f licensed under 50.21(b) or 50.22 or for a testing facility involves no l

significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or l

2. Create the possibility of a new or different kind of accident from any !

accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

3 J

CPSES No Significant Ha:ards Consideration - CTS JN.3 31 1020/98

TV. SPECIFIC NO SIGNTFICANT HAZARDS CONSIDERAT10NS NSHC LS 39 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Applicability Note [a] and ACTION Statements [5 and 9] for Functional Units 026a

[1, 6-b-6ta;2) 19. and 20] of current TS Table 3.31 are modified to provide an alternative to opening the reactor trip breakers (RTBs) while still assuring that the function and intent of opening the RTBs is met. As currently worded, these ACTION Statements result in a feedwater isolation signal (FWIS) less tha_n [564_*F.] A more generic action, which TR 3.3 006 Aw an h MnnF 1 with a Tm ssures tne roos are fully inserted and cannot Cregerires'thatcaction be;takenfto}ic method of precluding rod withdrawal.

be witnarawn, replaces um wa The revised Applicability and ACTION Statements still assure rod withdrawal is precluded. This change does not involve any safety impact and is consistent with traveler TSTF-135. The proposed change allows more freedom in how rod withdrawal is precluded and is thus less restrictive. However, the intent of using physical plant l characteristics to prevent rod withdrawal is not diminished. The specification now acknowledges that the Rod Control System can be effectively disabled by 0 3.3-122 means other than opening the RTBsEe.gMby;defenergizingiall CRDMs,lopening thejRTBsEoride energizing;the motorJgeneratorf(MG)1 sets. i This proposed TS dunge has been evaluated and it has been determined that it involves no sigraficant hazards consideration. This determination has been !

performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

"The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new cr different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant l

hazards consideration standards:

Does the change involve a significant increase in the probability or j 1.

consequences of an accident previously evaluated? l The proposed change does not alter the requirement to preclude rod withdrawal using physical plant characteristics. The specification does not allow administrative control or other means which could be conceived as less CPSES No Significant Ha:ards Consideration - CTS 3M.3 61 10B088

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-19. Rev. 1 Not Incorporated NA Not NRC ;pproved as of ,

cut off dott. W oved I"1 JA 3 '

bythe;NRC]Ba~ses changes"Jonly.

T N 30. ncv 2 Iracrpreted M R0-3.3 34 l TSTF-37, Rev. 1 Not Incorporated NA ITS 5.6.8 still addresses PAM reports. Sections after ITS 5.6.7 were not renumbered.

TSTF 51 Not Incorporated NA Requires plant-specific reanalysis to establish decay time dependence for fuel i handling accident.

TSTT 01 Not Ir.ccrporated NA [ ] Alicw;bic '.'alue: 1 TR 3 3 005 for ic;s of voltog; :nd I - -- - - - - -

dcgraded volts;; will rcrcin in th; TS.

TSTF 111, Rev. 1 Incorporated NA _

3 TSTF 13 ,;.Rev2 3 Pertially 3.3 41. Tr;;;1cr is to; breed I-006 )

Incorporated 3:3L44, scop in naturc; I 3DjN.? ;hculd h;vc bccn 313-91; several ;;perate trovcicr;.

7 3.395. Portion; cf the tr;vcler th;t 3.3 95, significantly clarify 3.311067 sperability requir;; cats h;ve 3.3-122, bcca incorporated.

3;31142 Incorporated 3.3-79 ApproyedlbKtheCNRC l .TSTF-161,Revfil I

Incorporated 3.3 43 ApprovedbftheNRC l 0 3. -43 l ,

TSTF-168 J l

l l Incorporated 3.3 42 Approved bytthe;;NRC2 TR-3.1-003 TSTF 169 Incorporated 3.3 49 i o.3. .49 l '401003STFZ242 l su num mammes l

Incorporated 3.3 107 "0C tiini-Croup A; tion o 3.. 107 TSTE.946;rropcs;d 4 t7;;cier Itat #145.

l

P RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.11 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.11. ,

l 1

ACTIONS

....................................... NOTE -- --

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME I

i A. One or more Functions A.1 Enter the Condition Immediately l with one or more referenced in Table .3.1 1 for the channellsVor 3.3 142 r ed channels ^~

TR 3.3-006

.rajes inoperable. q (s1 B. One Manual Reactor Trip B.1 Restore channel to OPERABLE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months channel inoperable. status. j 08 B.2-1 Be in H00E 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months x3:3-106 i i

6HB 3.2.0 Cpcr rccctor trip 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months becakcr (il":;) .

l (continued) i e

CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-1 10BOR8 i

_ - - . . - - = _ _ - ._ - . - . --

1 i

RTS Instrumentation

' 3.3.1 f

t

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l

EiEEF_iHMEEECSEEE BWIC3RRes1EsoKpet 3.3 13s sn 1 . w s al a ir A 03.3135 6

assamuum'usenEV m 213IS N C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 6...

~-

um..u

.= x.u ~~. w za OPERABLE status.

??AuriabO:Hidicr5 08 r

C. One channel or train IC.2.1 0 a ""shtiateh ours 3.3 122 inoperable. Ca~ctionitoffGily,finsert TR 3.3 006 al]itods; -

ate 4Kj!ours. M3.3 1224 c;212 Place 3Migod39meol liystenMLeondjgon mcapable'ofmod ;

MtlWtM12 l 1

l I

1 i

3.3-2 10B088 CPSESMarkup ofNUREG-1431 - ITS 3.3 1

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. One Source Range Neutron I.1 Suspend operations involving Immediately Flux channel inoperable. positive reactivity additions.

J. Two Source Range Neutron J.1 0 rea.Ctor;trtp;tireakers Immediately g Flux channels .TBsl. n.3"3 006 inoperable.

K. One Source Range Neutron K.1 Restore channel to OPERABLE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Flux channel inoperable. status.

DB K.2;I 0= "S3 J hours dictionTtofruuyansett 3.3 122 m.3.3.w6 ajkr_cos.:

aim 491hoyrs ':' 3.3e122 5 KI2;2 PlaceltheiRod; Control systealin'a;conditio.g in_capattle orrod Withdrawa1; CPSES Markup ofNUREG-1431 - ITS 3.3 3.34 103088

RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 1 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES SURVE!LLANC E f*fe .; s ,

OR DTHER ALLOWABLE GE4PGIM"

-4 SPECIFIED REQUIRED REQUIRUMENT FUNCTION CONDITIONS CHANNELS CONDITIONS S VALUE"'

1. Manual Reactor 1,2 2 B SR 3.3.1.14 NA NA Trip 3 , 4*', 5 *' 2 C SR 3.3.1.14 NA NA

2. Power Range Neutron Flux

a. High 1,2 4 D SR 3.3.1.1 D11;7%RTP . ' = :: "f8-PS Mi SR 3.3.1.2 M4 2 SR 3.3.1.7 SR ,.3.3 55 i

__. 3. .3,.1.

. . . 11,

b. 1(C), 2 4 E SR 3.3.1.1 i'27.7%RTP s'-259Htte # 6 P$ :"'$

Low SR 3.3.1.8 Ehe SR 3.3.1.11

= :.:. .;:,

23.3 551

3. Power Range Neutron Flux Rate e- High Positive 1,2 4 E SR 3.3.1.7 k,'6;3 tre v + *te Rate SR 3.3.1.11 % RTP W: ... . . . -

with time constant F O*Ib D constant t-E see 2 2 sec L. . : :. _.._ ave v + e :.:33.}?, ;;;.::3:r . ;;;: ;

33,3413 Ree,

= :.:.: ::. eenetene coneeene 2 ::: ..c a ::: aec

4. Intermediate Range 1 , 2 '" 2 F,G SR 3.3.1.1 k31:51 . = :: pgep37; Neutron Flux SR 3.3.1.8 5+% RTP SR 3.3.1.11 a~ e *

5-+ + ::: ::: - = :: c3,3 95 A

.m . . . , . . . . ,

= :.:. .;;

(continued)

(c) :.. . . . ' e ;;a. . L;. . . ; er c . f ; c ..,,L.. . .; a 6-.; ._, . .; . ; , . .; , ;,; ; .:.,; . V. 6 a, . .J , . . "; ;,~ ; . ;

"3.3708m

J, _3..,J.,; , ..J L, .

.e . ;. The AllowablelfstlW: defirmiltbe:11miting~tefetraystem: setting; 9es:9NC9eosa;fotlthe~7 rip:5etpoints; ^

(b) :...; ; :..,,;...L.,e ;;;;.; ;.,..J . J Rod Control System capable of rod withdrawal or one o 3.3 122 TristiM193nserted! TR 3.3 006 l (c) the P-10 (Power Range Neutron Flux) Interlocks.

(d) Above the P-6 (Intermediate Range Neutron Flux) Interlocks.

.;: ;; 6 .:.. r :, ;;.;.. --J:a . :. . :. a,.,c ; ) . . . ... ; ,&er <3:3.:954 CPSES Markup ofNUREG-1431 - ITS3.3 3.3-16 10/30/98

l RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER Nttf g"g4 SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE GE4POWi" FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE" i

l 1

1,J SR 3.3.1.1 s 1.4 E5 e-+;9-E5 2* " ' "gbg"- .

5. Source Range 2 ~c-Neutron Flux SR 3.3.1.8 cps epe

@}*{a]- S3963 I 3*,4*,5* 2 J,K SR 3.3.1.1 $114 E5 = ..: :: e wg '.q' ' i SR 3.3.1.7 cps epe SR 3.3.1.11

                                                                                                     = :.: . =                                                       W3.3+555!

a*r.4*r-s* e e = :.:.: .- e e t3.3 41u

                                                                                                       .. ....i I

6. Overtenperature et 1,2 4 E SR 3.3.1.1 Refer to Refer-to ; p 'g a q~

N-14 sR'.3.3.1.2 Note 1 M SR 3.3.1.3 teege teo9e SR 3.3.1.6 575-i%t 5-5-i%t 13 M30 A SR 3.3.1.7 SR.3,.3. 1. 10

                                                                                                                                                                         '>3i3-50 i         ,

1

                                                                                                      --r
                                                                                                            ......r6 e323-551              i j

i

7. Overpower et 1,2 4; E SR 3.3.1.1 Refer-te Refer-te p -a g g 3 Pj4 SR13;1~.2 Mote-2 Note-f ;

SR 3.3.1.7 (Pete tPege 3R I 3;1;10 ,5-5 5-5-25t r$;3005!

                                                                                                      ;; : ." 1                  5114;3X O3 I* M 3: 3.3.1 16                   RTP (continued)

(c) :. . , ;- . . ;.. ; . u.... .,,. ;,,. ...v; - ,,;.;.... ,_ , .. .; . , , , . .; , ;,; ; - L'. . v. ; J.r.. ,J ; . , 0. ; r ,, ,; P 3.3*M d

        ;; , . G,.c.,;,, eed           L, J..     .: . The A(Touable^Volue'defirpCthaltimitlegf ssfety; system setting; SNrW~aeseCfor;the "T risi Setp61nts ;                                                                          -
                      ; ,..J ...; Rod Control System capable of rod withdrawal or Q one Tr                                              'motifully (b) W                                                                                                                                                           3.3 122 TR 3.3 006
 -()    Below the P-6 (Intermediate Range Neutron Flux) interlocke.

l ; a ;: ... n. :=. , . . ... . : . . .; . : . , . . . . . . .. . .c ; . . , a- . . .. ; r. . . , ;. . .c ; ,, . . , r : ; ;- .

r. .. ;c ,, v ; ;, ,:.. :.. . . c ; ; . . ;..; ' ,,,, ;, ;.c, ;L= : .:.;;, . .

,,J a.u .. ,.

CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-17 10/3088

RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 6 of 9) Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SURVEILLANCE ALLOWABLE tett SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE" GE4 94M "' p.g;gg 2 trains o SR 3.3.1.14 NA M

17. Safety 1,2 Injection (SI)

Input from Engineered Safety Feature Actuation System (ESFAS)

18. Reactor Trip System Interlocks

a. Intermediate 2* 2 S SR 3.3.1.11 2 6E-11 amp 1-4E-40 e- rB.M SR 3.3.1.13 anp Range Neutron Flux, P-6

b. Low Power 1 1 per T NA 1 die NA 3.3 54 train SR 3.3.1.5 M Reactor Trips 3;; 2.2.1.;; 0 3.3 54 Block, P-7 e;; 3.3.1.;;

454 T 5the

c. Power Range 1 SR 3.3.1.11 ss50.75 RTP . : , ::r E 8;PS M Neutron Flux, P8 SR 3.3.1.13

d. Power Range 1 454 T SM .=:7 6-3-44 Neutron Flux, SR 3.3.1.11 's52.7% RTP g.3.3-44 P9 SR 3.3.1.13

e. Power Range 1,2 454 S ,, he a in nr Mg.p$ pg Neutron Flux, SR 3.1.1.11 Y L 33 RTP P-10 SR 3.3.1.13 and 4iNE ;p;g.p$ py dJZ.75 RTP 2 T 4M r-40% <.p$ y 3

f. Turbine 1 terrbhw taprtse Ef ret M :.3.1.0 sJ2.7X SR 3.3.1.10 turbine power A S.PS ~ ;

Stage SR 3.3.1.13 power Pressure, P-13 1,2 2 trains R SR 3.3.1.4 NA M

19. Reector T g Breaker k) 3* , 4, 5 " 2 trains C SR 3.3.1.4 NA W TR 3.3 006 (continued)

(c) ;;m L_,.'.

                                    ; ;.. ;,... . m ;f..           ...v;...~,.;.;. .. ._ , . .i ; . . .; 7 :. ; ; - A V. 6 a,~ .J . . , . . R Wtre                                                           3.3-g A
            ;; J, _;;.#,                 ,  ..J L,    :.       .;;. The. Allowable .ValueTdefines,thelIlmitlWssfety?systesOsetting; See
                                                                                                                    ~

the.teipsiforiShelrlpTSetpointel rodslFetJfut(y (b) With ;;;;. .;.aJ ->.d Rod Control System capable of rod withdrawal ork one;cr truerted; (2) Below the P-6 (Intermediate Range Neutron Flux) interlocks. ~ (k) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. 3.3 122 TR-3.3-006 CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-21 10/30R8

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 9) Reactor Trip System Instrtmentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVE!LLANC ALLOWABLE f*fe FUNCTION CONDITIONS CHANNELS CONDITIONS E REQUIREMENT VALUEco SE#94M" _g j S

20. Reactor Trip 1,2 1 each U SR 3.3.1.4 NA M Breaker per RTB Undervoltage and Shunt Trip 3 , 4, Si 1 each C SR 3.3.1.4 NA M Mechanismsaa per RTB ;,3,3.g4 y;

21. Automatic Trip 1,2 2 trains Q SR 3.3.1.5 NA M Logic 3 , 4 * , 5 2 trains C SR 3.3.1.5 NA M

                          ._. __     - - ...... .- .                    ..-_.----.s, co) ::.... .^. ;et.. u. . . ., . . . ,              . . v ; ...~ . . . ; . . .. . , .. .: . . . . _ . ; , ; ; ; -.: : . ;. ; _ J., . .J . . . . ;. :,~            .:          N' 3;3-084
       ;;; ;,        u. a ;,,,, .; L, u..               .:: Tiit:At tesikble yaluaMfjnKthe35miting[setetiGavstemTeettjng; Esi3hiGaliiCfoCtWTtip petpojnts;                                                                                                          e (b)          Rf9s-etose& and Rod control System capable of rod withdrawat                                                              eni. loc          notifuy (k) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

i 1 l CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-22 10B0/98 i

RTS Instrumentation i 8 3.3.1 f BASES

1 The decision logic matrix Functions are described in the (

functional diagrams included in Reference 1. In addition to the i reactor trip or ESF, these diagrams also describe the various

                          " permissive interlocks" that are associated with unit conditions.                    :

' Each train has a built in testing device that can automatically test the decision logic matrix Functions and the actuation i devices while the unit is at power. When any one train is taken l out of service for testing, the other train is capable of providing unit monitoring and protection until the testing has been completed. The testing device is semiautomatic to minimize testing time. APPLICABLE The RTS functions to maintain the applicable Skr-limi_ts during SAFETY ANALYSES, all A00s and mitigates the consecuences of nRAs in all MODES in LCO, and _ _ j;ontrol.lsystenjiisicapableloQod,yithdrawallor;on]e ' APPLICABILITY; onsoreitodslareMtifullylinserted. n.. ..s . . _ . f TR-3.3 006 l Each of the analyzed accidents and transients can be detected by one or more RTS Fun:tions. The accident analysis ; described in Reference 3 2 takes credit for most RTS trip Functions. RTS trip Functions not specifically credited in the accident analysis are qualitatively credited in the safety analysis and the NRC staff approved licensing basis for the unit. l These RTS trip Functions may provide protection for conditions l that do not require dynamic transient analysis to demonstrate i Function performance. They may also serve as backupAridiverse trjps to RTS trip Functions that were credited in the accident I analysis. The LCO requires all instrumentation performing an RTS Function, listed in Table 3.3.1-1 in the accompanying LCO, to be OPERABLE. Failure of any instrument renders the affected channel (s) inoperable and reduces the reliability of the affected Functions. The LCO generally requires OPERABILITY of four or three channels in each instrumentation Function, two channels of Manual Reactor Trip in each logic Function, and two trains in each Automatic Trip Logic Function. Four OPERABLE instrumentation channels in a two out of four configuration are required when one RTS channel is also used as a control system input. This configuration i j accounts for the possibility of the shared channel failing in such a manner that it creates a transient that requires RTS action. In this case, the RTS will still provide protection. ' (continued) B 3.3-7 10/30/98 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

RTS Instrumentation B 3.3.1 BASES APPLICABLE even with a random failure of one of the other three protection ; SAFETY ANALYSES, channels. Three operable instrumentation channels in a l LCO, and two of three configuration are generally required when there is APPLICABILITY no potential for control system and protection system interaction l ~ (continued) that could simultaneously create a need for RTS trip and disable ! one RTS channel. The two-out of three and two out-of four configurations allow one channel to be tripped orl)ypassed i CP-3.3 009 during maintenance or testing without causing a reactor trip. Specific exceptions to the above general philosophy exist and are discussed below. Reactor Trio System Functions The safety analyses and OPERABILITY requirements applicable to each RTS Function are discussed below:

1. Manual Reactor Trio The Manual Reactor Trip ensures that the control room operator can initiate a reactor trip at any time by using either of two reactor trip switches in the control room. A Manual Reactor Trip accomplishes the same results as any one of the automatic trip Functions. It is used by the reactor operator to shut down the reactor whenever any parameter is rapidly trending toward its Trip Setpoint.

The LC0 requires two Manual Reactor Trip channels to be OPERABLE. Each channel is controlled by a manual reactor trip switch] i;;2;;;;tip,. wits. Each channel activates the reactor trip breaker in both trains. Two independent channels are required to be OPERABLE so that no single i random failure will disable the Manual Reactor Trip l Function. In MODE 1 or 2. manual initiation of a reactor trip must be l OPERABLE. These are the MODES in which the shutdown rods and/or control rods are partially or fully withdrawn from the core. In MODE 3, 4, or 5, the manual m.3.3 p06 initiation Function must also be OPERABLE ifg

                              ,6r morelhutdown or control rods are withdrawn or the                                 f d   -m         .- m    ..m  -, Rod Contro4ystem is capable of withdrawinn tho thutdown rods or the control rod and'1f 611 rodsratelfuljy; inserted In this condition, ina vertent control i vu ,,d.i.21 1s possible. In MODE 3. 4. or 5.

manual initiation of a reactor trip does not have to be OPERABLE if thgRod Contro} System is not capable of withdrawing the continued B 3.3-8 10B088 CPSESMarkup ofNUREG-1431 Bases -ITS3.3

RTS Instrumentation B 3.3.1 BASES APPLICABLE shutdown rods or control rods dfE@elWods"tre;fuliy SAFETY ANALYSES,; nsettedNftherodscannnt/bawithdrawnfromthecore LCO, and anl RU h r p m $ % C ~ M there is no APPLICABILITY new w pe apie to trip the reactor, because all of the rods (continued) are inserted. In MODE 6. neither the shutdown rods nor the control rods are permitted to be withdrawn TR 3.3 006 and the CRDMs are disconnected from the control rods and shutdown rods. Therefore, the manual initiation Function is not required.

2. Power Ranoe Neutron Flux The NIS power range detectors are located external to the reactor vessel and measure neutrons leaking from the core.

The NIS power range detectors provide input to the Rod , Control System and th; Stc;; Ccacrator (SC) " tcr L aci Control System. Therefore, the actuation logic must be j able to withstand an input failure to the control system, 1 which may then require the protection function actuation, l and a single failure in the other channels providing the protection function actuation. Note that this Function also provides a signal to prevent automatic and manual rod withdrawal prior to initiating a reactor trip. Limiting further rod withdrawal may terminate the transient and eliminate the need to trip the reactor.

a. Power Ranae Neutron Flux-Hiah The Power Range Neutron Flux-High trip Function ensures that protection is provided, from all power levels, against a positive reactivity excursion leading to DNB during power operations. These can be caused by rod withdrawal or reductions in RCS temperature. i The LC0 requires all four of the Power Range Neutron Flux-High channels to be OPERABLE.

In MODE 1 or 2, when a positive reactivity excursion could occur, the Power Range Neutron Flux-High trip must be OPERABLE. This Function will terminate the reactivity excursion and shut down the reactor l prior to reaching a power level that couldlesult i in Lan unacceptabl.efjeveEnf damagelto the fuel. I CP 3.3 ED j In MODE 3, 4, 5, or 6. the NIS power range l detectors cannot detect neutron levels in this range. In these MODES, the Power Range Neutron Flux-High does not CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-9 10/3038

RTS Instrumentation B 3.3.1 BASES APPLICABLE Because this trip Function is important only during SAFETY ANALYSES, startup, there is generally no need to disable channels for a LCO, and testing (geneggWPJggggeplet;goupf,Je!!qsJp3gterlthan ) (continued) thelP306MAttpoggt: m 2wh11e3 the Function is required to be OPERABLE. Therefore, a third channel is unnecessary. In H0DE 1 below the P 10 setpoint, and in H0DE 23bygelthe IE6IngReint, when there is a potential for an uncontrolled RCCA bank rod withdrawal accident during reactor startup, the Intermediate Range Neutron Flux trip must be OPERABLE. Above the P 10 setpoint, the Power Range Neutron Flux-High l Setpoint trip and the Power Range Neutron Flux-High Positive Rate trip provide core protection for a rod withdrawal cr

a+ Ta Mnnr2 beloW1theT6 setooi ~ ,_he;SourceJange~Neutronmux3rjpfunction TR 3.3 006 rovidesrcore~ protection;for: reactivity ~ accidents 7 In1 MODES d . *. or o Ine intermediate Range Neutroh riux trnp does not have to be OPERABLE because the control rods must be fully inserted and only the shutdown

'                                    rods may be withdrawn. The reactor cannot be started up in this condition. The core also has the required SDH to mitigate the consequences of a positive reactivity addition accident. In H0DE 6. all rods are fully inserted and the core has a required increased SDH. Also, the NIS intermediate range detectors cannot detect neutron levels present in this H0DE.

5. Source Ranae Neutron Flux j l

The LCO requirement for the Source Range Neutron Flux trip Function ensures that protection is provided against an uncontrolled RCCA bank rod withdrawal accident from a l saberitical condition during startup. This trip Function provides redundant protection to the Power Range Neutron Flux-Low Setpcir.t and Intermediate Range Neutron Flux trip Functions. In H0 DES 3, 4, and 5. administrative controls also prevent the uncontrolled withdrawal of rods. The NIS source range detectors are located external to the reactor vessel and measure neutrons leaking from the core. The NIS ' source range detectors do not provide any inputs to control systems. The source range trip is the only TR 3.3 006 RTS automatic protection function required in MODES 3. 4 and 5 With;theiRod' Control'Systemicapabje;of2pd withdrawaEo,r;WithMH;one;orteore s])otIful1ylinsertedj Therefore, the functional capauinty the specified Trip Setpoint is assumed to be available. - B 3.3-13 108088 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

i RTS Instrumentation B 3.3.1 I BASES l APPLICABLE 5. Source Ranoe Neutron Flux (continued) , SAFETY ANALYSES, LCO, and The LC0 requires two channels of Source Range Neutron (continued) Flux to be OPERABLE. Two OPERABLE channels are sufficient l to ensure no single random failure will disable this trip Function. ";; LOO ci;; r;quirc; ea; chenici of the Scur;;

                               "en g "cutron n ux to b; 0"C"M LE in "00 3. 4. er S with
                               "";egn. In thi; ;;;;;. the ;;ur;; rr.ng Tunction i; t; previd; ;;atr:1 rce; indication erd input to tre ";rea Oilution "retecti;n Sy;tc; '"0"S). The outputs of the Function to RTS logic are not required OPERABLE igMJ                                         i ten the "?"; er; egnLet[Ldleg310903tMOGly29gsetted                                         i andAM$ghttoglidgemXJgcapit@pyMRittjtitelsal .                                               l The Source Range Neutron Flux Function provides protection for control rod withdrawal from suberitical, beren dilution and control rod ejection events. The function el;;

l provid;; vi;;;; rautrea flux indi;;tica in th; ;;atr:1 reen-In MODE 2 when below the P 6 setpoint during a reactor ! i l l startup, the Source Range Neutron Flux trip must be OPERABLE. Above the P 6 setpoint, the Intermediate Range Neutron Flux trip and the Power Range Neutron uip =iii pi unoe core protection l Flux-L@ivity for react accidents. Above the P 6 setpoint, the NIS source range detectors er; d; crergized end ire g rebic. saghpigagallEldo@eplEMtF112tiloMtgp]3pge3tip tungtonW blo@ed1the3fghL@ltaggojetitupp]fis resqHpp] nMODES4,4, with the rc;;ter ; hut de.;, Rod L CoggggL M i.. Jp3![3ndigitgilegK7.,.l 7 g u .3.3 0 l {g3gigggtJgl}Qgggtpgl, the Source Range eu ron l' l Flux trip Function must also be OPERABLE. If the GAD l , Rodt=**m1TSystem CC.";; r Jtne Source Range is capable Neutron _ofFluxrodtrip withdrawalhi l must be OPERABLE to provide core protection against a rod l withdrawal accident. IftheGRBRod;GontN1Systemisnot l J capable of rod withdrawa1 Q e R & .. u .i m ;.L.r;;" the source range detectors are not requireo 1.o trip tne i reactor. However, jtMs; good;ptactjoelfodtheir monitoring Function mest to;be OPERABLE to monitor core neutron levels l I and provide indication of reactivity changes that may occur as a result of events like anlinadvertent boron dilution. Tre:;; input; er; provided to the "0"S. The requirements ! for the NIS source ( B 3.3-14 10/30/98 CPSES Markup ofNUREG-1431 Bases - ITS 3.3 L _ .

RTS Instrumentation B 3.3.1 BASES The Turbine I;;;puls: Fast,1tage Pressure. P 13 interlock is actuated when the pressure in the first stage of the high pressure turbine is greater than CP 3.3 ED

                                   ;ppraintcly                     -1J-3]10% of the rated full power pressure.3sIDJLMhteryssponds                                              I t!s.@st                                           T@se                          l 13$elgggBts is determined by one out of two pressure                            l detectors. The LCO requirement for this Function                               l ensures that one of the inputs to the P 7 interlock is available.

The LC0 requires two channels of Turbine !;pulscljtst Stage Pressure, P-13 interlock to be OPERABLE in MODE 1. l The Turbine I;;; pulse ChabcifirstJStage Pressure, P 13 interlock must be OPERABLE when the turbine generator is operating. The interlock Function is not required OPERABLE in MODE 2, 3, 4, 5, or 6 because the turbine generator is not operating.

19. Reactor Trio Breakers This trip Function applies to the RTBs exclusive of individual trip mechanisms. The LCO requires two OPERABLE trains of trip breakers. A trip braicr trein ansists of all trip brukers associated with ; single RTS logic train that orc racked in. !

closed, end sp:bic of supplying p;Wcr to the CR0 Systc;. Thus, the tr in n y a nist ;f th; =in bru kcr er bypen br aici er min braicr end bypu s brukcr. dcpading upon the systc; a nfiguration. Two OPERABLE trains ensure no single random failure can disable the RTS trip capability.

19. Reactor Trio Breakers (continued)

I These trip Functions must be OPERABLE in MODE 1 or 2 Wha th; rcseter is critical. In MODE 3, 4, or 5, these RTS trip Functions must be OPERABLE when the ! ' R":; er anecisted bpas braicrs ;rc ci;scd, and the C40 thelRo(Contrt0FSystem 1 capable of rod withdrawal;or@Mor moore _ods are notifullylnserted.

20. Reactor Trio Breaker Undervoltaoe and Shunt Trio neuim .sms The LC0 requires both the Undervoltage and Shunt Trip !

Hechanisms to be OPERABLE for each RTB that is in service. ! i continued i I CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-34 10/30/98

RTS Enstrumentation B 3.3.1 BASES The trip mechanisms are not required to be OPERABLE for trip breakers that are open, racked out, incapable of supplying power to the GRB RadiControlSystem, or declared inoperable under Function 19 above. OPERABILITY of both trip mechanisms on each breaker ensures that no single trip mechanism failure will prevent opening any breaker on a valid signal. These trip Functions must be OPERABLE in MODE 1 or 2-when the reacter is critical. In MODE 3. 4, or 5. these RTS trip Functions must be OPERABLE when .~ ..~ m m associetcd byp;ss brc hcrs are cicscd. ;r.d the C",0 the R_od" Control, System is capable of rod withdrawal [or m.3.3 006

                             @gQ{rodsTare30tifu]ldnserted.

21. Automatic Trio loaic i

The LCO requirement for the RTBs (Functions 19 and 20) and l Automatic Trip Logic (Functior 21) ensures that means are l provided to interrupt the power to allow the rods to fall into the reactor core. Each RTB is equipped with an undervoltage coil and a shunt trip coil to trip the breaker open when needed. Each RTB is equipped with a bypass breaker to allow testing of the trip breaker while the unit is at power. The reactor trip signals generated by the RTS Automatic Trip Logic cause the RTBs and associated bypass breakers to open and shut down the reactor. The LC0 requires two trains of RTS Automatic Trip Logic to be OPERABLE. Having two OPERABLE channels ensures that random failure of a single logic channel will not prevent reactor trip.

21. Automatic Trio Locic (continued)

These trip Functions must be OPERABLE in MODE 1 or 2 wher, the rc;; tor is critical. In MODE 3, 4, or 5, these RTS trip Functions must be OPERABLE when the m-3.3 006 RTBXandiassociateQypass)reakerslare;closedgand thelGRBJt}}e:Ilod Control Syst_em is capable of rod withdrawali,or 'loteo odsfarejnogfully insetted. _ The RTS instrumentation satisfies Criterion 3 of 10CFR50;.36(2)(c)(ii). 8 3.3-35 IW3W98 CPSES Markup ofNUREG-H31 Bases -ITS 3.3

RTS Instrumentation B 3.3.1 BASES with a trip Function then the unit is outside the safety analysis. Therefore, LCO 3.0.3 must be immediately entered if applicable in the current MODE of operation. Rcvic.;cr's Netc. Certain LCC C a piction Tin ; erc b; x d on

                         ;pprovcd t;pical icperts. In ordcr for ; liccax; to un the:c ti n :. th; li a nxc = ;t ja:tify the C a piction Ti n ; ;; requircd by the ;t:ff S;fcty Ev;1acti;n Rcpert (SER) f;r the topical repert.

IL1 Condition A applies to all RTS protection Functions. - TR-3.3-006 Condition A addresses the situation where one or more p required channelshtrainsJor one or more tuncuans are inoperable at the same ume. The Required Action is to refer to Table 3.3.1-1 and to take the Required Actions for the protection functions affected. The Completion Times are those from the referenced Conditions and Required Actions. B.10and B.2.1. and S.2.2 Condition B applies to the Manual Reactor Trip in MODE 1 or 2.

This action addresses the train orientation of the SSPS for this Function. With one channel inoperable. the inoperable channel l

must be restored to OPERABLE status within 48 hours. In this Condition, the remaining OPERABLE channel is adequate to perform the safety function. l The Completion Time of 48 hours is reasonable considering that there are two automatic actuation trains and another manual initiation channel OPERABLE, and the low probability of an event occurring during this interval. If the Manual Reactor Trip Function cannot be restored to OPERABLE status within the allowed 48 hour Completion Time, the unit must be brought to a MODE in which the requirement does not apply. To achieve this status, the unit must be brought to at I least MODE 3 within 6 additional hours (54 hours total time) l follond by sp;ning .~ ...~ ....in 1 eddition;l hour (55 hours total tin). The 6 additional hours to reach MODE 3 end thc f 1 4 (continued) B 3.3-37 10/30/98 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

RTS Instrumentation B 3.3.1 BASES 1 hour to egn the RTSs are reasonable, based on operating experience, to reach MODE 3 ... m .. m.m .m ~ from full TR 3.3 006 l power operation in an orderly manner and without challenging unit systems. With the RE s eg n end the unit in MODE 3 this trip Tunction is no lenar rc= ired to bc 0"E"J".,LE. l r ;;, 7 % 1 s tered

h uuns M t h m u sarkesmesset l rLwetsuhmearamest

                            - m es mmone2tedencemangtgrj!Isant!!!stAsseseassge a we==m e==ser m ]                            l          ,

l C.1-and C.2 W and t m 2 TR 3*3-006 I Condition C applies to the following reactor trip Functions i l i in MODE 3, 4 or 5 with the RE s cicsed sad the CR0 Rod. Control System capable of rod withdrawal;orgg;or,,.mor,grods notifullyJnserted: l

                            -        Manual Reactor Trip:
                            .        RTBs:
                            .        RTB Undervoltage and Shunt Trip Mechanisms: and
                            .        Automatic Trip Logic.                                                       I i

l l This action addresses the train orientation of the SSPS for these Functions. With one channel or train inoperable, the lTR-3.3006 { inoperable channel or train must be restored to OPERABLE l status within 48 hours. If the affected Function (s) cannot ' be restored to OPERABLE status within the allowed 48 hour Completion Time, the unit must be placed in a MODE in which the requirement does not aoolv. To achieve this status h tfonlaust l

                         /treeinitiated within~theisame.J8JyoutsAIuuy.jMallrods g      .m ;ucs ;;;ust r,c egac- 1Q;.t;f:.      T :::~CC;n Rand-      ~

the;,od.IogtfoliSfstem R medFa w A BLJ00 0 3.3 122 withdraw 6] within the next hour m g g R d_eZenettfring )l1 CRDMs3yZppening;the3]Bs;Zot[deienergizingithe;notor generator 3LIGEsets). The additional hour provides sufficient time to accomplish the action in an orderly manner. With the RTS: cpcn.IInithis' condition ithese Functions are no longer , required. The Completion Time is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to perform ! l the safety function, and given the low probability of an event j occurring during this interval. I continued l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-38 10B088

          ~ _ . _ - . . _ _ _ .        .- -      .    --              .          --             .. ._. .            _.

RTS Instrumentation l B 3.3.1 BASES Not1Used; Condition " epplic; to th; Interxdistc "angc Ncutrea riux trip wkn EE""/L "'"'E" is klow the " S sctpcint end enc or two chen=1; erc ire g rebic. "cisw the " 5 xtp; int, th N!S source rr.ng; grfera; the renitoring end protection function;. Thc ire g r:ble NIS intcrx dietc rengc :.henni's) ;ust bc rcturacd to 0"E"XL :tetu: prier to inc.c; sing p;.cr ;b;x tk " 5 setpint. ";c N!S intc,adist; rengc ;kaxis ;;;t k 0"E"XLE whcn the p;;cr icvel is ;bev; the c;pbility of th; ;;urce rensc, j

                                " S, and kl;w th ;;gbility of tk pucr r;nsc. " 10.                                     l L1 Condition I applies to one inoperable Source Range Neutron Flux                       ,

trip channel when in H0DE 2 below the P-6 setpoint-end i perfor;ing ; rc ater :tertup. With the unit in this Condition, below " 5. the NIS source range performs the monitoring and , protection functions. With one of the two channels inoperable, operations involving positive reactivity additions shall be suspended immediately. i i Thisiaction will preclude any power escalation. With only one source range channel OPERABLE, core protection is severely reduced and any actions that add positive reactivity to the core

must be suspended immediately.

l i 1.1 CP 3.3 009 l Condition J applies to two inoperable Source Range Neutron Flux trip channels when in H0DE 2, below the P 6 setpoint, j end grfer;ing a rcater st;rtup. or in H0DE 3, 4, or 5 with the RTBs closed and the GRB RodTContml Svstom capable %j of rod withdrawalema cr4more ivG5:not?fh11y1nsertedy ' With the unit in this Condition, below P 6, the NI5 source range performs the ;enitoring ;nd protection functions. With both source range channels inoperable, the RTBs must be opened immediately. With the RTBs open, the core is in a more stable l conditior, and th; unit cater; Condition L. i K.1-end. K.2"1 rand Kr2:2 Condition K applies to one inoperable source range channel in H0DE 3, 4, or 5 with the "sT"; cic;cd and the C"O Rod Control continued B 3.3-43 10B0M8 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

    . -       _    . -.                     - - - - --- _ - - . - .__-. - -.                                                                                                  --                              ~ _ - . - - -             - . . .

4 4, 1 RTS Instrumentation B 3.3.1 BASES System capable of rod withdrawal or .ZWCoqrodsinot 7 I fu])ydnserted; With the unit in th 3 0,~.bsm., velow P 6, the NIS source range performs the renitorin;; and protection functions. With one of the source range channels inoperable. 48 hours is allowed to restore it to an OPERABLE 0-3"3 122 status. If the channel cannot be returned to an OPERABLE status, 7 y ; E . . ;i.E WMhlCh@majig8jlebrCto fu]h.L . n a ' L. .. 1 additional hour is allowed to $0]y ispart h d f 1. ; 4 . L EWJ$5lE28RR;1RM~mt.g$ttion il 9.0 .A uTL M :.a t lWiK"JILM]tU3lIWisEby ope!@g1t!em , K HL i w NH3&gegeE!toCQIE) s _ets). eg n tt.c ",0 ;. Once t_hete_"A_C_Jm__lS_iare."po_up_leted; the ""; . . i arc e g n, the core is in a more stable condition. end th; unit cater- Cendition L. The allowance of 48 hours to restore the : channel to OPERABLE status, and the additional hour to ;rca the )

                           "E'.                 GUMIiEGUGinp]acelthe; Rod 1 Control Systealin~a                                                                                                                                                 1 conditiorCincapab]CofiroMthdrawaD are justified in Reference 7 5 L .1. ' . .'. . m- ~'                          '.'d                                                                                                                                                                  ;

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                                .Pr. ai sb t. .nsea . e 'L. sv_     us . ussw sas swh ybs (continued)

B 3.3-44 10B0/98 CPSES Markup ofNUREG-1431 Bases - ITS 3.3

RTS Instrumentation B 3.3.1 BASES be placed in MODE 3 within the next 6 hours. The Completion Time of 6 hours (Required Action Q.1) is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to perform the safety function and given the low probability of an event during this interval. The Completion Time of 6 hours (Required Action 0.2) is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging unit systems. The Requirea Actions have been modified by a Note that allows bypassing one train up to 4 hours for surveillance testing, provided the other train is OPERABLE. R.1 and R.2 Condition R applies to the RTBs in MODES 1 and 2. These actions address the train orientation of the RTS for the RTBs. With one train inoperable, I hour is allowed to restore the train to OPERABLE status or the unit must be placed in MODE 3 within the next 6 hours. The Completion Time of 6 hours is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging unit systems. The 1 hour and 6 hour Completion Times are equal to the time allowed by LCO 3.0.3 for shutdown actions in the event of a complete lose af DTR FuncH on. Placina tha 9a* in MODE @ ]ts t "*3 3 *

                           . . _ Jtion;$letopugfMEBittafalis3!Loperablepemoves the rcqui.; = nt for this porticular function.

The Required Actions have been modified by two two ry'otes;

s. %;te 1 I!otei3Lehetgallows one channel to be bypassed for 0 3.3 117 up to 2 hours for surveillance testing' Oo u g ggnance provided the other channel is OPERABLE.ggge3;gjggslone RlBAM.33pa.$ sed 3Gylfocit_heltjm31EshgQoggtfoming majatenangeIappoor#1tage;otishuntarJt CacDetrtss;aericpMitfori U, provided the other channel is OPERABLE. .-.....m n.

to bc bypused for up to 2 hours for mintenance en undcrvoltc;c or shunt trip =chcnis= if the other "," trein is 0"E"J"LE. The 2 hour ti= li;;it is justificd in "cfcccacc 7 ~5. S.1 and S.2 Condition S applies to the P 6 and P 10 interlocks. With one or note required channel (s) inoperable; for enc cut of-two or two cut of four coincidcacc logic. the associated interlock must be verified to be in its required state for the existing unit conaitionLbyf obseryationlofithel permissivelar!nuncjatorAindow continued CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-48 10/3088

 - . .      .          ..   -            -         .=      .-. -           -

RTS Instrumentation B 3.3.1 BASES 1 accomplishes the interlock's Function. The Completion Time of 1 hour is based on operating experience and the minimum amount of time allowed for manual operator actions. The Completion Time of 6 hours is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner and without , challenging unit systems. The 1 hour and 6 hour Completion Times are equal to the time allowed by LCO 3.0.3 for shutdown actions in the event of a complete loss of RTS Function. T.1 and T.2 l Condition T applies to the P-7, P 8. P 9, and P 13 interlocks. With onelor:scre channe1[s] inoperable; for en; eut of tw; or tw; cut of four ;;inciden;; logic, the associated interlock must be verified to be in its required state for the existing unit condition:by~obseryatioCoLthe;peratssivelangunciatotMindow within 1 hour or the unit must be placed in MODE 2 within the next 6 hours. These actions are conservative for the case where power level is being raised. Verifying the interlock status manually accomplishes the interlock's Function. The Completion Time of 1 hour is based on operating experience and the minimum amount of time allowed for manual operator actions. The Completion Time of 6 hours is reasonable, based on operating experience, to reach MODE 2 from full power in an orderly manner and without challenging unit systems. i U.1 and U. 2 .1 and 'J. 2. 2 Condition U applies to the RTB Undervoltage and Shunt Trip Mechanisms, or diverse trip features, in MODES 1 and 2. With one ! of the diverse trip features inoperable, it must be restored to an OPERABLE status within~48 hours or the unit must be placed in a MODE where the requirement does not apply. This is accomplished by placing the unit in MODE 3 within the next 6 hours (54 hours total time) follow;d by egning th; ISs in 1 ;ddition;l hour (55 hour; tot:1 ti;;;;). The Completion Time of 6 hours is a reasonable time, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging unit systems. With the-RT"s eg n ;nd th; unit in MODE 3.-this trip TR 3.3 006 Function is no len;;r recuired to b; OPERABL-EECondition~Cds entered 3 ithe,fagnahlteactoritfjpjmHgLaaws geeg _. _jaDdI19eltod1 Control Sys.tgisMWHpMod := , withdrMcEgr!OnCOM a0ModsTarewtMf Mwhile one of l eeMeaHef The af rected Mits suaei mn. us u tie diverse features is inoperable except for the time required 1 B 3.3-49 10/30/98 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

CHANGE HutSEB JUSTIFICATION 9, and 11] and the Applicability for ITS Table 3.3.11 Functions 1 and

20. The current TS provides for these Functions to be restored to OPERABLE status with 48 hours or the plant must be in HOT STANDBY within the next 6 hours when the plant is initially in MODES 1 or 2.

Once HOT STANDBY has been reached, the shutdown mode applicabilities, i.e., MODES 3, 4, and 5, prevail. When in these MODES, another 48 hour A0T is allowed by the current TS or rod withdrawal must be precluded in the next one hour. Therefore, ISTS Required Actions B.2.2 and U.2.2 for Functions 1 and 20 in Table 3.3.1-1 are not necessary since the performance of Required Action B.2.1 and U.2.1 l takes the plant to MODE 3, exits the Applicability, and requires , entry into Condition C. This change is consistent with ITS 1.3 l and 3.0.4 113 ye) E TSTF l \ l l l l l l l l i 4 lid 10B088 CPSES Differencesfrom NUREG-1431 -ITS 3.3

CHANGE NUMBER JUSTIFICATION 3.3 121 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 122 ITS 3.3.1 Applicability Note (b) for Functions 1. 5, 19-21 and - m3.3 006 Conditions C and K are revised to replace Actions requiring the RTBs to be opened with actions that ensur(subcriticality is maintained (i.e. , by%,"ct_t_y,n'$o q rfu t iy n- 6.., a n rods and ensuring the Rod Contrui Mt- % ble of rod withdrawal) yet do not initiate a feedwater isolation (P 4 and low T,,) in MODE 3, consistent with traveler TSTF 135. i l 3.3-123 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 124 Consistent with the current TS Table 4.31. Note [15]. the notes for l i ITS SR 3.3.1.4 and Table 3.3.1-1. Function 20 are modified to clarify that the SR is required for the reactor trip bypass breaker local manual shunt trip only. The Bases for SR 3.3.1.14 clearly state that SR 3.3.1.14 includes the automatic undervoltage trip of the reactor trip breakers. The note (k) added to Table 3.3.11. Function 20 clarifies the Applicability of the undervoltage and shunt trip mechanisms to include ! i those functions of the reactor trip bypass breakers when in use. 3.3 125 ITS SR 3.3.1.11 is modified by a note that requires verification that the ; time constants are adjusted to the prescribed values. The addition of I this note is consistent with SR 3.3.1.10 and is required because SR i 3.3.1.11 is used for the Power Range Neutron Flux High Positive Rate [] ( trip function, which has a time constant associated with its calibration. The surveillance frequency associated with the RWST Level Low Low ESFAS 3.3 126 function is restricted to 9 months by the drift allowance in the CPSES- i specific setpoint study. Therefore, a new surveillance requirement (SR 3.3.2.12) is specified that replaces SR 3.3.2.9 used for those ESFAS functions with 18 month surveillance frequencies. This modification is I consistent with the CPSES current TS. 3.3 127 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 128 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3-129 Consistent with the current TS. the ITS requirement to have the Loss of Power Diesel Generator Start Instrumentation (ITS 3.3.5) applicable in Modes 5 and 6 when the associated DG is required to OPERABLE by ITS LC0 3.8.2 'AC Sources - Shutdown" is deleted. In these modes, the Reactor l Coolant System or Reactor Vessel cavity temperatures are low enough that I the time available for the reactor operators to manually start the diesel generators is adequate. Thus, there is no need to require the 13 10/30/98 CPSES Differencesfrom NUREG-1131 -ITS3.3

CHANGE NUMBER JUSTIFICATION 3;'32140 Not"appUcable;to;CPSES]"gsee;Conyersion;ComparisonlTable a.3,3.ao7 (EnglosureL68)J 3132141 Notiapplicableito1CPSESHESeeiConyersionicompatisonlTable m 3.3 002 (Enclosote;6BN 431g2 Addsm.arainsj@;LuinTgtglittogmea!!sisge!srirLth.j _d 73 3,3 00o 3.3Xanittramewas!EMER 3}M MlappM.cableXJPSES';ISee:Coupetsjon CagnefjsenlabJe 7g.3,3.co7 (Enclosute;68)] 14a 10/30M8 CPSESDifferencesfrom NUREG-1431 -ITS3.3

Page 18 cf 22 CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.3 APPLICABILITY TECH SPEC CHANGE COMANCHE PEAK WOLF CREEK CALLAWAY . DIABLO CANYON i NUMBER DESCRIPTION N/A N/A N/A N/A 3.3-115 Not used. No No Yes No 3.3-116 ACTION J of ITS 3.3.2 is not used since DCPP does not rely on motor-driven AFW pump start with loss of both main FW pumps. No not i c.. . c,,t Yes Yes This change to ITS 3.3.1 Condition R reflects current TS Yes 503.311 r l 3.3-117 & Yes Table [3.3-1. ACTION Statement 112] which was based on NRC Generic Letter 85-09. Yes Yes Yes Yes 3.3-118 This change is for consistency with ITS 3.7.10 Condition [G). No No Yes No 3.3-119 This change reflects Callaway-specific BDMS analysis restrictions associated with RCS mixing volume and dilution flow rate. These are administratively controlled under the , current TS, as approved in OL Amendment No. 94 dated March 7, 1995. However, with the conversion to ITS 3.3.9. these analysis assumptions should be included in the body of the TS. Ves N/A Ves N/A Ves N/A ITS 3.3.1 C;-dition 0 is rcvi;;d to rcf';;t ITS 5" 3.2.4.2 Ves:N/A

                                                                                                                                 '                                                         l0-3.3-121   l 3.3-120 e-d CM 3.2 IS '- the 3/4.2 p;;k;;;. Mused No                 No           Yes No 3.3 121     For Callaway. ITS 3.3.9 is revised to reflect that only one BDMS train is required OPERABLE in MODE 5 and that the

suspension of positive reactivity additions and accelerated SDM verifications are required only if no source range neutron flux indicator is OPERABLE.

Yes Yes Yes ITS 3.3.1 Applicability Note (b) for Functions 1. 5, 19-21 Yes l TR-3.3-016 l 3.3 122 and Conditions C and K are revised to replace Actions requiring the RTBs to be opened with actions that ensure subtriticality is maintained (i.e.. by fulgtiatty ~ it rods and ensuring the kuu Cw arol fcon,to; insert g' of rod withdrawal) yet do not initiate Synt= ~ ' ::;d . a feedwater isolation (P-4 and low T.,,) in MODE 3. consistent with traveler TSTF-135. t 102088 . CPSES Conversion Comparison Table -ITS3.3 !

CONVERSION COMPARISON TABLE FOR DIFFERENCES FRON NUREG-1431, SECTION 3.3 Page 22 cf 22 APPLICABILITY TECH SPEC CHANGE COMANCHE PEAK WOLF CREEK CALLAWAY DIABLO CANYON NUNBER DESCRIPTION lki 10 0 No Yes 3.3+140 Changes..to,RTS:end;E5FAS UTj. Functions; erg eede;to reflect -3.3 0C Callawef A Amendment; Non125;deted;4/p; No No yes sumuuuuuuuun Changes,toiESFASifeedwaterLIsoletion2 Functions:ere madetto Ito 3 3 141 2 E CA-3.3-002 reflecticalloweyAAsenchmentellets125; datedt 4/13/98; yes yes les b 42 Adds;%trainito;ITS. Condition Ancons1 stent 2with ITS yes lTR-3.30055 (q 3.3i2;and,TSTF1135; -- _- No No yes Ye$ 3.3t143 Revise,SR 3.3.1415: Frequency;petWDGt122 l TR-3.3-007 l ygj3ggg CPSES Conversion Comparison Table -ITS3.3

                     .          .             _ . . _ . . _____ -            ._ . _ . _ _ _ _ _ = _ _ .

h ADDITIONAL INFORMATION COVER SHEET i ADDITIONAL INFORMATION NO: O 1-B GEN APPLICABILITY: DC, CP, WC, CA REQUEST: Generic Bases Changes RAI Comment: For all topical reports listed in the Section 3.3 Bases provide documentation of an NRC staff letter approving plant-specific use of topical report TS changes. FLOG RESPONSE: This RAI must be addressed on a plant-specific basis. Plant Soecific DiscussioD For Comanche Peak, WCAP-10271-P-A, Supplement 2, Revision 1 is referenced with regard to i the allowed outage times. This document was approved for CPSES in License Amendment 13 dated January 12,1993. ATTACHED PAGES: i None l i I i t 4

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-01 APPLICABILITY: DC, CP, WC, CA REQUEST: A Note, " Separate Condition entry is allowed for each Function," is added to the ACTIONS for the Reactor Trip System, ESFAS, [ Remote Shutdown, including each required ' ASP control], and Accident Monitoring Instrumentation. This change clarifies those situations where the current TS ACTION Statements are not uniquely associated with a particular Function or where the required channels are specified on a per steam line, per loop, per SG, per bus, etc., basis. Comment: The new note Separate Condition entry allowed for each function is justified as an administrative change reflecting the current interpretation of the technical l specification requirements. This is inconsistent with the fact that CTS LCO 3.3.3.5 l explicitly provides for separate condition entry (Action c). If separate condition entry is i the general practice, one would expect that explicit provision for this would be unnecessary in LCO 3.3.3.5. Thus, adopting " separate condition entry" where CTS actions are not uniquely associated with a particular Function can not be evaluated as

           " administrative changes" as stated in this DOC. Evidence that separate condition entry is the current interpretation for the other LCOs should be provided.

FLOG RESPONSE: The reference to CTS LCO 3.3.3.5 Action c applies to DCPP only. PG&E received an amendment in 1994 (LA 94/93 for Units 1 and 2 respectively) that was based on I adopting some of the language of NUREG-1431 regarding separate Condition entry. The separate 1 Action or Condition entry language is not found in the old STS, NUREG-0452. Separate Condition entry is, in fact, the established plant practice at all FLOG plants where required Functions are , listed in tables and often use common Action Statements. DOC 1-01-A has been revised to provide l further discussion, j ATTACHED PAGES: Enci 3A 1 l i l l

p I DESCRIPTION OF CHANGES TO CURRENT TS SECTION 3/4.3 This enclosure contains a brief description / justification for each marked up change to the current Technical Specifications. The changes are identified by change numbers contained in enclosure 2 (Mark up of the current Technical Specifications). In addition, the referenced No Significant Hazards Considerations (NSHCs) are contained in enclosure 4. Only technical changes are discussed: administrative changes (i.e., format, presentation, and editorial changes) made to conform to NUREG 1431 Revision 1 are not discussed. For Enclosures 3A, 3B, 4, 6A, and 6B, text , in brackets "[ ]" indicates the information is plant specific and is not common to - all the Joint Licensing Subcommittee (JLS) plants. Empty brackets indicate that other JLS plants may have plant specific information in that location. ; CHANGE NUMBER RE DESCRIPTION i 1 01 A A Note, " Separate Condition entry is allowed for each Function," is added to the ACTIONS for the Reactor Trip System ESFAS, [ Remote Shutdown including each required HSP control], and Accident Monitoring Instrumentation. l This change clarifies those situations where the current l TS ACTION Statements are not uniquely associated with a particular Function or where the required channels are specified on a per steam line, per loop, per SG, per bus, , etc., basis. This change is consistent with current operatino oractices and NUREG 1431 Rev. 1. [ ] _ hMMMEEi_---':r - _E"'t g.1-01 E M Em2RES2Ebt 1!!oMtWBRERfBMBWEBNDERB32BptIB3NHLcE ! tJICMRSOsstatumsamoissageB3BmGtMGht tabialesmaRMELEluGe$musa!B142elples30 tmh ActjatangulaMRSauem!32mammbaKWstate CoMW*BiMR2f5Mbita!10 Dish!dRt3tg8HBaueMemonith oneJimatagginalMWlamKm!MtGEddaleg;giarit opstigmaammessameteitantameplantMmGhe cmagWes2BWEREIGRS3nBf.. o c a

VWmit l 199913bM3 HEM,29R!st1se] j manction th spech'amitgegCte@inBClagEGbsMs3!as noth1W3GE*1tN3ttheshansislerggher.goopcatthet EunctiogbattigZeiccanoCao@2aDgithich11Gddressed by1LCol3113)2SjndEth1Cchangeidoes30tInffectLthe opetatimilimitroryannerlirteightthelplantiis: current 1 rated.MthisZislaQesinistrativelchangel 1 02 LG The current TS require that response time testing be performed on each reactor trip and ESFAS function oc-m 001 '

every [18] months and that alternate trains be tested in successive tests. The current TS description of the channel testing protocol matches the improved TS CPSES Description of Changes to CTS 3M.3 1 10B088

                                  . - .     -   . . =  .       . - - - .         - - - . . . .- - ..

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-06 APPLICABILITY: DC, CP, WC, CA l REQUEST: A new ACTION Statement [2.1] is created which does not require a reduction in l THERMAL POWER to less than 75% RTP or the measurement of the OPTR if above 75% RTP. Comment: The new action referenced for the power range low setpoint and the two flux rate trips (functions 3 & 4) no longer require a reduction in power. The Discussion ! of Change (DOC) and No Significant Hazards Consideration (NSHC) justify this on the basis that the rate trips are not sensitive to the initial power level. This is true. However, the rate trips may be sensitive to the fact that with one channel inoperable one core quadrant is not directly monitored by the power range neutron flux function. Neither the DOC nor the NSHC discuss the impact of this on the possible need to reduce power. Revise the justification. FLOG RESPONSE: NSHC LS-2 has been revised to provide additional discussion. The impact on the rate trip Function is of no consequence since other Functions provide the required protection. ATTACHED PAGES: 1 Enci 4 17 ! l l l i

IV. SPECIFlC NO SIGNTFICANT HAZARDS CONSTDERATIONS NSHC LS 2 l (continued) t The high positive rate [ ] trip function is insensitive to the static power level . The proposed change will not affect any of the analysis assumptions for any of the accidents previously evaluated. [No FSAR Chapter 15 analyses specifically credit this trio function. It provides back up protection for l an RCCA E*th MJriencttW11;y; transients 1 at;coula th De 0-1-06 itolaccurlKj$lelcor!aDadounX#1th3sOnoperab)e2Mgh;positiv l roteittennellgsmmcontranea innamerstneramaEfnmysaberitical;or wpowergstettwicanettjanauncontrefLMaccNeneletthdramannt;paner, l wtthdramroflerswiggiganivoresectientate21ttestad pn pe; accident I analysesvather;taactat2rJpMW3eIs=pomer#angeyientran finx '- loWEsometrange;nentjen;flaEastot guettegetagatemi16DEdependi.ng uponlanalysisfassumptjoncregardincFinitiaPw==%ve17and'reactivit' inserti.onjtate p r oposed change will not affect the probaoliuy of any event inulators nor will the proposed change affect the ability of any safety-related equipment to perform its intended function. There will be no i degradation in the performance of nor an increase in the number of challenges imposed on safety-related equipment assumed to function during an accident situation. Therefore, the proposed change does not involve a significant l increase in the probability or consequences of an accident previously evaluated.

2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

l There are no hardware changes nor are there any changes in the method by which any safety-related plant system performs its safety function. The change in required ACTION will not af'act the normal method of plant operation and, in fact, will relieve the open%rs from performing actions not required for plant safety. No new accident scenarios, transient prect.rsors, failure mechanisms, or limiting single failures are introduced as a result of this change. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does this change involve a significant reduction in a margin of safety?

The proposed change does not affect the acceptance criteria for any analyzed event. There will be no effect on the manner in which safety limits or ! limiting safety system settings are determined nor will there be any effect on those plant systems necessary to assure the accomplishment of protection functions. There will be no impact on any margin of safety. NO SIGNIFICANT HAZARDS CONSIDEPATION DETERMINATION l Based on the above evaluation, it is concluded that the activities associated with l NSHC "LS-2" resulting from the conversion to the improved TS format satisfy the no significant hazards consideration standards of 10 CFR 50.92(c): and accordingly, a no significant hazards consideration finding is justified. CPSES No Significant Ha:ards Consideration - CTS 3M.3 17 1020/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATICN NO: O 1-07 APPLICABILITY: DC, CP, WC, CA REQUEST: With one intermediate range neutron flux channel inoperable when the plant is above P-6 but below 10% RTP (the P-10 interlock setpoint), current ACTION Statement [3.b] is revised to establish a 24 hour Completion Time for channel restoration or changing the power level to either below P-6 or above P-10. Although this change is less restrictive since a power increase is an allowed option, the ACTION Statement would ensure protection by entering the range of the four power range neutron flux channels. The Applicability for Functional Unit 5 is revised such that current ACTION Statement [3.a] can be deleted. With both intermediate range neutron flux channels inoperable when the plant is above P-6 but below P-10, LCO 3.0.3 would be entered under the current TS and the plant would have to be in MODE 3 within 7 hours. New ACTION Statement [3.1] requires immediate suspension of operations involving positive reactivity additions and a power reduction below P-6 within 2 hours. Comment: Explain how the 2 hour and 24 hour repair times provide protection and ensure the low probability of occurrence of a reactivity transient that would require the need for an IR flux trip. Explain why the ITS actions will provide for continued safe operation of the plant. This change references TSTF-135 which is not approved by the staff. Provide discussion to explain the relation of this change to proposed TSTF-135 changes. Note that not all proposed TSTF-135 changes are acceptable to the staff for implementation in ITS. FLOG RESPONSE: DOC 1-07-LS-3 and NSHC LS-3 have been revised to clarify the suspect l wording. This DOC is unrelated to TSTF-135, discussed under Comment Number Q 3-LS-GEN. The 24 hour Completion Time is taken from TSTF-246. See the response to Comment Number 3.3-107 for additional discussion of TSTF-246. , ATTACHED PAGES: Enci 3A 3 j Enci 4 18

CHANGE NUMBER EliG DESCRIPTION the window of operation during which the intermediate range neutron flux trip functi_on provides protection in 0-1 07 a 1 of 1 looic confiaurationI end casures the Further,Y

                               / therexisialjow probability or occurrence or a reacuvity transient auring this time period that would require an intermediate range flux trip. Although this change is less restrictive since a power increase is an allowed option, the ACTION Statement would ensure protection by entering the range of the four power range neutron flux channels.

With both intermediate range neutron flux channels inoperable in MODE 1 (below P-10) and MODE 2 (above P 6). LCO 3.0.3 would be entered under the current TS and the plant would have to be in MODE 3 within 7 hours. .With both intermediate channels inoperable. new ACTION Statement [3.1] requires immediate suspension of operations involving positive reactivity additions and a power reduction below P-6 within 2 hours. New ACTION Statement [3.1] is less restrictive since a reduction to MODE 3 would no longer be required; however, the current TS are overly conservative in this area. Below P 6 the source range channels provide protection: therefore, the required action for both intermediate range channels inoperable should be to exit plant conditions where this trip function provides protection. New ACTION Statement [3.1] will preclude any power level increase and require a controlled power reduction to less than P-6 where the source range channels provide protection. The 2 hour Completion Time ensures the low probability of occurrence of an event during this period that may require the protection afforded by the intermediate range neutron flux trip. These actions actually provide a more timely and appropriate redress to the condition than entering LCO 3.0.3. These changes are consistent with NUREG 1431 Rev.1. 1-08 M Current ACTION Statement [4]. for one source range channel inoperable in MODE 2 below P 6, is revised to require the immediate suspension of operations involving positive reactivity changes. The CTS does not specify the timing for this ACTION. A new ACTION Statement [4.1] is added to address the condition where both source range channels are inoperable in MODE 2 below P 6 [and in MODES 3. 4. and 5]. The new ACTION Statement [4.1] requires that the RTBs be opened immediately. This action essentially accomplishes the reactor trip function. In such a condition with the current TS. LC0 3.0.3 would have been entered. This is CPSES Description of Changes to CTS 3M.3 3 103088

IV. SPECIFTC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-3 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS With one intermediate range neutron flux channel inoperable, current ACTION Statement [3.a] applies below the P-6 interlock. For those times that the plant is above P-6 but below 10% RTP (the P-10 interlock setpoint), current ACTION Statement [3.b] applies. ACTION Statement [3.b] is revised to establish a 24 hour Completion Time for channel restoration or changing the power level to either below P-6 or above P 10. The intermediate range neutron flux channels provide protection between these power levels and the APPLICABLE MODES have been revised accordingly. The source range neutron flux detectors provide protection below P 6 and the power range neutron flux detectors provide protection above P-10. The addition of the 24 hour Completion Time (current TS has no Completion Time) limits the window of operation during which the intermediate range neutron flux trip function provides 0-1 07 protection in a 1 of 1 logic configuratio{. Gnd casurcs the Further,nthere is ab low probability of occurrence of a reactivu,y transient occurring during this time period that would require an intermediate range flux trip. Although this change is less restrictive since a power increase is an allowed option, the ACTION Statement would ensure protection by entering the range of the four power range neutron flux channels. With both intermediate range neutron nux channels inoperable in MODE 1 (below P-IO) and MODE 2 (above P-6), LC0 3.0.3 would be entered under the current TS and the plant would have to be in MODE 3 within 7 hours. With both intermediate channels inoperable, new ACTION Statement [3.1] requires immediate suspension of operations l involving positive reactivity additions and a power reduction below P-6 within 2 hours. New ACTION Statement [3.1] is less restrictive since a reduction to MODE 3 would no longer be required: however, the current TS are overly conservative in this area. Below P-6 the source range channels provide protection: therefore, the required action for both intermediate range channels inoperable should be to exit plant conditions where this trip function provides protection. New ACTION Statement [3.1] will preclude any power level increase and require a controlled power reduction to less than P 6 where the source range channels provide protection. l The 2 hour Completion Time ensures the low probability of occurrence of an event during this period that may require the protection afforded by the intermediate i range neutron flux trip. These actions actually provide a more timely and appropriate redress to the condition than entering LC0 3.0.3. The proposed TS change has been evaluated and it has been determined that it

involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below

                  "The Commission may make a final determination. pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no l

CPSES No Significant Ha:ards Consideration - CTS 3N.3 18 10BW98

i i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 1-11 APPLICABILITY: CP, WC, CA ! REQUEST: [New] ACTION Statement [39] is applied to the low fluid oil pressure and turbine I stop valve closure trip functions. Rather than entry into LCO 3.0.3 if current ACTION Statements [6 and 11] are not met or if multiple low fluid oil pressure channels are inoperable, the new ACTION Statement requires inoperable channels to be tripped within 6 hours or power reduced below P-9 within 10 hours. Comment: By adopting the STS, Turbine Stop Valve Closure channels are given a 4 hour bypass allowance which is related to WCAP-10271. The ITS proposed is not evaluated. Provide additionaljustification. Based on 8/14/98 meeting this comment will be responded to as part of the JFD 3.3-02 comment response. l l FLOG RESPONSE: See the response to Comment Number O 3.3-02. ATTACHED PAGES: None l I l i n

t 4 ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-13 APPLICABILITY: DC, CP, WC, CA i REQUEST: [ ACTION Statement [9] is revised to note that the 2 hour [] reactor trip breaker

bypass allowance for [] breaker surveillance testing can also be used for maintenance.]

ACTION Statement [9] is (also] revised to require restoration of an inoperable RTB within 1 hour or the plant must be in HOT STANDBY within the next 6 hours. This is less restrictive since an

additional hour is provided for the transition to MODE 3.

l Comment: 1) Pending TSTF review - this DOC discusses adding a 2-hour AOT for j instrument maintenance. Use of maintenance AOTs have not been approved by the staff. TSTF-168 for maintenance bypass is not approved by the staff. Revise the ITS to j adopt the STS note to Action R for reactor trip breakers in Modes 1 and 2. Based on 8/14/98 meeting this comment will be responded to as part of the JFD 3.3-43 comment response.

2) CTS requires 2 channels of RTBs to be operable. ITS requires 2 trains of RTBs to be operable. The ITS action R Notes 1 and 2 address both channel and train inoperabilities. Provide DOC discussion for each CTS change.

4

FLOG RESPONSE: See the responses to Comment Numbers Q 3.3-03, O 3.3-43, and O 3.3- [

i j 117. Although the ITS will use the "RTB train" wording, the words " channel" and " train" mean the same thing when there are only two separate entities involved. This wording is an artifact of i l the last STS, NUREG-0452. , ATTACHED PAGES: None l l 1 l I

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-14 APPLICABILITY: DC, CP, WC, CA REQUEST: In the ISTS Table 3.3.1-1, Function 20, the reactor trip breaker (RTB) undervoltage and shunt trip mechanisms are separate from the RTB Functional Unit. The current TS have been revised to reflect these requirements. New [ footnote (d) has] been added to the RTB Functional Unit to note that the same OPERABILITY requirements and ACTIONS apply to a bypass breaker if it is racked in and closed for bypassing an RTB. The bypass breakers were already handled in this fashion. ACTION Statement (12] in current TS Table 3.3-1 has been revised accordingly.

Comment: 1) Adopting a current practice as a TS is not an administrative change to current TS. Provide a separate DOC for the footnote change which is consistent with

I the " change" in current TS requirements that results from adopting the NUREG STS.

l 2) The staff presumes that the CTS were retyped and that the CTS markup represents a comparison between the retype and the additions made to the CTS to adopt the ISTS. The staff continues to find mistakes in the retype, changes that are neither redlined or shown in strike out but which are obviously not consistent with the CTS. For example, {CP} T3.3-1 Function 19 (RTBs) the applicability in Mode 5 has footnote "k" whereas the other applicable Modes have footnote "a." Footnote "k" does not exist. Based on 8/14/98 meeting Rev 0 is accepted and this comment does not need a response.

3) CTS action [12] contains a requirement not to bypass the breaker while one of the diverse trip features is inoperable. This prohibition is not included in the actions for Conditions C or U. Neither the CTS markup nor the DOC cover this deletion.

FLOG RESPONSE: DOC 1-14-A has been revised to demonstrate that this change does not just formalize " current practice", rather it is consistent with the current TS. The CTS ACTION statement allows the RTB to be bypassed for the time required to restore an inoperable trip attachment to OPERABLE status. This is covered by ITS 3.3.1 Condition R Note 2. See also the response to Comrnent Number Q 3.3-117. ATTACHED PAGES: Enci 3A 5

l CHANGE EMIEE HSIE DESCRIPTION ) requirements are not met, then new ACTION Statement [7.1] I requires that the unit be taken to MODE 2 within 7 hours. ! In addition, current ACTION Statement [7] is revised for those interlocks required to be OPERABLE in MODES 1 and 2. If one channel is inoperable, the interlock must be I determined to be in its required state or the plant must i be in at least HOT STANDBY within 7 hours. l l The changes to current ACTION Statement [7] and the addition of new ACTION Statement [7.1] are more restrictive. consistent with NUREG 1431 Rev.1. Current ACTION Statement [7] will continue to apply to Functional Units [18.a. 18.b.1), and 18.e.] Revised ACTION J Statement [7] and new ACTION Statement [7.1] provide one less hour to exit Applicability, i.e. 7 hours, than the current ACTION Statement [7] which has the 1 hour interlock state verification or entry into LC0 3.0.3 which j allows an additional I hour plus 6 hours to exit i I Applicability, for a total ~ of 8 hours. 1 13 _LS 6 {-} ACTION Statement [8] is [ ] revised to require restoration of an inoperable RTB within 1 hour or the plant must be in HOT STANDBY within the next 6 hours, consistent with NUREG 1431 Rev.1. This is less restrictive since an additional hour is provided for the transition to MODE 3. 1-14 A In ISTS Table 3.3.11. Function 20. the Reactor Trip Breaker (RTB) Undervoltage and Shunt Trip Mechanisms are separate from the RTB Functional Unit. The current TS have been revised to reflect these requirements. New [ footnotes (j) in Table 3.3-1 and (f) in Table 4.31 have] been added to the RTB Fenctional Unit to note that the same OPERABILITY require'aents and ACTIONS apply to a bypass breaker if it is rar.xed in and closed for bypassing an RTB. The bypast breakers were already handled in this fashion. ACTION Statement [11] in currantTS Table 3.3-1 has been revised accordingly.MchangeMs o.i.14 administrativejn,naturetsinci,the;catentKalready : SpecitieCoperabiljtyiand.surveillancefrequirements;on ; the; diverse 3tip~ attachments andJhe; bypass; breaker.s:(whe l l racked A andlejosed m a.s; evidenced M Ts;1ab]eis;3-1 ACTION 5;[9fand ;11]1orjunctionaLUnit][19]^,T[?] ETable 4;311; Note 1311)]Iforifunctional;UnitJ[19]RandjTable ( 4331 Wote~[(15)] Nor; FunctionaliUnit((21];? 1 15 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). CPSES Description of Changes to CTS 3N.3 S 10B0/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-16 APPLICABILITY: DC, CP, WC, CA REQUEST: The requirement to verify the setpoint during the quarterly TADOT for RCP Underfrequency [and RCP Undervoltage] is deleted. l l Comment: Expand LS discussion. The extension of the allowed outage time for one CRVS channel inoperable from i hour to 7 days is justified based upon the fact that the J AOT for a single inoperable mechanical train is 7 days. The bases, however, indicate i that the two channels are used in a one-out-of-two logic to start both CRVS channels are used in a one-out-of-two logic to start both CRVS trains. A single inoperable instrumentation channel, therefore, degrades the operability of both mechanical trains. This is a different condition than inoperability of a single inoperable mechanical train 1 thus the justification provided for the 7 day AOT is not germane. FLOG RESPONSE: LS-40 is revised in the response to Comment Number Q 2-LS GEN. The remainder of the comment does not apply to this DOC, as discussed in Reference 6. It applies to DOCS 2-16-LS-12 and 3-05-LS-14. See the responses to the comments on those DOCS. ATTACHED PAGES: None ) l l i i l i i i 1

l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-18 APPLICABILITY: DC, CP, WC, CA REQUEST: The current TS requirement to rnduce the power range neutron flux trip setpoints in the event a power range flux channel is inoperable is deleted. The time to reduce power below 75% RTP is increased from 4 hours to 12 hours and, if actions are not completed as required, the unit must be in MODE 3 in 12 hours. (See also CN 1-53-A.) Comment: (1) The CTS requires QPTR to be monitored per SR 4.2.4.2 if one channel is inoperable and power is not reduced to less than 75%. The markup relaxes this requirement to only require OPTR monitoring if the input to the OPTR function is inoperable. This change has not been justified. The justification provided for not reducing power presumes that the OPTR is being surveilled. It is likely that what is ; intended here is that OPTR be surveilled in all cases where power is not reduced below 75%, however if the input to the OPTR monitoring function is OPERABLE then that 4 monitoring may be accomplished via that function using the power range inputs. If the i OPTR input is inoperable then QPTR must be monitored per SR 4.2.4.2. The ITS actions should reflect the NUREG-1431 STS and the CTS changes should be evaluated. (2) The CTS markup eliminates the requirement to change the power range trip setpoint after power is reduced. The DOC justifies this on the basis that the loss of a channel , does not indicate an abnormal flux tilt The proposed change also places the power l limitation under administrative control rather than enforcing it by changing trip setpoints. The basis for this change should be discussed. Provide a technical basis for changing the power reduction completion time from 4 to 12 i hours.

3) The CTS requires resetting the power range neutron flux trip setpoint to 85% of rated thermal power on loss of one channel of power range neutron flux - high setpoint. The ITS markup requires restricting power to 75% of rated thermal power. No justification is provided for change in power level or from change from " trip setpoint at 85% power" to

          " restriction to 75% power".

I Neither the DOC not the NSHC provide specific justification for extending the AOT for two inoperable channels by 11 hours (or by 3 hours when a tie breaker is closed). FLOG RESPONSE: Comment (1) is addressed in the response to Comment Number Q 3.3-120. NSHC LS-7 has been revised to address comments (2) and (3). The last paragraph is written against the wrong DOC as discussed in Reference 6; see the response to Comment Number O 2-18-LS-31. ATTACHED PAGES: Enc! 4 26

    ..   .               - -          --     .-.                - - - _ - - .                . - - - - . - . ~

IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-7 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE l REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS In current ACTION Statement [2c]. the requirement to reduce the power range neutron flux high trip setpoint is deleted. The loss of one power range neutron flux channel does not impact the reliability of the reactor trip system because the J channel is required to be placed in trip. With an NIS power range channel inoperable, tilt monitoring for a portion of the reactor core becomes degraded. To address the impact on measuring QPTR. the QPTR TS provides conditional notes to the surveillances that verify QPTR. Although the loss of one power range channel may affect the ability to measure QPTR. there is no basis for reducing the power ringe high flux trin enoint and increasing the potential for an inadvertent reactor I tr Js:tio]accidentianalys1sammopyv,1:stjeG=J, ion 3o;852 RTP 2 Jhione: Inoperable:channellinitrip.ZAl]1acejdentlanalysesicted.iting; power 7ange neuttoglflux;highiare; based ,on_seetinglaisafety; analysis 311mitlofJl8tR.(1092 - 0 1-18 RTPitr.ipisetpoint:pl us;fnstrumentiettotsnReducing .,the;powetileyelito325tiRTP ga. 4sioperation of;the; core 31th~tadial;powetidistt1 buttons;beyond;the; design limits;atia;powetae*Dheteps2cogitions may; exist;EP, lacing;thEcurrentJS Action; statement'sloptfonitorza poweCreduction;undecadministrat1W3cntrolErathe than.;enforeigg;1t;byJalrsodced3ripIsetpointqdoesigotitender3he2equirementlany j lessyslidayyast;majotityrofalechtlicallSpecificatijoKAction?requirementsIarej enforced?administratiyelyEnot]by;eguipmentichanges; me exisung surveu iance requiremem m me VFlK W p. .w aucqua w su.. d measures (increased l surveillance frequency and/or different method for monitoring QPTR) when an ! l inoperable power range channel affects the input to QPTR. In addition, the monitoring of QPTR every 12 hours will no longer be required if the input to the QPTR from the power range neutron flux channels remains OPERABLE. A consistent completion time of 12 hours is imposed on either of the thr quired actions i.e. power derate. QPTR surveillance, or shutdmn M ""E 1*@e l o 1 18 _ _ E1ollfromyoutwo.xtug.golesincessabelowl581R1151slaccept.able ba_sedCon3his;be1Dg3DreIc_ontrgiledEmplutjgitoltake20ad70ff!tt2a;tgducedirat.e eheq11tjls3noWDitheIpowerIr_aggelsogitettgg3s)ptbjlityls'"dentaded! Th.islisia teasonableltime;tjo reduce:poWetEgiven;that.3NSB[changeslteletivelyJs1,cW1yjatifu1]. poWeCandithe;actjon;tpiplace3hCinoperable3hanne1I1g;ttip]ithjn163eours'al. ready (addgssesithe;RTS;unavail performed M an orderlyzmagnetrand without1 abiljtyIconcernEJhis; challenging:p] ant 1 system

ensures 3:help The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted l

below:

                                                                                                                          )
                      "The Commission may make a final determination, pursuant to the procedures in                       ;

50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no CPSES No Significant Hazards Consideration - CTS 3N.3 26 1080/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-23 APPLICABILITY: DC, CP, WC, CA REQUEST: This change adds notes to the RTS and ESFAS SR Tables 4.3-1 and 4.3-2 that explicitly require the 18-month calibrations to include verifications of affected time constants where applicable. Comment: Provide CTS Table 4.3-2 and Note (5) for staff review of proposed changes. The A-DOC discusses additional requirements and should be evaluated as an M-DOC. The A-DOC discusses the addition of surveillance requirements to include time ; constants and should be evaluated as an M-DOC. l Amendments 126/124 include 24 month surveillances for CTS function 1.b,11.c,1.d,1 e, 2.c, 3.a.2, 3.b.2, 3.b.3, 3.c.1, 3.c.4,4.c, 4.d, 4.e, 5.a. 5.b,6.b, 6.c.1, 6.c.26.d, and 8a which are shown as 18 months in ITS SRs 3.3.2.9 and 3.3.6.7. Provide CTS /ITS markup revisions. {WC, CW) CTS TADOT surveillances are modified in the ITS with a note that

               " verification of setpoint not required." This change is not evaluated. For CW this change is also not identified in the CTS markup. Provide justification for all proposed l               changes to CTS as they are reflected in the ITS.

i ! FLOG RESPONSE: The first and second comments were discussed with NRC staff during a meeting on 8/14/98 whereupon NRC agreed with the FLOG's contention that, since this represented current plant practice, the DOC was indeed administrative in nature. The NRC , ' concurred in the meeting minutes (Reference 4 to the cover letter). l J l In response to the third comment, the changes to the DCPP CTS and ITS associated with I l l Amendments 126/124 are provided via Additional Information item DC-ALL-005. Please note that the Functions listed in the comment include Functions revised via LA 122/120 and LA i 123/121 as well. Not all of the Functions revised by these LAs are listed. Additional information Number DC-ALL-005 includes all of the revised Functions and the revised SRs 3.3.2.9 and 3.3.6.7 as well as other affected SRs. In response to the last comment, new DOC 1-64-A has been generated as well as the associated CTS mark-ups. i l ATTACHED PAGES: Enct 2 3/4 3-10,3/4 3-12,3/4 3-39,3/4 3-40,3/4 3-42,3/4 3-45, and 3/4 3-46 End 3A 14 and 14a Enci 3B 10a i

TABLE 4.3-1 BEACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES-FOR E l-44** \ d CHANNEL DEVICE WMG1 OPERATIONAL OPERATIONAL ACTUATION SUR"EIL' A."CE CHANNEL CHANNEL CALIBRATION TEST IEST LOGIC TEST IS REOUIRED-FUNCTIONAL UNIT CHECK

1. Manual Reactor Trip N.A. N.A. N.A. RH 101 N.A. 1. 2. 3'--4' il-32-LG:

N. P 1-64 A a 1-23 Power Range. Neutron 2. Flux

a. High Setpoint S D 2. 4) . Q N.A. N.A. 1. 2 9121-Aw]!

QQ R(4. 5)

b. Low Setpoint S R(4;5) S/U(1;9) N.A. N.A. F--2 ,1-22aNe..u r,

Q(9il7) F1-39 A a -

3. Power Range. Neutron N.A. R(4;5~,18) Q N.A. N.A. 1. 2 F1-23;AOi1 Flux. High Positive Rate rl-39 Ac d

4. Not Used

5. Intermediate Range. S R(4. 5) S/U(1;9) N.A. N.A. F--2 s.1 22 M; A ;

Neutron Flux Q(9;17) Source Range. R(4.13) S/U(159). N.A. N.A. 26, 3.4.5 F122 Ni l

6. S Neutron Flux 0(9.17) t i

[ CPSESMarkup of CTS 3M.3 3M 3-10 10/30M8

TABLE 4.3-1 (Continued) REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING M S FOR CHANNEL DEVICE WHIEH OPERATIONAL OPERATIONAL ACTUATION St'R"EILijXE ?1 44.A W CHANNEL CHANNEL CALIBRATION TEST TEST LOGIC TEST IS REOUIRED-FUNCTIONAL UNIT CHECK

14. Undervoltage--Reactor N.A. R H.A. Q(10) N.A. 48 Coolant Pumps Q(10) N.A. 18 (1-16 LSi4

15. Underfrequency--Reactor N.A. R N.A.

Coolant Pumps

16. Turbine Trip P

a. Low Fluid N.A. R N.A. S/U(la,10) N.A. i:1~24 LS 4 Oil Pressure P Turbine Stop Valve N.A. R N.A. S/U(la 10) N.A.

b. !1 24 LS 1 Closure

17. Safety Injection N.A. N.A. N.A. N.A. 1, 2 1

Input from ESFAS

18. Reactor Trip System Interlocks ;

Intermediate Range N.A. R(4) R N.A. N.A. 2* a. Neutron Flux, P-6 i

b. Low Power Reactor Trips Block, P-7 R N.A. N.A. 1, 2

1) Power Range N.A. R(4) i Neutron Flux P-10 N.A. R N.A. N.A. 1

2) Turbine First R Stage Pressure P-13 CPSESMarkup ofCTS3N.3 JN 3-12 10/3088

s TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTKi10N SURVEILLANCE REQUIREMENTS TRIP MODEG-

                                                                                                                                                                                                                 *1 # #

ANALOG ACTUATING CHANNEL DEVICE MASTER SLAVE FOR '4tICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEIM ANGE CHANNEL IS-RE0!! IRED CHECK CALIBRATION TEST TEST LOGIC TEST TEST _ TEST FUNCTIONAL UNIT

1. Safety Injection (ECCS, Rcactor Trip, fcciatcr Isolation, Control Rec;;; E;;;cre..;.y Rccieettlation E;;;ergacy Diesc1 Concrator Opcratica, Contai..a..t Vcnt Isclation Station Scrvice Water, Phasc A . .

                                                                                                                                                                                                               ,c2-19 LG a.: ;.

Isclatic .. Auniliary fccd.ecter "ctor Drivcn Pu;;;p, Turbiac Trip, C+acat CocHag Water, Esscatial Vcatilation Systies, and Contai. ant Spray Pu;;;p).- 1, 2, 3, 4 1 64-A N.A. N.A.

a. Manual Initiation N.A. N.A. N.A. 6) N.A.

lQ1-23 g M N.A. M(1) M(1) Q 1, 2, 3, 4

b. Automatic N.A. N.A. N.A.

Actuation Logic and Actuation Relays R Q N.A. N.A. N.A. N.A. 1, 2, 3

c. Containment S Pressure--High-1 N.A. N.A. N.A. N.A. 1, 2, 3

d. Pressurizer S R Q Pressure -Low R(5) Q N.A. N.A. N.A. N.A. 1, 2, 3

                                                                                                                                                                                                                   ,1 23 A_ -

e. Steam Line S Pressure--Low CPSESMarkup of CTS 3M.3 3M 3-39 10/30/98

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQ TRIP ANALOG ACTUATING MODES 91 44 g73' CHANNEL DEVICE MASTER SLAVE FOR '4110" ' OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY "='!EItCE . CHANNEL CHANNEL CHANNEL TEST LOGIC TEST TEST TEST _ IS RE00! RED-FUNCTIONAL UNIT CHECK CALIBRATION TEST

2. Containment Spray N.A. N.A. N.A. N.A. N.A. -1. 2. 3. 4

a. Manual Initiation N.A.

N.A. N.A. N.A. M(1) M(1) 0 1. 2. 3. 4

b. Automatic N.A.

Actuation Logic , and Actuation Relays S R Q N.A. N.A. N.A. N.A. 1. 2. 3 '

c. Containment Pressure--High-3 ;

3. Containment Isolation i

a. Phase "A" Isolation N.A. N.A. (6) N.A. N.A. N.A. 2.3.4

1) Manual N.A.

Initiation N.A. N.A. N.A. N.A. M(1) M(1) 0 1. 2. 3.-

2) Automatic 4 ;

Actuation Logic and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

l 3M 3-40 10B088 CPSESMarkup ofCTS 3N.3 _ _ . _ _ _ __ . , _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ . -- . - , , _ - - - . - - - - - _ _ =e. -m- .-. -m- w

18BLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES pg,44. gg , CHANNEL' DEVICE MASTER SLAVE FOR-WHEH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY S!E'!EIL' E C CHANNEL TEST' LOGIC TEST TEST TEST IS-REOUIRED. FUNCTIONAL UNIT CHECK CALIBRATION TEST

4. Ste6m Line Isolation

a. Manual Initiation N.A. N.A. N.A. h N.A. N.A. N.A. 1. 2, 3 1-64 A ,

N.A. N.A. N.A. N.A. M(1) M(1) Q 1. 2. 3 jQ1-23

b. Automatic Actuation Logic and Actuation Relays R Q N.A. N.A. N.A. N.A. 1, 2. 3

c. Containment S Pressure--High 2 R(5), Q N.A. N.A. N.A. N.A. 1, 2, 3 1;23 A M '

d. Steam Line S ,

Pressure--Low Q N.A. N,A. N.A. N.A. -3 1-23 Ah:ii

e. Steam Line S R(5).

Pressure--Negative Rate High ,

5. Turbine Trip and Feedwater Isolation N.A. N.A. M(1) M(1) Q 1, 2

a. Automatic N.A. N.A.

Actuation Logic and Actuation Relays

b. Steam Generator S R Q N.A. N.A. N.A. N.A. 1, 2 ;

Water Level-- High-High

c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

CPSES Markup of CTS 3N.3 3M 3-42 10/30A>8

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIRENENTS TRIP ANALOG ACTUATING MODES ;.144 gg4 CHANNEL DEVICE MASTER SLAVE FOR h'!!Cli CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SUR"EILLA.KiE CHANNEL CHECK CALIBRATION TEST TEST LOGIC TEST TEST IE11_ IS REOUIRED FUNCTIONAL UNIT

9. Control Room Emergency Recirculation ;-2-12-N N.A. N.A. N.A. 6) N.A. N.A. N.A. AM 3,g,3

a. Manual Initiation 0 1-23 new;;; Automatic" ActuationJ tAE3MM N. A;ESZEIE N; ATRy;MLEN. A.MERN!ATTFA;hM:A?:;cN {Ag r2 47.MM'

LLogiciandActuat100 1 Relays

b. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

10. Engineered Safety Features Actuation System Interlocks

a. Pressurizer N.A. R Q N.A. N.A. N.A. N.A. 1. 2. 3 Pressure. P-11 1 64-A

b. Reactor Trip. P-4 H.A. N.A. N.A. 6). N.A. N.A. N.A. 1. 3. 3 0 1 23 ra

11. Solid State Safeguards Sequencer (SSSS)

a. Safety Injection N.A. R N.A. M(1. 3. 4) N.A. N.A. N.A. 1. 2. 3. 4 Sequence i2-13-Ae9l

b. Blackout N.A. R N.A. N(1. 3. 4) N.A. N.A. N.A. 1.2. 3.4 Sequence 3M 3-45 1g/3ogg CPSES Markup ofCTS3H.3

TABLE 4.3 2 (Continued) TABLE NOTATIONS (1) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS. (2) Whenever the plant is in COLD SHUTDOWN for 72 hours or more and if this surveillance testing has not been performed in the previous 92 days. (3) Setpoint verification is not applicable. (4) Actuation of final devices not included. W] Includesige!1fgrtionD W Z h jappligble? zg,ggg; M1 YetXtcation;;ofisetpoint;mtztest1 red; T 70 1 23 d f i l l l i i= CPSESMarkup of CTS 3M.3 3M 3-46 10/30/98 l l

i l CHANGE l NUMBER HlillC DESCRIPTION and ESFAS sensor response time testing to be performed per WCAP-13632-P A Revision 2 " Elimination of Pressure Sensor Response Time Testing Requirements," or other similar methodologies. This change is consistent with traveler TSTF 111, which revises the Bases for ITS SR 3.3.1.16 and SR 3.3.2.10 to allow the elimination of pressure sensor response time testing. CPSES has not yet provided a plant specific submittal describing the manner in WCAP 13632-P A or a similar methodology will be applied. Therefore, until a plant-specific submittal is approved by the NRC, CPSES.will continue to response time test all Reactor Trip System and ; ESFAS sensors. The proposed changes to the wording in the Technical Specifications remain applicable, regardless of the implementation of the sensor response time i elimination. 1 59 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 1 60 - Not used. 1-61 M This change reflects a revision to CPSES current ACTION Statement 6. If the requirements of current ACTION Statement 6 are not met. LC0 3.0.3 would be entered which would allow 7 hours to exit the LC0 applicability by entering MODE 2. In accordance with the ISTS, this ACTION Statement is revised to state that if the ACTION requirements are not met, the plant must be taken below the P 7 interlock setpoint (the LCO applicability) within 6 hours. Thus, this change is more restrictive, by one hour, than the current TS. 0 1 A GEN IL63 A A1]iteformattj_nggrenumbetingGand: editorial rewotingjfslinzagcordangeyith~the3estinghous_e d l StandairdlechnicaESpeciffgat1AnsENUREGIId31EDuting _the deve]ppeent;g.ertai_n; wording preferegeefor;English 1anguage:conventjons)ere adoptedDsjXtesultf4the Iechnj cal SpecificatipnsJTSEshould;be; note;teadily readabj ezand;therefore3nderstandabH2b3Cp] ent; operators and"OtherMetCDurigg 3heltefotsattjpgZtegumbeting; and;tewotdtng:processnno; technical; changes 36therjactual oninterpre_tational)_'to;the TSyer,eLaade~unless;they were identified.a'nd; justified # i 1-64 A Th_e;tefueljng;interva];TADOT_s"forfunctiona] Unjts31 and;17]!jn;CTSlab]e.X311Lhaye~beenlevjsed;to includ 0 1 23 l OXi S. ting; Note V0 CSetpoint Neri ficationlis:not CPSES Description of Changes to CTS 3M.3 14 10/30/98

l l CHANGE l NUMBER H2iG DESCRIPTION cablelmL1!n!!#isetrefue]1ng;1ntervaLTAoaIs;fot FunctionaRik!1tsI[UaZ21agXal1UMg9.aland;10.b] o 2 23 in;ctsJahielEntagbeen terjsed; toted.apewlmate [UMBit10E881 serf'8B!;po.1Rt]!p&2MBG!sd!A@!# camses.aglongannet23ssing2segggheJgMpct

                                               ;,,           t. m x a.; m 3sqq_uggen; l

1MEmmteMfeWEmittmgpetapimanegges2uagrassenet igg 80lltRNelusMts3pprtstedaBel!Mp30Mbumen!tto c!mWlEII!RBagualstatMstletWESBiggetE4lisse 13!lIBR!0sinessungre3gtwsthese Rgggggsiglp!ts3C4engGgl sgKan acigne!aggesentat j upt;the:co!Tagagenempts:3;'3;1;14; 3^3XIll."JedL32A111havexaplicitaotelto:thi ettect; lj65 Notlapplicab] Q oiCPSES G See:Co m ersion ComparisonJ able ; (Enclosutgl3Bl. 1:66 LS!45 lheX15Mlows3ertainlinopetableichannelsZorlforis.ame P1mtt;cne;othetichannelZto;belpypassedifotitestjng 0 3.3.J ' peCSpMiticatje3;Enrori4;3XNEThe2nte!!tlof typspassIisito11191testinghat2M131tetifBhat the:channeE!Wsit!eein restoredMag;0PEIUllLE3Xindjtjenlagd caLbeltetorneOEssitylceAI!!plallowed#pasciselfor te_stismosenwilestedIMdislias!!Egite!csa!ety agajysesmitlha'sjeedetete@ltdl1!!stj!ghelimpactIof;ths alle!soypasses:itoir!nime17pleegheritEbyppstifsifot setMLat3etitlestionMtespg!s(tjmeli!adtteatghas; go 1spect1opitheJiastreelysisMIh1Celiange3ould3selete theteferencelto3pecificatioGLsmatill:4m2 min 3he allowedDpass;nosesicmtainediq~cettagcJsJCTIon statements;ahus:anreitting ;amlt. estioneededlfor testantt1MEtheTinopstable3tunction; li6Z M NotZapplicableit0CPSESESee~C. ontersMCompatisonlab]e (Enclosute23BL LS154 Notiapp11 cable 3o;CPSES E SeelConVersion; Comparison 3 Table 1168 gnclosure:138). 1169 M Not.; applicable;to;CINESIESee; Conversion; Comparison: Table , QnclosureG3Bl. l l 2 01 A The Engineered Safety Features Actuation System l Instrumentation [ ] Allowable Values are moved to ITS Table 3.3.2-1. 2 02 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 14a 10BOR8 CPSES Description of Changes to CTS 3N.3

Page 10a of 22 CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 APPLICABILITY TECH SPEC CHANGE DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK Yes Yes Yes Yes 1 63 All refermetting.. renumbering.1end editorial,uording.istin_.accordance with_the A Westinghouse; Standard Jechnical,Specifjcations E NUREG-14311 yes yes les ye ' 64 Notes;are.added;to lest 4,3:1;andets3 2 tto,emc]ude,eetppfat;verjficetjens 0-1~23 ' A durjng;TADOTsionlunctionaliUnitsithatLJoyotihogo;setpointslassocleM,trttti a t yes yes 5e 1 65 ExplanationistA ITSdreatmentxofneeven(slavez relays (withiextendediarvei,1}ance No A f n_ JJ yes Yes yes ; Yes 0-3.3,. 1 66 Thisichengesson)d; delete;the;referenceitoppacification14;3;111gandM2il;,ist LS-45 the. allowed.topassinates: containeditelesttein_CI5:#CTION;statementsatless ' persitting , attesting;needed1fortreeteration;ofmiinoperelelfunction] I Yes No IE) No 1 67 This, change; revices. CTS _ ACTION 533;es42p:te. provide; epecifici shutdaus) -- N requiremesits toiex1tcApp11 cab 111tmi%11eu,ofiapplying cts;.LCo;3;.opa71,1s E 0-3 3 44 E changea is..more;restCictive by oneihmekthen:the;CT54 5 Thisichengeideletes;DCPPP,CTSJablef,3;1; note;(8)iehich11s!applicableLto;the yesMseetalso No No No less source;rangeaThe CNJ LS:54 a vetiticationicennotibe; performed;1%)mEi3*;4*landMisince the;panet:andiintermediateirange; channels; are'yot; required [tojefererablejuntil 1:69 M R 24 Thistchangee appliesinew noted20)1te DCPPsCTStTable;4:3i1; function 6ltsource yesr-iseeiaiso 50 les No ' It69 z range, neutron fluxJ CNI M < 1-68 LS-54 Yes Yes Yes Yes l 2 01 The Engineered Safety Features Actuation System Instrumentation [ ] Allowable A Values are moved to ITS Table 3.3.2-1. i i 10B088 CPSES Conversion Comparison Table - CTS 3N.3

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 1-25 APPLICABILITY: DC, CP, WC, CA REQUEST: NUREG-1431, Rev.1 incorporates the current TS 4.0.4 exception from Table 4.3-1 Notes (2), (3), and (6) into the ITS SR 3.3.1.2,3.3.1.3, and 3.3.1.6 surveillance frequencies. Comment: No justification has been provided for changing the power level in CTS Table 4.3-1 note 3 from 15% to 50%. For note (2) the addition of the time period for 1 completion of the CHANNEL CAllBRATION does not provide clarification to this surveillance as this is a daily surveillance and if not performed within 24 hours, this functional unit would be declared inoperable. Furthermore, this change is categorized as an administrative change when, in fact, the change results in less restrictive TS requirements. FLOG RESPONSE: The 50% RTP level establishes the lower safety analysis boundary for the AFD and OPTR LCOs. Below 50% RTP there are no corrective actions required for off-normal power distributions. DOC 1-25-A has been revised and changed to an "M" DOC, since the new limitations are more restrictive than the current TS with its SR 4.0.4 exception. l l ! ATTACHED PAGES: ! l Enci 2 3/4 3-14 Enci 3A 8 and 9 ! Enci 3B 5 I l I , l l 1 l a i-

  . _- = ._.         ~~                    .            ..             ..     .-_ .. _ _. -      . _ . - - .          ..

l TABLE 4.3-1 (Continued) l TABLE NOTATIONS I l

Only if thC rGGCtcT ITip brCONCrs h0pp;n I; bc in IhC ClosGd positicG $1-44-'A N l- ard the Control ",cd Driv; Systc;;; is ;pabic of red withdr:wal.
Scisw " 5 (Intc T.ediate ",;n;c !!cutren Flux Intericck) Sctpcint.

Sels " 10 (Low Satpcint ";wcr "on;c !!cution Flux Intericck) Sctpcint. d AL..,. AL. M i fA& Mm .- \ P &- J & r urv v b betw a s inb a brvvw s / .rb b y s s i b .

               ".bcvc the " 0 ("c;ctor trip en Turbin; trip Interlock) Sctpcint.
            ' WhenitMMJggLuegor'M ;41 W.jdpAnad                                                              ;1.gsgya    j (1)         If not performed in previous 3R92 days.                                         11-24 15 4 l

(la)Tilfinotsp!qformed"inMyioGsl311 days] 41-24;LSvi l I i (2) Comparison of calorimetric to excore power and N-16 power , indication Within"24 hours 2after1THERHALM;is above 15% of 1 25 RATED THERMAL POWER. Adjust excore channel and/or N 16 012 i I channel gains consistent with calorimetric power if absolute difference of the respective channel is greater than 2%. The l provisions of Specification 4.0.4 arc act opplicabic for entry into tiOCE 1 or 2. (3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE With1N24;hourQLfte@lEl]MA1L P0hER_1s1M50!;ebeve 1 25 0 1-

Et of RATED THERMAL POWER. Recalibrate if the absolute l

difference is greater than or equal to 3%. For the purpose of these surveillance requirements. "M" is defined as at least l once per 31 EFPD. The provisicas of Spccification 4.0.4 arc not I applicabic for entry into "00E 1 cr 2. (4) Neutron and N-16 detectors may be excluded from CHANNEL CALIBRATION. L (5) Octactor platcou curvcs shall bc obtaincd and evaluated. For the Intermediate Range Neutron Flux. Power Range Neutron Flux i& 26-LG H and N 16 channels, the provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2. 1 l (6) Incore-Excore Calibration, ebeve within772; hours 7afteR 1 25 achieving:equilibtium~ conditions"aboveJ75% of RATED THERMAL POWER. For the purpose of these surveillance requirements "Q" 012 , is defined as at least once per 92 EFPD. The provisicas of Spccification 4.0.4 crc not opplicable for catry into tiOOC 1 , er : i (7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

I d

CPSESMarkup of CTS 3N.3 3M 3-14 10/30198 j

CHANGE NUMBER RSE DESCRIPTION interlocks are verified to be in their required state during all COTS on the Power Range Neutron Flux Low and Intermediate Range Neutron Flux trip functions. These changes are consistent with NUREG-1431 Rev.1 and g,3,3,49 travelerR742] '400 105. 1-23 A This change adds new Note [(18)] to current TS Table 4.3-1 and new Note [(5)] to current TS Table 4.3-2 that explicitly require the 18 month calibrations to include verifications of affected time constants, consistent with NUREG-1431 Rev.1. 1 24 LS 9 This change reflects a relaxation in the performance of COTS prior to startup, consistent with NUREG-1431. Rev. 1. These COTS, for the Power Range Neutron Flux - Low, Intermediate Range Neutron Flux, and Source Range Neutron Flux trip functions, will not be required if performed within the previous 92 days. Note [(1)] of CTS Table 4.3 1 has been revised to extend this period from 31 days to 92 days. Note [(la)] is added for use with the turbine trip function TAD 0Ts, for which no such change was , provided.

1-25 NUREG 1431 Rev. 1 incorporates the current TS 4.0.4 o-1-25 exception for the surveillances covered by current TS Table 4.31 Notes (2). (3), and (6) into the ISTS SR 3.3.1.2, 3.3.1.3, and 3.3.1.6 surveillance frequencies. 3 In the current TS. these surveillances have no time i requirements.[ ] In general, the combined effect of current TS 4.0.3 and current TS 4.0.4 would allow [24 hours] for completion of a surveillance if it were not performed upon entry into the specified H0DE or other condition for that surveillance. Current TS 4.0.3 allows [24 hours] for the completion of a surveillance once the appropriate MODE or plant condition is established. In the improved TS. the TS 4.0.4 exceptions are incorporated as a NOTE in each affected surveillance. In converting to the NUREG 1431 format. ITS SR 3.3.1.2, SR 3.3.1.3, and SR 3.3.1.6 require these surveillances to be performed within [24] hours after THERMAL POWER is greater than or equal to 15% RTP (current TS Note (2) for the comparison of NIS power to calorimetric power), within [24] hours after 50% RTP (current TS Note (3) for the comparison of excore Axial Flux Difference (AFD) to incore AFD), and [within 72 hours after achieving equilibrium conditions with THERMAL POWER greater than or equal to 75%] RTP (current TS Note (6) for the incore excore calibration), respectively. Since these surveillances are conditional on THERMAL POWER 8 10B088 CPSES Description of Changes to CTS 3N.3

CHANGE NUMBER ESEC DESCRfPTION levels greater than the MODE 2 to MODE 1 breakpoint, there is no need to retain the current TS 4.0.4 exception, as discussed in ITS Section 1.4, as long as the ITS Surveillance Notes allow the plant to reach conditions appropriate for the performance of the surveillances. The power level at which the monthly surveillance is performed to compare incore vs. excore AFD. and adjustment of the NIS as required by Note (3) of current TS Table 4.3 1, is changed from 2 15% RTP to 2 50% RTP. This change is also precipitated by the conversion to the ITS format which replaces the current TS 4.0.4 exception with a finite time interval after exceeding a specified power level. With the deletion of the current TS 4.0.4 exception, the specified power level in ITS SR 3.3.1.3 should reflect the applicable safety analysis basis consistent with the [ Applicability and] Required Actions of ITS LC0 3.2.3 (AFD) and LOC 3.2.4 (0PTR). As with the changes discussed above, there is no need to retain the current TS 4.0.4 exception as long as the ITS Surveillance Notes allow the plant to reach conditions appropriate for the performance of the surveillances, ese changes are con;i i r d e tinistrative more testrictjvejinnatureinthattheysicplyreficctthm o.1 25 incorpor:tica of sincelthe current TS 4.0.4 exceptio ar_eMRisitedBinto the i;progTS. -. 1 26 LG This change moves the details concerning NIS detector calibration to the BASES for ITS SR 3.3.1.11, consistent with NUREG 1431 Rev.1. This information is more appropriately controlled outside of the TS while the calibration requirement itself and its Frequency are unchanged. 1 27 LS-10 Surveillances on the Source Range Neutron Flux trip function are reorganized to reflect plant status in accordance with NUREG 1431 Rev. 1. New Note [(17)] requires that the quarterly COT be performed within 4 hours after reducing power below the respective source range instrumentation Applicabilities, if not performed within the previous [92] days. Since the COT is valid for I [92] days, there is no need to repeat it if one has been performed within the prior [ quarter]. The 4 hour allowance permits a normal shutdown to proceed j without a delay for testing in MODE 2 and for a short time in MODE 3 until a]1;rodslareifu1Minsertediand TR-3.3 006 theJod Conttollsystenjsgendeted]ncapable ofirod wjthdrawa1Qfter"which the 1c;ctor Trip Orcakcr; crc l cpcacd and this trip function no longer provides protection. Since the current 9 10B088 CPSES Description of Changes to CTS 3/4.3

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 5 of 22 TECH SPEC CHANGE APPLICABILITY DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK Yes No - see CH Yes Yes 1-19 If the requirements of current ACTION Statement [6] are not met. LCO 3.0.3 would 1-61-H LS-8 be entered. In accordance with the ISTS this ACTION Statement is revised to state that, if the ACTION requirements ~are not met, the plant must be taken below the P-7 interlock setpoint within the next 6 hours. [The Applicability for Functional Units 9.11,12,14. and 15 in current TS Table 3.3-1 is also revised to add new footnote (b).] No No No Yes 1-20 Callaway's current ACTION Statement 31 is reformatted per NUREG-1431 Rev. I to A require restoration of an inoperable channel within 6 hours or the plant must be taken to MODE 3 within 12 hours. This is an administrative change since the total time to exit the Applicability is unchanged. Yes Yes Yes Yes 1-21 This change reflects the reorganization of the surveillances on the A incore/excore axial flux difference. There is no change to the surveillances or how they are performed. See also CN 1-25-A. Yes Yes Yes Yes 1 22 Quarterly COTS have been added for power range - low and intermediate range flux H channels. [The requirement to verify the state of P-6 and P-10 has been added for these COTS.] Yes Yes Yes Yes 1-23 This change adds notes to the RTS and ESFAS SR Tables 4.3-1 and 4.3-2 that A explicitly require the 18-month calibrations to include verifications of affected time constants where applicable. The COTS for the Power Range Neutron Flux - Low setpoint, the Intermediate Range Yes Yes Yes Yes 1-24 LS-9 Neutron Flux and the Source Range Neutron Flux trip functions will no longer be required if performed within the previous 92 days (extended from 31 days). Note [la] is added for use with the turbine trip functions, for which no such change was provided. NUREG-1431 Rev.1 incorporates the current TS 4.0.4 exception from Table 4.3-1 Yes Yes Yes Yes 1- 5 AM Notes (2) (3), and (6) into the ITS SR 3.3.1.2. 3.3.1.3 and 3.3.1.6 surveillance frequencies. l01 \ This change moves detail concerning NIS detector operation and testing to the Yes Yes Yes Yes 1-26 LG BASES for ITS SR 3.3.1.11. CPSES Conversion Comparison Table - CTS 3N.3 1030/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-37 APPLICABILITY: DC, CP, WC, CA REQUEST: In the current TS, the " Minimum Channels OPERABLE" is one less than the " Total Number of Channels" for Functional Units [18.c] (P-8), [18.d](P-9), and [18.e](P-10) in Table 3.3-1 and Functional Unit [11.a](P-11)in Table [3.3-3]. For these Reactor Trip System and ESFAS interlocks, current ACTION Statements [8 and 20] for an inoperable channel are based on the " Minimum Channels OPERABLE" columns in Tables 3.3-1 and [3.3-3]. In the improved TS, only the " Total Number of Channels" information is retained in the LCO and that column is relabeled as the " Required Channels", as discussed in CN 1-04-LG and CN 1-43-A. Required Actions in improved TS 3.3.1 Conditions S and T and improved TS 3.3.2 Condition L are tied to the Required Channels. Therefore, the required permissive channels for these Functional Units are revised in the current TS. Refer also to CN 1-51-LG for P-7. Comment: [ DOC] - The CTS markup changes the total number of channels for the P7, P8, P9,and P10 interlocks (CTS functions 22b, c, d, and e) from 4 channels to 3 and the required number of channels in the ITS is 3 instead of 4. This is counter to the format of the improved TS. Allinstalled RTS channels should be required to be OPERABLE and actions provided for any channel out of service. if the impact of a single inoperable channel is very low, the Required Action may be minimal. Revise the ITS Table to require 4 channels for P7, P8, P9,and P10 interlocks. [OOS issue] The CTS markup changes the total number of channels for the P-11 interlock (CTS function 8a) from 3 channels to 2. The intericek enables on any two of three channels, thus proposed required channels do not account for single channel failures. This is counter to the format of the improved tech specs and this is a change to the CTS. All installed channels are required to be operable and actions provided for any channel out of service. If the impact of a single inoperable channel is very low, the required action may be minimal. This change in conjunction with JFD 3.3-44 (multiple function entry for inoperable interlock channels) are OOS issues. Sing e channel inoperabilities can be verified and operation is indefinite, but multiple inoperable channels as proposed could place the plant in an unsafe condition if the applicable P-11 setpoint (AV)is disabled because power is lowered and then re-enabled because power is raised again. At the transition back into the power range when P-11 is required the ITS would not require subsequent reverification of setpoints per Required Action L.1. {not WC} The CTS markup changes the total number of channels for the P11 interlock (CTS function 8a) from 3 channels to 2. This is counter to the format of the improved tech specs. Allinstalled RTS channe!s should be required to be OPERABLE and actions provided for any channel out of service if the impact of a single inoperable channelis very low, the Required Action may be minimal. FLOG RESPONSE: See the response to Comment Number O 3.3-44. All permissive channels will be required OPERABLE in the ITS and DOC 1-37-A was changed to 1-37-M. ATTACHED PAGES: I None m

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-51 APPLICABILITY: JC, CP, WC, CA REQUEST: This change moves the description of the P-7 inputs, i.e., P-10 cnd P-13, to the Bases since they are duplicated by Functional Units [18.e and 18.f] and lists "1 per train" under the Required Channels column. [] Comment: The requirement for a channel operational test of the P-7 function should not be deletec. The P-7 function is a distinct function for which surveillance must be specified. Eliminating the channel calibration requirement is acceptable since P-7 has no setpoint of it own. The COT, however, should be retained because the P-7 function has elements which are not part of P-10 or P FLOG RESPONSE: The P-7 logic function is tested under CTS Table 4.3-1 Functional Unit 20 (Functional Unit 22 for DCPP) and will be tested under the ITS as described in the response to Comment Number Q 3.3-54. This comment is directed to DCPP, which has surveillance requirements associated with P-7 in the CTS. As explained in the response to Comment Number Q 3.3-54, the testing requirements specified for P-7 are inappropriate for a logic circuit. DOC 1-59-LS-46 has been created to justify the deletion of the CHANNEL CAllBRATION, per the reviewer's suggestion. In addition, the new LS DOC justifies the deletion of the COT and the adoption of an ACTUATION LOGIC TEST on a refueling outage basis. As a result of this reyision, DOC 1-51-LG is revised to delete the bracketed sentence at the end of the DOC (empty brackets for the other FLOG plants). ATTACHED C/4GES: None m

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-53 APPLICABILITY: DC, CP, WC, CA REQUEST: Current TS Table 3.3-1 ACTION Statement [2.c] is revised to be consistent with ITS SR 3.2.4.2, as discussed in CN 4-04-LS-12 in the 3/4.2 package. Comment: The note "* on CTS markup action 2.c is justified as changing the completion time to be consistent with ITS SR 3.2.4.2. This change is categorized as an administrative change to the CTS. Approval of ITS SR 3.2.4.2 is pending staff approval because it represents a less restrictive change to CTS 4.2.4.2. The staff concludes note "* is also less restrictive to CTS T3.3-1. Provide a revised DOC for this change. The note *** is also shown in the CTS markup to apply to Source Range shutdown modes. This note is not included in the BDPS LCO. Provide clarification of the intetnt of the CTS markup. FLOG RESPONSE: DOC 1-53-A has been withdrawn. See also the response to Comment Number Q 3.3-120 and the attached pages for that response. The second comment refers only to Callaway and was resolved during meetings with NRC staff between September 15-18,1998, as discussed in Reference 6. ATTACHED PAGES: None

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1-58 APPLICABILITY: CP REQUEST: The proposed change would allow Reactor Trip System and ESFAS sensor response time testing to be performed per WCAP-13632-P-A Revision 2, " Elimination of Pressure Sensor Response Time Testing Requirements," or other similar methodologies. This change is consistent with traveler TSTF-111, which revises the Bases for ITS SR 3.3.1.16 and SR 3.3.2.10 to allow the elimination of pressure sensor response time testing. Comment: Reject - The 1TS proposes generic changes to the STS by deleting SR 3.3.1.16 for applicable functions in T3.3.1-1 and modifying SR 3.3.1.16 that are not included in an approved TSTF. Adoption of WCAP-13632 for eliminating selected sensor response time testing requires staff review independent of the Conversion TS review. Based on 8/14/98 meeting the staff noted that the category of response to TSTF-111 Rev 1 is " modify." The staff also expressed concerns with generic format changes proposed for the ITS which were not proposed by TSTF-111. See also JFD 3.3-55 comment response. FLOG RESPONSE: Per JFD 3.3-55, the active verb in STS SR 3.3.1.16, SR 3.3.2.10, and others, is " verify." For consistency with the STS, the active verb in the CTS 4.3.1.2 and 4.3.2.2 is changed from " demonstrated" to " verified " Use of " verify" does not require adoption of WCAP-13632 nor the elimination of response time testing. Because CPSES has not demonstrated to the NRC, via a license amendment request, compliance with the requirements of WCAP-13632, CPSES can not eliminate response time testing. The use of the verb " verify" does not imply, in any manner, anything to the contrary. ATTACHED PAGES: None.

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-03 (3.3) APPLICABILITY: CP REQUEST: The engineered safety features actuation system instrumentation trip Setpoints are moved to a licensee controlled document. Comment: {CP} CTS T3.3-3 specifies % AVs in terms of" narrow range instrument span." Revise ITS Table 3.3.2-1 to include this unit of level indication. FLOG RESPONSE: See response to Comment Number O 3.3d GEN. l l l ATTACHED PAGES: l See attached pages for Comment Number Q 3.3d GEN l l I

2 j 1

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-05(3.3) APPLICABILITY: DC,CP REQUEST: The Functional Unit for containment purge isolation, CTS 3.c, is moved to improved TS 3.3.6. Improved TS 3.3.6 adds requirements on the OPERABILITY of the containment purge radiation monitors and extends the Applicability for the manualinitiation and ; BOP ESFAS actuation logic to include during movement of irradiated fuel assemblies within '

     - containment and core alterations.

Comment: Action 18 and CTS Table 3.3.4 (page 3/4-25) reference DOC 02-05-M. The description of change discussion says this change is not applicable to Diablo l Canyon. Provide the correct reference and CTS change documentation. l l FLOG RESPONSE: For DCPP, the entry for enclosure 3A is incorrect and has been revised. ! In addition, the applicability for FUNCTIONAL UNIT 3.c.1) on Table 3.3-3 has been revised to show the MODE 6 inferred requirement from the CTS and delete the CORE ALTERATION reference. The MODE 6 requirement for a single Containment Ventilation Exhaust Radiation monitor (RM-44A or 448) for FUNCTIONAL UNIT 3.c.4) is shown on Table 3.3-6 INSTRUMENT 3.a.3) and 3.b.1), but is repeated here for clarity. In addition, Table 3.3-3 has been revised to show that FUNCTIONAL UNIT 3.c.4)is required to be operable during MODE 6 and only requires one channel, again for clarity since it is shown in Table 3.3-6, and during i movement of irradiated fuel in containment. CPSES has also adopted DOC 2-05-M and applied it to CTS Table 3.3-4, FUNCTIONAL UNIT 2. Specifically, the Applicable Modes for this functional unit is extended from MODES 1, 2,3,4, and 6 during CORE ALTERATIONS or movement of irradiated fuel within containment to MODES 1,2,3, and 4 and during CORE ALTERATIONS or movement of irradiated fuel within containment, regardless of whether the plant is in MODE 5,6 or no mode. ATTACHED PAGES: Enci 2 3/4 3-48 Enci 3A 15 Enci 3B 11 l i 4 i , i j ; k i

TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS REQUIRED C:':::t:ELS HINIMUH v1 43-A-A TO CHANNELS APPLICABLE ALAR 4/ TRIP TRIP /AEARM OPEPJOLE MODES SETPOINT AlH0!1 i-1 04-LG4 FUNCTIONAL UNIT

1. RCS Leakage Detection Particulate Radioactivity N-A- 1 1,2,3,4 N.A. 29 a.

Gaseous Radioactivity -N-A- 1 1,2,3,4 N.A. 29 b.

2. Containment Ventilation Isolation 2

1,2,3,4,Q* * -. Gaseous Radioactivity 4 1 27

3. Control Room 4/4nteke 2/ intake AM 51.4x10-*pC1/ml 28 r3-04 M Air Intake-Radiation Level 1;2,3,4,5,6 and during movement ofdirradiated; fuel assemblies

Must satisfy Gaseous Effluent Dose Rate requirements in Part I of the ODCH.

                                                                                                                  **        During CORE ALTERATIONS or movement of irradiated fuel within containment.

CPSES MarAup of CTS 3N.3 3M 3-48 1030M8

I i CHANGE NUMBER HSiG DESCRIPTION 2 04 LG The requirenients stipulated in ACTIONS a and b are moved to ITS Table 3.3.2-1, with explicit direction contained in the ITS ACTIONS Bases. N 2 05 H Not epplicabic to CPSES. Scc C;nvcrsion C a pori,cn T;bic (Enciesurc 38).7sJRiena13nitJfpt D Om!Beamrematpatjap3%2!EEITeMgaf4 East 3malemntg]EsomuodygurjasinspinIsa i lumiuRGEE33m@m!dsitsug!ppLscaldighthe [CogatesqE4mJttsstiertssolutsgnacepstandestc'.to inquen.Rrtss amament;;of2ttratetatedmJssemb11es , Witingicantatnaertt2[end;CoreRteratjonsZtegard.less ' l MODE). l 2 06 LS 33 Not ;ppliable to CPSES. Scc Conscrsion C a parison 0225 Tobic (Enclosurc OS). FunctionallUnitXa;1)lof current ; i TS;Tablej [3.332]~,~ nanualj nitiation :oflindividualisteam line21solationMis;notjan ESFJunctionland jtlis;therefore deleted;along XithiitsMIONiStatement2[21];fromlthe , ESEASiTSZconsjstentiwith_NUREG;1431;Rev211 i 2 07 LS-11 [ Note (c) to current T: Tobic 3.3 2 for the Stcs Line Isolation function:1 'Jaits 4.:.2, 4.b 4.c. 4.d. ;nd 4.c : is revised to stat; th t the LC0 requirencats erc net ; epplic:bic in "00ES 2 end 3 den the "SI"s ;rc closed erd dc;ctivoted.] Note [(g)] is added to current TS 0 2 07 Table [3.3 2] for the Feedwater Isolation and Turbine Trip Function [ Functional Units 5.a. 5.b] to state that the LC0 requirements are not applicable when the [FIVs and bypass valves] are closed [and deactivated or isolated by a closed manual valve];;thereforeJitMrelisino~need for the;associatedlactuatien ttDstrumentation1to;beloperable;] T_heiclosjtre_loDhel.1dentineealtreszis;suff_ici_entdo ensutejttjelisolat_1on2functionljgicomplete. When these valves are closed [and deactivated or isolated), they are already performing their safety function. These changes are consistent with NUREG 1431 Rev.1. 2 08 H [New ACTION Statement 17.2 replaces ACTION Statement 17 in current TS Table 3.3 2 Functional Unit 5.b. New shutdown requirements are added for Action 17, new Action 17.1 and new Action 17.2.] These ACTION Statements, written to reflect the Applicability of the affected channels and for consistency with ITS 3.3.2 [ Conditions D. I and K]. are more restrictive, by one hour, than the current ACTION Statement [s] which invoke [ ] LCO 3.0.3 if the inoperable channel is not placed in trip within 6 hours. 15 10B088 CPSES Description of Changes to CTS 3N.3 i

Page 11 cf 22 CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 APPLICABILITY TECH SPEC CHANGE DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK No - not in No - not in Yes Yes 2-02 CTS ACTION b.1. Equation 2.2-1. and the values for Total Allowance (TA). Z, and current TS. current TS. A Sensor Error (S) are deleted consistent with NUREG-1431 Rev. 1. No - retained Yes - Hoved to Yes - Moved Yes - Hoved to 2-03 The Engineered Safety Features Actuation System Instrumentation Trip Setpoints to USAR. ITS 3.3.2 in ITS. Bases. LG are moved to a licensee controlled document. Bases. Yes Yes Yes Yes 2 04 The requirements stipulated in ACTIONS a and b are moved to ITS Table 3.3.2 1. LG with explicit direction contained in the ITS ACTIONS Bases.

                                                                                                                                                                                          ";    ;cc                          "; ;cc              Yes                        Yes 2-05                            onal Unit for Containmenth[pergeiVentilation] Isolation CTS [3-e-C" 2 20 A.Yes                      C" 2 20 ^.yes H      ' Table,3.3 4 Junctional: Unit. 2]. is moved to improved TS 3.3.6. Improved
                                                                                           .                                                                                                                                                                                                    mui TS 3.3.6 [edd; ccqui. _..;; on t';c 0"C"""!LI" ;f the so .t;i.-... p..w 020 radiction ;;;cnit; ; nd] extends the Applicability for the ["=u;l !niti; tion ;-d "0" ESTWContai.nmentJentilationilsolation] actuation logic to include during movement of irradiated fuel assemblies within containment [and Core Alterations;                                                                                                               ~
                    - pa.ofMODE].

2-06 Functional Unit 4.a.1) of current TS Table [3.3-32] has been deleted. No - retain CTS.

                                                                                                                                                                                                                             "; R c C" 2 25-Ar Yes "o R; C" 2-25-A- yes.

Yes f LS-33 Yes Yes Yes Yes 2 07 ["ct: (c) i; = di' icd for cu..s..; 5 T;bic 3.0 2 for thc Stc= Linc I;MeHen LS-11 Tunction to :t;tc th;t th: LCO scqui. m ..t; arc not ;pplicabic ' "^^C0 2 =d 3

                       ~._:.m.                  ...~.,_.._..._].                                                                        Note [(g)] is added to current TS                                                                                                                  B0-20' Table [3.3-2] for the Feedwater Isolation and Turbine Trip Function to state that the LCO requirements are not applicable when the [FIVs] are closed and deactivated [or isolated).

Yes Yes Yes Yes 2-08 [New Shutdown requirements are added for ACTION 17. new ACTION 17.1 and new M ACTION 17.2] These ACTION Statements. written to reflect the Applicability of the affected channels, are more restrictive, by one hour, than the current ACTION Statement [] which invoke [s] LCO 3.0.3 if the inoperable channel is not placed in trip within 6 hours. Yes - Hoved to Yes - Moved to Yes - Moved Yes - Moved to 2 09 Separate ESFAS entries for the motor-driven and turbine-driven auxiliary Bases. Bases. to Bases. Bases. LG feedwater pumps are no longer necessary. The only difference in the requirements (an SR 4.0.4 exception for response time testing of the turbine-driven auxiliary feedwater pump) has been addressed in the ITS by a Note in Surveillance Requirement 3.3.2.10. [] CPSES Conversion Comparison Tame - CTS 3N.3 102088

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-07(3.3) APPLICABILITY: DC, CP, WC, CA REQUEST: [ Note (a) is added to current TS Table 3.3-3 for the steam line isolation function to state that the LCO requirements are not applicable in MODES 2 and 3 when the MSIVs are closed.] Note [(b)] is added to current TS Table [3.3-3] for the feedwater isolation and turbine , trip function to state that the LCO requirements are not applicable when the [MFIVs] are closed (). Comment: Explain why the tech spec limits that remain provide an adequate limits to operation in an unsafe manner. FLOG RESPONSE: Change description DOC 2-07 been revised. For CPSES, the bracketed l t first sentence is a more restrictive change and has been relocated to DOC 2-55-M. For all FLOG plants, DOC 2-07 and LS-11 have been enhanced to indicate that when all MSIVs and MFIVs, as appropriate, are closed there is no need for the associated actuation instrumentation to be operable. The closure of the identified valves is sufficient to ensure the isolation function is complete. ATTACHED PAGES: Enci2 3/4 3-26 ) Enci 3A 15 and 19a ' Enci3B 11 and 16a i Enci 4 33 Enci5B B 3.3-87 Enci6A 7 l r

TABLE 3.3 2 (Continued) TABLE NOTATIONS ,

Trip function may be blocked in this MODE below the P-11 (Pressurizer 2-22 A Pressure Interlock) Setpoint. 2 50-LG
Trip function sutc;;tically blocked abovc P 11 and may be unblocked below P-11 by blocking the Safety Injection on low steam line pressure.
N Not applicable if each affected main steam isolation valve and its q associated upstream drain pot isolation valve per steam line is closed 83 a ( M iyated, d Het Used. Thc provision; cf Spccificatica 4.0.4 or; not ;pplicabic for 12-09 1A ;

entry into 2 : 3.

The channel which provides a steam generator water level control signal (if one of three specific trip channels is selected to provide input into 2 52 A ,

steam generator water level control) must be placed in the tripped 0 3.3 65 condition within 6 hours and maintained in the tripped condition with the exception that the channel may be taken out of the tripped condition for up to 4 hours to allow testing of redundant channels. Not applicable if Preferred Offsite Source Breaker is open. 32-11-A' cf I 8 Notiapplicable:when_ allimajnzfeedwaterfjsolationiand bypass]valyesj are closed and; deactivated;ordsolated by;a; closed _manualivalvej ?207-LS] ACTION STATEMENTS ACTION 12 - Deleted. ACTION 13 - Deleted. i i CPSES Markup of CTS 3N.3 3M 3-26 103088

l CHANGE j RUMBER EE DESCRIPTION j 2 04 LG The requirements stipulated in ACTIONS a and b are moved , to ITS Table 3.3.21, with explicit direction contained in the ITS ACTIONS Bases. 2 05 H l4;t ;pplicebic t; CPSES. Scc Convcision C ,; risen 0 2 05 T;bic (Erel;;urc OS).Mfunt21onal3dtjict Deetaj!ald F M 3se M ]ejSI3ff l Fag 2Ligu$D!t31We!!Le83ltteggggl3E5 Ri ! lammitesNs]!Lweassemis s!!apsst4caldtttym3he [gestagne!!!sinstemdenJsolantenggummutpellosinto inc}!Lde31udgg3Hggejt20fMadistell]fuellessemblies l witi!1alco!! tam 3and.3creTAlterationstrega_rdless of i MELE]. .

I I

2-06 LS 33 !?;t applic;bic te CPSES. Sec Conver; ion Ce-perison 0 2 25 T;ble (Encle:urc 30). FunctionaliUnjt ,41a;1) ofccurrent TS',TableI[3W2]Cuanualiinitiation ofindividuaEsteam linelisol ation aisinot:an~ ESEfunctlpnlandiitiis1therefore deletedf along Mthif ts,"ACTIONj Statement][21]ifrom;the ESFAS3SEconsjsteet:with NUREGG4311 rec 1;: 2 07 LS-11 hc (c) t; currcat TS Tobic 3.3-2 for the Stc;; Line Is;istien functi;nel " nit; 4.:.2, 4.b. 4.c. 4.d. :nd 4.c is revised t; :tetc th;t the LC0 requirc; cats ;r; not opplicable in ii0000 2 nd 3 den the "S!"; ;rc cic;" nd d;;;tivated.3/Tiote [(g)] is added to current TS Table [3.3 2] for the Feedwater Isolation and Turbine Trip Function [ Functional Units 5.a, 5.b] to state that l "0 2 07 the LC0 requirements are not applicable when the [FIVs and bypass valves] are closed [and daacHvatad ne isolated by a closed manual valve otheteforegthere;j_s po;need;for dassociatedIact .. onlinstrumentatlogitolbeloperable?" The:c]osure of;,Qeldentifjedyalves11s3uffigjentito

                                          'sureithe;1solatiorfifugetjoln is!ccuplete valves are ciosea [anu deadivatea            ated), they areor is3[. L'h already performing their safety function. These changes                      )

are consistent with NUREG 1431 Rev.1. 1 [New ACTION Statement 17.2 replaces ACTION Statement 17 in l 2 08 H ! current TS Table 3.3 2 Functional Unit 5.b. New shutdown requirements are added for Action 17 new Action 17.1 and !' new Action 17.2.] These ACTION Statements, written to reflect the Applicability of the affected channels and for consistency with ITS 3.3.2 [ Conditions D I and K] are i more restrictive, by one hour, than the current ACTION Statement [s] which invoke [ ] LC0 3.0.3 if the inoperable channel is not placed in trip within 6 hours. CPSES Description of Changes to CTS 3N.3 15 10BOM8

 -   -   a B      e-* Asesea-  4i--as -Q-      '--4--    -   4- -LW-A=34 5 n.---u* a,-   A n "4.n4+^ 1 -*-m3- 61.4144,-4A-w 4 e b- Tu,--*A2 *w*e-4+A9.u-  -~m -- nui-   *Ma-4A-+--&a c

i CHANGE NUMBER NSE DESCRIPTION 2152 6 Notel(elltopajgt3SJpblglJi22Lapplieditoithe;Turbigeilrjpland 0 3.3-65 EeeenterasolationInctiona]1 mitts Ebn1EstlecteditrcIIS2ab]e 1 3.;3;2il AnctientDtnitimEfootnote;(ptsthis; footnote; ors rewireG8teLaft!agMiagututo;D!Edeclared3RoperableEIheltondition fot.AnituperetHIR!M!EmiEgmE4Matedatu@nseltans;actionstare esm!GLNll3DN71bOEEth!n!!!!temighmwustulaes;are , espretamit:ts!BIRMIE!EngmM58lH153 Isle 5BDise!!aenistsymre IsaaBIERE8ERIRBM!I;li!!Iggngryasts!Emis]esim!gesjedM3n amma!sagt!!am! zW H ustausgemble:1gggEsirigee;moamannen3esperisangable (Ench!sWLeC3BU 215! H Notlapplicpblello;CP_SESESeehtsionicomparjs.onlTable (Enclosire 38)] c . f.55 N Note (c)1to; current 35:Jable;3;312;foritheLSteam; .Line;Isol ation 0247 i Eunctional; Units.1EaI2 E4;b;~41c F&d;[and ;4;eli syvj sed ;tols_ tate l thatitheil.C0;tepitements; ate;notlapplicable2LniMODES;2;and Awhen _the l MSIvslate31osedJnd ideactlyated;2His: change;1sinote; restrictive; ' in i l that;thelgiditionalltepitseentitoldeactivate;thelclosedjyalves;is l

                                           ;1sposed;21his;cha!geI1s_:cytsistent;withJUREG1143171ReVZ12 2156           LSi48 Notiapplicab]elt0CPSESHSeelConvers.iorCComparison; Table

! (Enclosugl38)] 2iSZ 6 Not Lapplicable;tolWidSeelConversion;CompactsonJable l (EnclosureT.38)J 215B 8 Not1 applicable;to'CPSES;ESeelConyersion;Comparj sonJable (Enclosurel3BM ! 3-01 A The requirements of this current TS [3.3.3.1] are moved to [three] separate specifications in the improved TS. The RCS Leakage Detection l requirements are moved to improved TS 3.4.15. [ ] The Control Room requirements are moved to improved TS 3.3.7. [The Containment Ventilation requirements are moved to improved TS 3.3.6.] 4 CPSES Description of Changes to CTS 3N.3 19a 1030/98 l l l

Page 11 cf 22 CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 APPLICABILITY TECH SPEC CHANGE COMANCHE WOLF CREEK CALLAWAY DIABLO NUMBER DESCRIPTION CANYON PEAK No - not in No - not in Yes Yes 2 02 CTS ACTION b.1. Equation 2.2-1 and the values for Total Allowance (TA), Z, and current TS. current TS. A Sensor Error (S) are deleted, consistent with NUREG-1431 Rev. 1. No - retained Yes Hoved to Yes - Hoved Yes - Hoved to 2 03 The Engineered Safety Features Actuation System Instrumentation Trip Setpoints Bases. to USAR. ITS 3.3.2 in ITS. LG are moved to a licensee controlled document. Bases. Yes Yes Yes Yes 2 04 The requirements stipulated in ACTIONS a and b are moved to ITS Table 3.3.2-1. LG with explicit direction contained in the ITS ACTIONS Bases. No ;cc No ::: Yes Yes 2-05 The Functional Unit for Containment 1[ptreget V entilation] Isolation CTS [3-e-CN 2 20 "..Yes CN 2 20 ^.Yes H Table 3.3 4 Functional _ttnit.2]. is moved to improved TS 3.3.6. Improved TS 3.3.6 [edds .cqafim..t: on thc 0." Cit"0!LI"! cf thc contsi m,. pur c l0205 radictica acnitor; :nd] extends the Applicability for the [";nu;l !nitiction and BOP-E5FAS Contairvient Ventilation Isolation] actuation logic to include during movement of irradiated fuel assemblies within containment [and Core Alterations; regardless of 19]DE]. No - retain No Scc CN 2 F; Scc CN Yes . 2-06 Functional Unit 4.a.1) of current TS Table [3.3-32] has been deleted. CTS. 25-A Yes 2-25-A- Yes. LS-33 Yes Yes Yes Yes 2 07 [Netc (c) is =cdificd for cu . cat TS I;bic 3.3 2 for thc Stc;; Linc Isci; tion LS 11 Tunction to tst; that thc LCO .;;uirements arc not applicabic in "0000 2 cnd 3

      & thc "SIW cre cle:-d ;nd dc;;tivatcT- note [(g6 is aded 6 wii cia TS                                                      -                                        , l0-2-0,   l and Turbine Trip Function to state Table [3.3 2] for the feedwater Isola that the LCO requirements are not applicable when the [FIVs] are closed and deactivated [or isolated].

Yes Yes Yes Yes 2-08 [New Shutdown requirements are added for ACTION 17, new ACTION 17.1 and new M ACTION 17.2] These ACTION Statements, written to reflect the Applicability of the affected channels, are more restrictive, by one hour, than the current ACTION Statement [] which invoke [s] LCO 3.0.3 if the inoperable channel is not placed in trip within 6 hours. Yes - Hoved to Yes - Hoved to Yes - Hoved Yes - Hoved to 2-09 Separate ESFAS entries for the motor-driven and turbine-driven auxiliary to Bases. Bases. Bases. Bases. LG feedwater pumps are no longer necessary. The only difference in the requirements (an SR 4.0.4 exception for response time testing of the turbine-driven auxiliary feedwater pump) has been addressed in the ITS by a Note in Surveillance Requirement 3.3.2.10. [] 10/30/98 CPSES Conversion Cornparison Table - CTS 3N.3

Page 16a cf 22 CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 TECH SPEC CHANGE APPLICABILITY DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK No NO No Yes 2:53 In this Callaway-specific changefxthe;t1e. breaker _ closure ld1scussionJn. ACTION;19 LG of CTS Table 3.3-3 is moved to.the BasesforcITSi3.5.5 Condition'B;asione exanple of. multiple. channels inoperable;on one, bus ~ n . Deletion,0f ACTION b.14 eliminates.one p,ossible.recoursefors an Allowable;Value not Noy Not in_ CTS No2 Not;in Yes Yes

 ; 54 set.4                                                                                                                                                                                                                                                   Q H

4.a.2.,4.b.3.Cu4.d.Eand Aelis;revis'ed toistate_that1the LCO requirements'";are

                                                                                                                                                                                                                                                                                        ~
                                                                                                                                                                                                                                                                                           ^/        0-2 Oi

('H not applicable 1 1n.H00ES12 sand;3 whenithe,HSIVslaretclosediandl deactivated: Yes No No No 2 56 DCPP; CTS ACTION. Statement 35;is; revised sto require;NODEi2_ entry;and1toidelete the LS.48 requirement.to. enter LCD 3.0.3 whichfequires;the unit.to;be placedi1n H0DE;3:as a minimusi NomHott in Yes Yes 2-57 Current t TS .! Table; 3.3-3 tFunctional:Unitt3.c;2)dContainmentgPurgc1 Isolation No n Not.in CTS A Automatic; Actuation,Logicsand : Actuation; Relays 3 (SSPS) d andifunctional 2 Unit9t .b; CTS Control;P.comilsolation1 Autonetic Actuation Logic;and: Actuation.Re}ays;(SSPS) Rand associated surveillante' requirements;are deletedi

No No Yes No 2-58 WCGS Amendment:No ?117; dated Nay;28 a199Br;added:ainew Action;. Statement;to. CTS A 3/4,3.2.1Tabl_e 3.3-3.; Functional; Unit;7.b.,: Refueling Water; Storage;TanKlevel (RWST);-_ Low-Low Coincident with Safety . In.1ection. Yes Yes Yes Yes 3-01 The requirements of this specification [ CTS 3.3.3.1] are moved to [three] A separate specifications in the improved TS. The RCS Leakage Detection requirements are moved to improved TS 3.4.15. [ ] The Control Room requirements are moved to improved TS 3.3.7. [The Containment Ventilation requirements are moved to improved TS 3.3.6.] Yes Yes Yes Yes 3 02 The requirements stipulated in ACTION [a] are moved to ITS Tables [3.3.6-1 and M 3.3.7-1]. with explicit direction contained in the ITS ACTIONS Bases. The 4 hour A0T for setpoint adjustment is eliminated. CPSES Conversion Comparison Table - CTS 3N.3 1030/93

I IV. SPECIFlC NO SlGN!FICANT HAZARDS CONSIDERATIONS 1 NSHC LS-11 ; l 10 CFR 50.92 EVALUATION : FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS [Notc (c) to current TS Tobic 3.3 3 for the Stc;; Linc Isolation functional Units l 0 2 07 4.0.2. 4.b. 4.c. 4.d. and 4.0 is revised t: ; tate that the LC0 requirenent; cre not applicabic in "00ES 2 nd 3 J.cn the "SI"s arc cicscd and dc;ctivated.1 Note L(g)] 1s added to current TS Table L4.J-ej iur we reeawater isola; ion and Turbine Trip Function to state that the LCO requirements are not applicable when the [FIVs and associated bypass valves] are closed [and deactivated or isolated by a closed manual valve]. When these valves are closed [and deactivated or isolated]p'cy arc a;rcedy l r.....,..~,, ,-.m., . ~.. . u=gsojesmy=-ljerugn , f==.7BTherefort? l . _35iHOJieed_for;ge;associa.$aQctuation1nstrumentat. ion;toibe,; operable; The proposed TS change has been evaluated and it has been determined that it involves no l significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

                      "The Commission may make a final determination, pursuant to the procedures in                              '

50.91, that a proposed amendment to an operating license for.a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed ; amendment would not: l I 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or l

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or i 3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

1. Does the change involve a significant increase in the probability or

[ consequences of an accident previously evaluated? l

Overall protection system performance will remain within the bounds of the o.2-07 I^

previously performed accident analyses since no hardware changes are , proposed. The proposed change adds a relaxation to the Applicability associated with [ ] Feedwater Isolation ESFAS functions. Those@lation functions are accomplished when the associated valves are closeo Lond ueactivated mlatedl. whether that closure is as a result of automatic isolation rator action. Operability requirements on c' r"by actuat instrumentatjon. Qrcuitryjnstrumentat, are not applicable if the valves are closed l

[and deactivatea or u,oiateoj. ine proposed change will not affect any of the analysis assumptions for any of accidents previously j

CPSES No Significant Ha:ards Consideration - CTS 3AI.3 33 10B0/98

ESFAS Instrumentation l B 3.3.2 BASES and cause a cooldown of the primary system. The Steam Line Isolation Function is required in MODES 2 and 3 unless all MSIVs and,thejr; associated; upstream", drip; pot o.3,3.s.1 isolationTealves are closed!andidanctivated .nthjs d?EE1%L www mus 942-;_. /IOQ5 Q 2 07 thgg$g gi g M instmungstation M s" Mrtle . n Muuts 4, 5. ano 6. tnere is insufficient energy in the RCS and SGs to experience an SLB or other accident releasing significant quantities of energy.

c. Steam Line Isolation-Containment Pressure-Hiah 2 This Function actuates closure of the HSIVs in the event of a LOCA or an SLB inside containment to maintain at least one unfaulted SG as a heat sink for the reactor, and to limit the mass and energy release to containment. The transmitters (d/p cells) are located outside containment ,

with the sensing line (high pressure side of the transmitter) located inside containment. Containment Pressure-High 2 provides no input to any control functions. Thus, three OPERABLE channels are sufficient to satisfy protective requirements with two out-of three logic. llcua r. for enhanced reliability, this Function was dcsi;incd with four channels and a two cut of-four legfe- The transmitters and electronics are located outside of containment. Thus, they will not experience any adverse environmental conditions, and the Trip Setpoint reflects only steady state instrument uncertainties. Containment Pressure-High 2 must be OPERABLE in MODES 1,

2. and 3, when there is sufficient energy in the primary and secondary side to pressurize the l containment following a pipe break. This would cause a significant increase in the containment pressure, thus allowing detection and closure of the MSIVs. The Steam i

Line Isolation Function remains OPERABLE in MODES 2 and 3 unless all MSIVs are closed and; deactivated. In o.3.3-a.1 MODE;4;the;jncreaselinicontajnsent pressurelfo] lowing:a Ripe . break 1wou]d 'occutLovet:altelatively;1ongitime Petiod?Auch3 hat _nanuallaction;c@ldjreasonably belexpected to1 provide:ptotection:andESFAS3FunctionfXc~need;notbe OPERABLE." sin MODES b 57 and 6, there is not enough energy in the primary and secondary sides to pressurize the containment to the Containment Pressure-High 2 setpoint. (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-87 10/3088

CHANGE NUMBER JUSTIFICATION 3.3 63 This change revises ITS Table 3.3.21 [ Note (g)] per current TS Table [3.3-2] Note [b]. This revision is a clarification to the operator that describes the circumstances under which the [Steamline Pressure Negative Rate High function may be blocked when below the] P 11 permissive. 3.3 64 This change revises ITS Table 3.3.21 Note (j) to exclude the MFRVs, consistent with current TS [ 3.7.1.6]. [The note defining the applicability is also revised to add an alternate method of main feedwater isolation, if available. The use of close manual valves serves the same safet f losed and hae+hatad valve.] ,

                          .. .        . ..              -           .-.kW M a-WNsCafgBM',"dtheJestyslaantatsmavagistredito initiateJhelgjpggLM3thes11erveQOSPMetlandatterefore d s                                              :
                                                                                                                  ~

Tree 81ted31olksestabM 3.3 65 A note is added to the steam generator water level high high trip function to reflect the CPSES design and current TS. In the CPSES design, only three channels of the four steam generator water level signals provide input to this trip function. Therefore, in order to satisfy the single failure criterion, if one of these three channels is used as input , to the Steam Generator Water Level Control System, its associated bistable must be placed in the tripped state. Iq1 M R S Z thjs requiteserisitsplemented throughifootnote3pttGable13;22n a 3.3 es . 41ch;tegoire.s2$he3ff_ected;chamento;beldeetated11mpetable:r5The l ectiesigecifist!1ER*41 timid!ou11thenylugen!dELhis Presentatjs:fEeMitalegt;toltheMuMEteAR1Legents;

3.3 66 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).

3.3 67 This change adds, in PAMS, CPSES specific operability requirements and 1 Required Actions for the T hot and T cold indications consistent with both the current licensing basis and the intent of NUREG 1431. If a T hot indication is unavailable, equivalent information is available from the l i Core Exit Temperature indication which is also a RG 1.97 variable. Similarly, if a T cold indication is unavailable, equivalent information may be derived through the use of the steam generator pressure and steam tables, because the RCS cold leg temperature closely follows the steam generator saturation temperature. The modification to ITS Condition C represents the best conversion of the current TS to the generic ITS that is consistent with the plant design. 3.3 68 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3,3 69 Not used. 7 10BOR8 CPSES1Nfferencesfrom NUREG-1431 -ITS3.3 i l

l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: O 2-11 APPLICABILITY: CP, WC REQUEST: The Functional Unit for Loss of Power [ CTS 8.a. 8.b] is moved to improved TS 3.3.5. Comment: {CP} The CTS LOP instrument titles were dropped in the ITS and this change was neither identified nor evaluated. Show that CTS requirements are not changed as a result of using new LOP Function terminology in ITS SR 3.3.5.3 {WC} T3.3-4 (F8.a. 8.b) trip setpoints are incorrectly deleted in the CTS markup and the inequalities are deleted in the ITS. The CTS applicability is expanded to adopt the iSTS. This change is neither marked-up or evaluated in the CTS. Provide revised CTS and ITS. FLOG RESPONSE: For CPSES, DOC 2-11-A remains correct. The function titles have been corrected in the ITS (see the response to Comment Number O 3.3-131). For WCGS, Functional Units 8.a. and 8.b., trip setpoints were incorrectly deleted in the CTS

   . markup. The CTS markup has been modified to show the setpoints as retained. ITS SR 3.3.5.3 has been modified to reflect the inequalities and the Bases modified to indicate that the l   inequality sign only indicates a conservative direction. The as-left value will be within a two-sided calibration tolerance band on either side of the nominal value. This is consistent with the adoption of licensee identified item CA 3.3-014 on RTS and ESFAS.

ATTACHED PAGES: None 1 4

i ADDITIONAL INFORMATION COVER SHEET , I ADDITIONAL INFORMATION NO: O 2-12 APPLICABILITY: CP, WC, CA REQUEST: This Functional Unit [ CTS 9.a-9.d] is moved to improved TS 3.3.7. The Applicable MODES have been expanded to include movement of irradiated fuel assemblies to cover fuel handling accidents. Comment: Previous CTS changes resulting in requirements moved to other specs in the ITS format the change is noted as administrative. What is different about this change that it is more restrictive? FLOG RESPONSE: As stated in DOC 2-12-M, the APPLICABLE MODES are extended from MODES 1-6 to MODES 1-6 and during the movement of irradiated fuel. In accordance with the CTS applicability, movement of irradiated fuel when the core was off-loaded (i.e, not in any defined MODE), would not be covered by this specification. Because the additional applicabilit", beyond that required by CTS, is being adopted, this change is considered to be more restrictive. ATTACHED PAGES: Enci 3A 16 l l l I l 1 l 1 1 l l l l l

l l CHANGE ! Nl#6ER HSBC DESCRIPTION y 2 11 A The Functional Unit for Loss of Power [ CTS Functional Unit 8] is moved to improved TS 3.3.5. 2-12 M This Functional Unit [ CTS Functional Unit 9, Control Room Emergency Circulation] is moved to improved TS 3.3,7. Consistent with NUREG 1431 Rev.1, the Applicable MODES ! j have been expanded to include movement of irradiated final me. 14*e +n eau fnal handlina accidents. _ g.2-12 l-M l 2 13 A This Functional Unit [ CTS Functional Unit 11. Solid State Safeguards Sequencer] is moved to ITS 3.8.1. l 2 14 M This change modifies ACTION Statement [18] for permissive P-11 [ ] to provide specific shutdown requirements to exit Applicability in lieu of applying LCO 3.0.3. This change l 1s more restrictive by one hour, consistent with NUREG-1431 Rev.1. , 1 2 15 M Action Statement [14] has been expanded to specify !' additional actions and options if an inoperable channel is ; not placed in bypass within the specified time period. In ; the current TS, this would have required an entry into 1 I l LCO 3.0.3, which would necessitate that the plant initiate a shutdown within 1 hour and be in the next mode in 6 hours. In the ITS, the requirements to place the inoperable channel in bypass within a time constraint and the reduction, by 1 hour, in the time to exit Applicability are more restrictive than the current TS. 0-2 15 [ ] ItCMM$$iCfMENMAri W 3s

                                                         " M J 6 2 ] S r k,o " e               . . - - . k_3 ensqulggline;1ganggMagilBREmulRGREefathe climEBB]lE9fs.3BtlGEWREllBl0lRBIBMOutet ofEclmmREntmir06 ffjcient3G888M131EMted Plot!BCtDDCt19ffel@e[tflGig]A]gDNEIDmsidettd Cygatgl_gQfig!C3tpteTofitN0ggtI4DgpegblgbanneEl segategocifictiMMGOQ8081aM3nelTSJ1tttis c!iagge3Olp!tsideredJ$d;bgMlR$1dCtM]

l l CPSES Description of Changes to CTS 3N.3 16 1080M8 , l

_ - . . A

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-13 APPLICABILITY: CP REQUEST: This Functional Unit [ CTS 10] is moved to ITS 3.8.1. Comment: {CP} The CTS markup is deficient. Actions 25 and 26 which apply to the SSSS are not included in the Rev 0. Provide the appropriate pages and justifications to complete the package. Justify each proposed change to the CTS. {CP} Actuation instrumentation testing is proposed for ITS Section 3.8.1. This is contrary to iSTS format which includes sequencer operability with DG operability in Section 3.8.1, but sequencer testing is limited to functional tests associated with LOCA/ LOP testing. Revise the ITS to adopt the iSTS format and bring sequencer instrument loop testing back into the instrumentation tech specs if LOP and LOCA testing is not otherwise sufficient to demonstrate operability. Justify each proposed change to the CTS. Note that CTS require channel calibration at refueling and TADOT at 62d staggered testing. FLOG RESPONSE: Item (1). The formal transmittal page of CTS 3/4.3-30 was incomplete. The complete page will be included. item (2). The CTS Table 4.3-2, Functional Unit 11a. and 11b Channel Calibration, performed ! with a refueling frequency, is captured within the requirements of ITS SR 3.8.1.18. The required TADOT, with its qualifying notes, is currently performed with a monthly frequency. This TADOT, and its qualifying notes, will be moved to the newly created ITS SR 3.8.21. These changes are administrative in that, consistent with the iSTS format as described in the Comment, all sequencer requirements are retained, but are associated with DG operability and, hence, are moved to the specifications associated with the DG. The ITS markup of SR 3.8.21 will be revised to reflect this philosophy. ATTACHED PAGES: Attachment 14 - ITS 3.8 - Electrical power Systems EnctSA 3.8-15 Enci 58 B 3.8-31 Enci 6A 5 Encl 6B 6 i 1

I l l l I AC Sources-Operating 3.8.1 I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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g_u~.~ . en _.w.m.vuv~w _ a_ _m _ _ ~r.vwr~w _ _ _ . ._ .w..~u ._ -m _ , u_ _m_w sm~.m~-s L _ - ~ ~ . a _ a_ _m a __. - a,L1 _ _e._. 2 _ _ _..__--- -. m - w _-n u m m - .u m ~ m w 58%8X21NPUetMithe: Solid statFMiegua000SeqQetWid (bothithe;5afetydnjection3SequencetJand3he314ptookJ540epce'rj arutixMperfwpanceMETptHcnitsmyt!11ence ta petfMmedMerriSEdaya; Thi s1SRJ sigodified)yMRtesWiTheWgstDtpi4@$ts vetificationataeggoints.;fros;thamptE25ht.22L*1taojnts;ars yerifiedipy;assertiot%the1ESFNnstgeentaticGIMyggpedActe excludes;actuatjoof.11pandecces?3peration:ofshe" sequencer dur.ing powerloperationtcouldidistuptisreaEgpgratiegndJgtuce a; plant;tragslent) REFERENCES 1. 10 CFR 50, Appendix A, GDC 17.

2. FSAR, Chapter 8. ,

1

3. SafetyLGuide;9EMarch30.21971 (lat,eritenamed Regulatory Guide 1.9).

4. FSAR, Chapter 6.

5. FSAR, Chapter 15.

(continued) CPSESMark-up ofNUREG-1431 Bases -ITS 3.8 B 3.8-31 10B088

CHANGE NUMBER JUSTIFICATION (enclosure 6B). 3.8 33 NUREG-1431 LC0 3.8.3 Condition B. and SR 3.8.3.2 would be revised to note use of a dipstick level for verification of lube oil inventory consistent with the Comanche Peak CTS. The Lube Oil Level at CPSES is measured by a Lube Oil Dipstick and not by gallons of oil. Specific limits are outlined in the Bases. The current CPSES Technical Specification does not require measurement of Lube Oil Level. 3.8 34 The frequency of SR 3.8.4.1 and SR 3.8.6.1 would be changed from i 7 days to 31 days in accordance with the recommended frequency of !

                          " at least monthly" identified in IEEE 450 1995. This change is consistent with TSTF-115.

3.8 35 Not applicable to CPSES. See conversion comparison table (enclosure 6B). j 3.8 36 Adds note, per current TS, that allows one SI sequencer channel I to be bypassed for up to 4 hours for surveillance testing l provided the other channel is operable.

                                                                                                             -                   l 3.3 37              The [scqucacer survci11cacc icquirc;;. cats] fre;;; caricr.t T" Section                               l 3/4.3 would bc cddcd to thc ITS. This is consistcat with NUPIC 1431. P,cv. I w'.ich cdds cn LOO requircrcat for the                                                  j
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capture;thelsontt0yJWreqd1:3d;101tuppigGPEBRII)JX of;theisplid s_tateJafeguaMsm=rpsmhitewreenkmce3#as telocatedJfrom ESf.HablGK2 Euj$10!$131Dit,31Cisujd31bf1] l The3 ccompanM pg M te_sithatideflgelt4!elscop Eoffthels M elllance i atelalso.Mcluded; e 3.8 38 ITS SR 3.8.4.7 Note 1 would be revised to allow the modified , performance discharge test in ITS SR 3.8.4.8 to be performed in lieu of the service test in ITS SR 3.8.4.7 at any time. This is consistent with IEEE 450 and current licensing basis. IEEE-450 l states, "A modified performance test can be used in lieu of a ! service test at any time." The modified performance test is a test that envelopes the service test with respect to the l discharge current being greater than or equal to the service test, and the amp hours removed is larger. This change is consistent with TSTF-115. \

3.8 39 ITS SR 3.8.4.6 would be revised for current licensing basis. The restriction to not perform this SR in H0DE 1. 2. 3. or 4 would be deleted. The battery charger test is not required to be performed during shutdown since the backup chargers could be in service, maintaining the DC subsystem operable during performance of this SR.

CPSES NUREG-1431 Differences -ITS 3.8 5 1030/98

6 o/7 CONVERSION COMPARISON TABLE - ITS SECTION 3.8 Diablo Canyon Comanche Peak Wolf Creek Callaway NLM3ER DESCRIPTION Yes No. Affected No. Affected No. Affected 3.8-35 The actions of 115 3.8.2. ITS 3.8.5. ITS 3.8.8. and. specifications are specifications are ITS 3.8.10 would be changed to add a note stating that specifications are not applicable for not applicable for not applicable for ITS LCO 3.0.3 is not applicable. This is consistent fuel movement. fuel movement. fuel movement. with Industry Traveler TSTF-36. Yes No No No 3.8-36 A note would be added in accordance with the CTS for CPSES that allows one 51 sequencer channel to be bypassed for up to 4 hours for surveillance testing provided the n N r ^ --1 h ooerable.

                                  /                                                                                                                                                                     Yes                Yes No: not in CTS  Yes 3.8 31          Mc ;5cquc.ccr 5":;) frc ; cu . c..; TS 3/".3 .;culd bc cddcd to thc ITS. SRi 3,8;1-21Listadded to;captureithq                                                                                                                                                 0-2-13(3 3) l monthly,TADOT;requireditoisupportLOPERAlHLIITiottM                                                                                                                                                 ~

Solid StateJSafeguards15equencersMThis;sotveillance l 7 wastrelocat.ed ; free .ESEilable_4;322RfunctLionaliUnit laaand 11bMThe; 3 accompanying.:potesithatJieff.neitM J the surveillancelbreialsatincludedi Yes Yes Yes 3.8 38 ITS SR 3X - _ _ . .~m u u= m i m - _._7 ' Yes modified performance discharge test in SR 3.8.4.8 to be performed in lieu of the service test in SR 3.8.4.7 at any time. Yes Yes Yes 3.8-39 ITS SR 3.8.4.6 would be revised for current licensing Yes basis. The restriction to not perform this SR in mode

1. 2. 3. or 4 would be deleted.

Yes No No No 3.8-40 ITS SR 3.8.1.7. SR 3.8.1.15 and SR 3.8.1.20 would be revised per DCPP CTS to add a requirement to verify DG achieves proper speed within 10 seconds after start signal. Yes Yes Yes Yes 3.8 41 The phrase. *that could degrade battery performance." would be added to clarify the purpose of the battery inspection. This change is consistent with industry Traveler TSTF-38. An Action is added to the LCO for an inoperable No, not in CTS No, not in CTS Yes Yes 3.8-42 autaamatic load sequencer to immediately declare the affected DG and offsite circuit inoperable. CPSES Conversion Comparison Table -ITS3.8 10/3M8

1 l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-15 APPLICABILITY: DC, CP, WC, CA l REQUEST: Action Statement [16] has been expanded to specify additional actions and options if an inoperable channel is not placed in bypass within the specified time period. In the ITS, the requirements to place the inoperable channel in bypass within a time constraint and the l ! reduction, by 1 hour, in the time to exit Applicability are more restrictive than the current TS. [] l Comment: The completion time for bypass of an inoperable containment high-high ! pressure signal (Functions 2.c and 3.b.3 - Action 17 and Function 4.c - Action 17.1) is I enanges from unspecified (immediate) to within 6 hours. Justification is not provided for the new completion time. This also appears to be a less restrictive, not a more l restrictive change. l The completion time for bypass of an inoperable channel in action 16 is changed from unspecified (immediate?) to 6 hours. Justification is not provided for the new time. This also appears to be a less restrictive, not a more restrictive change. FLCG RESPONSE: In practice, because a time for completion of an action is not specified, no f rigorous completion time is applied; the action is completed in an unspecified," reasonable" time frame. For the functions where a completion time is not specified, the operability of the channel has no safety significance. The required number of channels remain sufficient to initiate the required protective action, even if a single failure is considered, regardless of the state of the l one inoperable channel. Because a specific time would be required by the ITS, this change is considered to be more restrictive. DOC 2-15-M will be enhanced to reflect this discussion. ATTACHED PAGES: i Enci 3A. 16 i l t

CHANGE NUMBER HSBC DESCRIPTION 2 11 A The Functional Unit for Loss of Power [ CTS Functional Unit 8] is moved to improved TS 3.3.5. 2 12 M This Functional Unit [ CTS Functional Unit 9, Control Room Emergency Circulation] is moved to improved TS 3.3.7. Consistent with NUREG 1431 Rev.1, the Applicable MODES have been expanded to include movement of irradiated ; fuel assemblies to cover fuel handling accidents. o.2 12

. . oy g q ; , 37 j (i .: .. r :-l ' . . . ' 3%

C09803mingRg!gmelygt!@gje; 2 13 A This Functional Unit [ CTS Functional Unit 11. Solid State Safeguards Sequencer) is moved to ITS 3.8.1. 2 14 M This change modifies ACTION Statement [18] for permissive P 11 [ ] to provide specific shutdown requirements to exit Applicability in lieu of applying LC0 3.0.3. This change is more restrictive by one hour, consistent with NUREG-1431 Rev.1. 2 15 M Action Statement [14] has been expanded to specify additional actions and options if an inoperable channel is not placed in bypass within the specified time period. In the current TS, this would have required an entry into LC0 3.0.3, which would necessitate that the plant initiate a shutdown within 1 hour and be in the next mode in 6 hours. In the ITS, the requirements to place the inoperable channel in bypass within a time constraint and the reduction, by 1 hour, in the time to exit Appl- more restrictive than um - nt TS. 8.lGERC%.TC$ h E ttag,ilgtjgp 3] R jpg3tL _ 1[ ema w aww unusesw g asemmatanR2mamanuelesmLuulenspecernmu g,

                                       "tMamEICRMR2talRHotabGWC83BDWillERI co!ERBSRC83GEIRDUKtD!Mht3RR3!Bl%DtI3tte chansbaEIKadmLsingingencejangGaminumisbet oGalmaR520stin;soffic1,ntItagitJtgGbtitWited PtoNClifDictieZ9M1f2OJno1OlL11RG#1cantideted; tentdlns]IfitbGtateXthenEinmerabtentan12 BecangreMcJfr&1melwuld3NEgiquend;pEthelusmthis chan c isica!nidered;to'be:more;restr.ictive; CPSES Description of Changes to CTS 3M.3                                        16                                                                  108 0/98 L

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-16 APPLICABILITY: CP, WC, CA, DC REQUEST: ACTION Statement [26] for an inoperable channel in the current TS Table [3.3-3] Functional Unit [9.a-9.c] is modified to be consistent with NUREG-1431, Rev.1 (7 day AOT in ITS 3.3.7). Comment: Insufficient information is provided to justify extending the allowed outage time for one CRVS channelinoperable from {1 hour][48 hours] to 7 days. If the system arrangement is such that each instrument channel is dedicated to a single CRVS train (one-out-of -one starts one train), then the effect of a single inoperable instrument channel is similar to that of an inoperable mechanical train and the extended AOT may be acceptable. If, however, the two channels are used in a one-out -of-two logic start both CRVS channels, a single inoperable instrumentation channel degrades the operability of both mechanical trains and the justification provided for the 7 day AOT is not germane. {WC} CTS Action 26 provisions of 3.0.4 not applicable are deleted without evaluation. Provide a justification for this change. FLOG RESPONSE: The premise behind the NRC comment is that the 7-day AOT is acceptable for a design where the cross-train feed aspect is not present. The FLOG plants disagree since this design feature increases isolation function availability. Given one inoperable radiation monitor channel for a design without a cross-train feed, the associated isolation logic train is inoperable. Given one inoperable radiation monitor channel for the FLOG design with a l cross-train feed, both isolation logic trains remain functional since the OPERABLE radiation monitor channel will provide inputs to both isolation logic trains. However, the isolation logic l train powered by the same train as the inoperable radiation monitor channel will be declared inoperable. The isolation logic train powered by the same train as the OPERABLE radiation monitor channel will remain OPERABLE, meeting the same safety system status as provided l by a design without a cross-train feed. Since the FLOG design is superior to a design without a cross-train feed, the 7-day AOT is justified. PLANT-SPECIFIC DISCUSSION The Control Room Ventilation Isolation design is depicted on FSAR Figure 7.2-1 Sheet 8. Two l radiation monitors are associated with the North intake, one train A and the other Train B. Two radiation monitors are also associated with the South intake, one train A and the other Train B. l I Each of the four monitors will, upon detection of high radiation, provide signals to both trains of l Control Room Emergency Recirculation actuation. Cross train tripping is accomplished via l qualified isolation devices. ATTACHED PAGES: None

              - - _ .        -.       .         ..~         . - .       _ _ . . _ . - - - - - . , -  .-. . .- .

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-17 APPLICABILITY: CP REQUEST: The monthly TADOT has been extended to quarterly. Comment: Insufficient justification to evaluate the change. Retain CTS or provide instrumentation reliability data for staff evaluation. FLOG RESPONSE: This proposed change will be withdrawn and CTS will be retained. For CPSES, the surveillance test performed for this function is the same as that performed to support operability of the safeguards sequencers (ITS SR 3.8.1.21). Because of the lack of a significant burden imposed by the monthly performance of this surveillance, the frequency extension will not be pursued at this time. ATTACHED PAGES: Enct 2 3/4 3-43 Enci 3A 16a Enci3B 12 l End 4 1,37 and 38 EnctSA 3.3-32 i Enci5B B 3.3-119 l l i 1 t

TABLE 4.3-2 EgilliEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENT /. TION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING- MODES ;1443 CHANNEL DEVICE MASTER SLAVE FOR Mi!Cli CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVE4L+ANGE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS-REQUIRED

6. Auxiliary Feedwater

a. Automatic N.A. N.A. N.A. N.A. M(1) M(1) Q 1. 2. 3 Actuation Logic and Actuation Relays

b. Steam Generator S R Q N.A. N.A. N.A. N.A. 1. 2. 3 Water Level--

Low Low l

c. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

d. Loss of-Offsite N.A. N.A. N.A. N.A. 1, 2.

h'(3.4) I N.A. R 3 - o.2-17 Power

e. Trip of All siain N.A. N.A. N.A. R N.A. N.A. N.A. h-2 Feedwater Pumps

7. Automatic Initiation of ECCS Switchover to Containment Sump

a. Automatic N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2. 3. 4 Actuation Logic and Actuation Relays

b. RWST Level-- S SR Q N.A. N.A. N.A. N.A. 1. 2. 3. 4 i Low-Low Coincident With Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

CPSES Markup ofCTS 3N.3 3M 3-43 1020M8

CHANGE NUMBER N21C DESCRIPTION 2 16 LS 12 ACTION Statement [24] for an inoperable channel in the current TS Table [3.3 2] Functional Unit [9] is modified to be consistent with NUREG-1431 Rev.1 (i.e., a 7 day A0T in ITS 3.3.7). w 2 17 E:543 The scathly TA00T has bc;n cxtcnded to quarterly. 0-2-17 consistcat .;ith NUREC-1431 Rcv. 1. Ilotiused 2 18 LS 31 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2-19 LG This chang; ;;vc; function; providcd by : Safcty 0-2 19 Injcction signal nd the A".! pump ; tort entrics [ ] for functional Units [5.c. 5.d. and 5.c] in currcat TS Tobic [3.3 2 and 3.3 3] to th; ITS 3.2.2 Bests, consistent w+th NUREC 1431 Rcv.1. The: text _in: Functional Units'[1; 61cl~6]d,Eand16.e];oficurrentiTS" Jab]e;[3.3-2:and:3~.3 3], de.scribingLthe;ESFAS; functions providedibyla Safe.ty InjectionIsigna];andithe;AFW: pump;startlentrjes;[j]l are mored;to the: m APPLICABLE; SAFETY;ANALYSESRC0 ZAND APPLICABILIIESect1@EoltheJTS;3;3XBasesEThe]istlof functions 2 initiated by;a_ Safety 3njection3jona);and;the par,ticul ar;AFW;pumptsEstartedi1Mo]ve3] arifying information:for;t.he;tetained; Functional 31nitstthe limitattons3ndlestrletions~~of;thelcurrentjTSJre unchangedMfunctionallunits;are;tetaLned;1[the1ITS whi]eit.helde.scrj ptive;materialli s ~ movedito"the: Bases'. CPSES Description of Changes to CTS 3N.3 16a 10BOR8

Page 12 of 22 CONVERSION CONPARISON TABLE - CURRENT TS 3/4.3 APPLICABILITY

                                                                                -TECH SPEC CHANGE DIABLO            COMANCHE         WOLF CREEK                                        CALLAWAY NUEER         DESCRIPTION CANYON            PEAK No - not in       Yes              Yes                                               Yes                  ,

2 10 New KTION Statement [23f] is added to current TS Table [3.3-3] for one inoperable Main Feedwater Pump trip - AFW start channel. This is a more current TS. M restrictive change since it reduces by 1 hour the Completion Time to reach MODE 3 as compared with entry into LCO 3.0.3. Yes Yes Yes Yes 2-11 The Functional Unit for Loss of Power [ CTS 8] is moved to improved TS 3.3.5. A No - not in Yes Yes Yes , 2-12 This functional Unit [ CTS 9] is moved to improved TS 3.3.7. The Applicable ; NODES have been expanded to include movement of irradiated fuel assemblies to current TS. M cover fuel handling accidents. No - not in Yes Yes Yes 2-13 This Functional Unit [ CTS 11] is moved to ITS 3.8.1. wrret E. A Yes Yes Yes Yes 2-14 This change modifies ETION Statement [18] for permissive P-11 [] to provide M specific shutdown requirements to exit Applicability, in lieu of applying LCO 3.0.3. This change is more restrictive by one hour. Yes Yes Yes Yes 2 15 Action Statement [14] has been expanded to specify additional actions and M options if an inoperable channel is not placed in bypass within the specified time period. In the ITS. the requirements to place the inoperable channel in bypass within a time constraint and the reduction, by 1 hour, in the time to exit Applicability are more restrictive than the current TS. [ ] No - not in Yes Yes Yes 2-16 ETION Statement [24] for an inoperable channel in the current TS Table [3.3-2] Functional Unit [9] is modified to be consistent with NUREG-1431 Rev. 1 (7 day current TS. LS-12 ~ A0T in ITS 3.3.7).

                                                                                                                                                                                                                                                                                                             \
                                                                                                                                                                                                        ";                Ves,NA          #;                                                Ne-      g Q-2-I P E 2-17               TM -.-Sly TET M- kc. c;t..M to ,.rtcly. ";;tiused                                                                                                                                      gty _                           ctg .cd m.....      ...m                  -.. ... ...                                       Pete+n bd NA                                                ed A                                                                                                                                                                                                                                                                                    curren N                                                       J i

No - see CN No - see CN Yes Yes 2-18 Current TS Table 3.3-3 ETION Statement 19 is revised to reflect ITS 3.3.5 for the Loss of Power Functional Unit. 2 48 LS-28. 2-32-LS-23. LS 31 Yes Yes Yes Yes 2-19 This change moves functions provided by a Safety Injection signal and the AFW LG pump start entries [] for Functional Units [6.c. 6.d. and 6.e] in current TS Table [3.3-2 and 3.3-3] to the ITS 3.3.2 Bases. CPSES Comersion Comparison Table - CTS 3N.3 10B &98

I 1

NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC)

CONTENTS 9 I. Orga ni z ati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. Description of NSHC Eval uations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 III. Generic No Significant Hazards Considerations f "A" - Administrative Changes............................................. 6 "R" - Relocated Technical Speci fications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 "LG" - Less Restrictive (Moving Infornation Out of the Technical Speci fi cations) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 "H" - More Restri ctive Requi rements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 IV. Specific No Significant Hazards Considerations "LS" LS - 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot Appl i c abl e LS-2.................................................................... 16 18 LS 3.................................................................... LS - 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i c abl e LS 5.... ............................................................... 21 24 LS 6.................................................................... 26 LS 7.................................................................... LS - S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i cabl e 29 LS.9....................................................................

31 LS-10...................................................................

33 LS 11................................................................... LS 12..............................................................__ .. 35 LS - 13 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . @Jsed 39 , LS 14................................................................... 41 LS 15................................................................... LS - 16 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . No t a ppl i cabl e 43 LS.17................................................................... LS 18. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not appl i cabl e LS-19...................................................................45 LS 20 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot U s ed 47 LS-21................................................................... 49 LS 22................................................................... 51 LS.23................................................................... 54 l LS 24................................................................... LS 25............................................................. Not Used LS - 26 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Used .". . . l. "o."7 . . . 561," 58 LS 27................................................................... LS . 28 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e LS 29. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not appl i cabl e CPSES No Significant Ha:ards Consideration - TS 3N.3 1 l

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_..__A TL___ __ - wywsab. a : twa 4 vuaaa ww atv L3 awwb vis b3 N mus un sw a iss wi s i vu a au a L by e a sTi 5 k J vs __ssa--. J L-- 2- J -__ . 211 LL___ L. _tt__L __ 1 2 2 L 2 _ _. _ . c_ s . ....L-g a m a b s a sy suaLbJ dJ d bwuss ww b b 3 5 syJ .. usuw v bL a m i a Nu a avs w5 si bs aw. L uw w sJ_ _ . . wsaLwb via AL_._ 1._A ..mA_. _ _ _ _ _ _ _ _ . . s. _ _ . . . _ _ AL. ____--_1J.L___A _s ___A__s2__ ks rv dw y q ui s k JJ a bwssud g Nwsdgus J bv uddus v b3 N uwL t- y a s g a ussN s s b vs ys v bLw b s ys s Tu___ . 211 L. 2__ . .. ____2_ _t ..cs., l c..__La___ i m m b s vi s a , s s N. o .viss ww ,~ i s..yu w k s __m. m sg mu s y n s vs ou s wJ . , I I MS PTPMTPTPAMT ftATAMMP PAMPTMPnATTAM MPTPMuTUATTAM s yv wawrias Aurvis s y us u spw vvviw A uwa v s e e vii wwiwrusAswasAms I l L2__ JL 2. ----1..J J sL s sL- __L2 26 .L_J .2sk 1 l n.__2 __ sL- L_... _.. 1.. j puJLu vie bstw uvvvw w y u a pu b 3 vi 3, sb ua wviN4uvwu bs su b b5 N uwb vib5wa uddvwauwww TV s bi t 2--- LL_ ---..___A__ L. LL_ 2-___.._d TP S_--.L . . L a $. . LL_ . MPf 1P ut P 100 --_..SL2-_ riJs N sw AW I w du i b s 313 s s vm bsIL w m :yws a uvse bv b3 m a ruryi o y wu sw a vi assu b dubsJsJ bstw asu _, en r Pn ne,_s. ._2 .____;2__,.. . _2__2,2_._. L. __2 ____2;__. 2__ .. _;._2 e,n u woe s -s u b s on o hmmus u vs .u wi n u.-, mm www.un,3.J. 5 3, s s a 4 -. s b s m.ui u u..._s- 2_22__ 2...

                     .2,_2a2-._,                                               -3 . u _ _ . a . s

__.N .4 is a e a -s s b s m.u. u Bovaubso . n N o r, 2. ._ su b4asm. u c2_2 I 1 I [ CPSESNo Significant Ha:ards Consideration - CTS 3N.3 38 10/3088

I ESFAS Instrumentation 3.3.2 ; f i SURVEILLANCE REQUIREMENTS l - --- - - - - ---- -- - ----------.

     ........................................N0TE Refer to Table 3.3.21 to determine which SRs',;;other;;than1ESMFM
                                                              ? apply for each ESFAS Function. ESF                                      3.3 55

! _ g.3.3 55

         .. 5,    .

N1$.W. DR . _ .,, __.. _ , m - _ . . _msammxuw~ta =~wuM.. . ... SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours l SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.2.3 "CE W3:3-601 TP.; ;;ati ,uity 2;d ;;;;y k cxclud;d. 31 d;ys c. a mmfm- A f*Tt I A TT rul f Mr* T f* TPPT PT a r*f'Pn PM TPPT s sa a vs m nw s un a avvi n.vuaw e A.w a . v s nwwwawv s n.w e j BASIS j I!ptjtsed] SR 3.3.2.4 Perform MASTER RELAY TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.2.5 Perform COT. 92 days SR 3.3.2.6 Perform SLAVE RELAY TEST. 92 days N#8%M ' i 3*3'5 SR 3.3.2.7 --- -- --- -- - - NOTES - - - - CP 3~3 005 l IIVerification of relay setpoints not required. 22 ActuationXfina]ideviceslnotjincluded i 31_. ays s 4

                            ...............................................                              Y                                  o.2 17 mummmmme Perform TADOT.

l I 10BOM8 [ CPSESMarkup ofNUREG.1431 - ITS 3.3 3.3 32 i i l

ESFAS Instrumentation l

l l B 3.3.2 l : BASES be left set consistent with the assumptions of the current unit , specific setpoint calculation. : i The ";s found" ond "n icft" valucs ;;;ust als; bc raerded end i revicued for cemistc xy with the a s=+tism of th; survcillexc ! j intcry;l catcsion = lysis '"cf. O when applic;bic. ! The Frequency of 92 days is justified in Reference 6. j SR 3.3.2.6 l t SR 3.3.2.6 is the performance of a S uVE RELAY TEST. The SLAVE l RELAY TEST is the energizing of the slave relays. Contact operation is verified in one of two ways. Actuation equipment that may be operated in the design mitigation-N00ELaode is either i allowed to function, or is placed in a condition where the relay contact operation can be verified without operation of the ! i equipment. Actuation equipment that may not be operated in the design mitigation-N00E[aode is prevented from operation by the SLAVE REMY TEST circuit. For this latter case, contact operation is verified by a continuity check of the circuit containing the slave relay. This test is performed every 92 days. The Frequency is adequate, based on industry operating experience, considering instrument reliability and operating history data. SR 3.3.2.7 SR 3.3.2.7 is the performance of a TAD 0T every 1 92 aays. T This test is a check of the Loss of Offsite P , 0 2 17

                         ...m.. ..... ,,m.        ..,~--.y..m....                  .....m.  .. . ..mi on "ressurc      Low Functions. C;;h ruxti;n is tested up to, and including, the =stcr tr;=fer rel;y ceils.

The test also includes trip devices that provide actuation signals directly to the SSPS. The SR is modified by a Note that excludes verification of setpoints for relays. Relay CP 3.3-005 setpoints require elaborate bench calibration and are verified during CHANNEL CALIBRATION. The X isjuodifiedipy aisecondinoteithatlexcludeslthelactuation3fitina1Zdeylcesifrom thelsutgillanceitestijg7CThelstattlofithelauxiliarylteedwatet Pumps;during M 1 operations 11nitiates;anlunnecess.ary p] ant transient;I",qTheFrequencyisadequate. It is based on industry operating experience, considering instrument reliability and operating history data, i (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-119 10B0M8

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-19 APPLICABILITY: DC, CP, WC, CA REQUEST: This change moves functions provided by a safety injection signal and the AFW pump start entries (and " note] for Functional Units [6.e, 6.f, and 6.g] in current TS Table [3.3-3] to the ITS 3.3.2 Bases. Comment: Clarify the intent of this change is to state that descriptive text regarding ESFAS functions is moved to the Bases with the limitation and restrictions of the CTS ' j unchanged. Provide a citation giving the location of the text in the Bases. FLOG RESPONSE: The DOC 2-19-LG will be enhanced to provide the requested information. ATTACHED PAGES: Enct 3A 16a T I

 . _ _        _   _ _.           _ _ _ = . _ - . _ . _   _ . .  ._ _ _ _ _ ___ _                         ._. _.._ _ _. _.. .

l CHANGE NUMBER NSHC DESCRIPTION 2 16 LS 12 ACTION Statement [24] for an inoperable channel in the current TS Table [3.3 2] Functional Unit [9] is modified to be consistent with NUREG 1431 Rev. 1 (i.e., a 7 day A0T in ITS 3.3.7). ; 2 17 ES-+3 Thc ;.nthly T= h;s k:n atcaded to qu;rterly. 0 2 17 censistent with ""'IC 14H ";v 1.Ilotlesed 2-18 LS 31 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2 19 LG .his changc ;;;;vcs functions providcd by ; 5;fcty 0 2 19 f Injection sign;1 end th; A"' p;;p st;rt entries [ ] f., ' Tunctiensi 'Jaits [0.c. 5.d. end 5.c] in currcat TS j l T;bic with "J"IC [3.314312 end "cv.1. 3.3 3] to the Theltext]n; ITS 3.3.2 0;;;cs, con:;istcn functional;UnitsI[1'i 6;c;;6;d, land;61e):oficurrentMjJable;[3.3!2:andl3.3f 3) ; l describingithe;ESfASifunctionsiptoddedibyza; Safety l l Injeg,tiogisipallandithe;AFW;pimpistarrentrjes;[3l are i noveOolthEAPlMPSLE15MElEAII6LISES7&C0 ZAND APPLICABILIT.Ji$ection!stthe1ITS G22iBasesE?te31st_of functiersnitiatedExsafetrimette;sjmarand;the patthlatMpongsEMted3nyobe31stifying LniorisatjoniferIthaltetatriedluritt.tonauh!1ts;ItM IMtatiesIasd2gstrictsonslof;theauttent31 slate unchangedzDe fonctigajiunitsIntefetainedi1Ethe31s 411e3hEdesetip11gasterjatislaoyeditolthe;sases; l i l l l I L i . i i l l l r CPSES Description of Changes to CTS 3N.3 16a 10B088

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-20 APPLICABILITY: CP REQUEST: The Functional Unit for containment vent isolation is moved to ITS 3.3.6. There are no technical differences introduced by this process. Comment: Additional applicable conditions are added for CTS Function 3.c.1, Containment Ventilation Actuation Automatic Actuation Lcgic and Actuation Relays. Provide justification for these changes. Also, what is gained for the logic to be operable l under the specified conditions, if none of the trip functions are required to be operable. FLOG RESPONSE: The ITS Table 3.3.6-1, Function Unit 1, has been revised per JFD 3.3-79 . to retain the CTS. Specifically, the Applicable Modes for the Manual Initiation of Containment , ! Ventilation Isolation have been revised to maintain the CTS Applicability of MODES 1,2,3, and 4, as described in CTS Table 3.3.-2, Functional Unit 3. See response to Comment number Q 3.3-79. ATTACHED PAGES: None

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-21 APPLICABILITY: CP REQUEST: In CPSES current TS Table 3.3-2, Action 17.1 replaces Action 17 for RWST Level Low-Low and Action 17.2 replaces Action 17 for SG Water Level- High High. Comment: [OOSl]- Extended test AOTs for bypass and surveillance are based on approved topical report WCAP-10271. {CP} Correct the confusion in the opening statement of the NSHC. Clearly identify the CTS requirements and the proposed change to them. FLOG RESPONSE: The substitution of Action 17.1 for Action 17 for the RWST Level-Low-Low did not introduce any changes in the allowed outage times. Consistent with the STS format, Action 17.1 was created to specify the shutdown track required to exit the applicability of the RWST Level-Low-Low trip function. The only actual change introduced is the relaxation of the requirement to place an inoperable channel in " bypass" rather than in " trip." The bases for this change is described in LS-22. This LS will be enhanced to more clearly specify the scope of the evaluation. ATTACHED PAGES: Enci 4 49 l

i l l IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS l NSHC LS-22 10 CFR 50.92 EVALUATION ;

FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE l REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS l

l r cd application of Action Statement 17-1 to Jn-curr~elit

           ,/ an inoperable RWST Level Low-Low channel requires an inoperable a channel to be f         placed in bgcss. J.ich is icss restrictivc than piccing the channel in the                                      0-2 21 i
      /'          tripped position, effectively reducing the trip logic from 2-out-of 4 to i             1 out of 3.HThe proposed ~ change,2testng?ActicrEStatement'173,0would;only; require j                  thel M_$leichanneEtolbeJ1ecediin" bypass 3hich; effectively;reducesithe trip                                           {

l

                  )cgicXrosltheQnitiall2foutfofi4;to22500tsofi3HThe proposedichangelisfjes_s restrictiveqin;,thatitwo_channelsZareirequireditolinitiate;altrip;signar,7ather than'aisi.ngleichanne]gConverselyEfroalthelstandpoint offeliable: plant operation, thelproposed; change,would maintain;the;reli.abilitylof_theltwo-channels-toitr,ip logic] This cction is ;pplied to ESFAS Functional Unit 7.b. =ST Level Low Low nd reficcts improved TS 3.3.2. Condition K. The RWST Level Low low trip' function
                                                                                                    ~

coinddent-with-the-presence of7nM" 5Tgn87 provides a s~enif-~a~Dt~oiiialic switc over ! of the RHR pump suction from the RWST to the containment sump. The RWST level function is provided by 4 transmitters. These transmitters provide no control function; therefore, a 2 out of 3 logic is adequate to initiate the protection function actuation while providing single failure protection. A fourth channel has l been added for increased reliability: however, only two channels are required to satisfy the actuation logic. Placing one channel in the bypass condition modifies the trip logic to be 2 out of 3. Because this function provides no control function, the remaining

channel can be placed in bypass for an indefinite period of time without degrading !

the capability of the actuation function to tolerate a single failure. The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted l below:

                           "The Commission may make a final determination, pursuant to the procedures in                                 i 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves a no j                            significant hazards consideration, if operation of the facility in accordance

! with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an

> accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any
accident previously evaluated; or: 3. Involve a significant reduction in a margin of safety."

CPSES No Significant Ha:ards Consideration - CTS 3N.3 49 10B0/98

, .. _ _ _ - - . _- _ . . _ . .- m _. __ _ _ _ . _ - _ _ __ __ _ _ _ . - _ __ i l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: O 2-25 APPLICABILITY: CP, WC 1 1 l REQUEST: The requirement for manual actuation of a single main steam isolation valve has l been moved from current TS Table [3.3-3). OPERABILITY of individual lines is assessed under l ITS LCO 3.7.2. i i Comment: ITS 3.7 2 addresses valve operability and as such the CTS changes i proposed in Table 3.3.2 are deleted in the ITS. Provide an less restrictive justification for the CTS changes which result from eliminating these main steam line isolation l instrumentation requirements. CN 2-06-LS-33 is an appropriate application of changes to CTS. f {CP} Note that CTS Action 21 is deleted as part of this change and the DOC reference ! is 2-06A (CTS markup 3/4 3-28) which is 2-06LS in Section 3A. 2-06LS does not apply to the proposed changes in general and to CP specifically. FLOG RESPONSE: DOC 2-25-A will not be used. DOC 2-06-LS-33 will be adopted to justify the changes. Slight modifications are required to DOC 2-06 and to LS-33 to extend the j applicability to other FLOG plants. l ATTACHED PAGES: 1 Enct 2 3/4 3-21 and 3/4 3-28 : Enci 3A 15 and 17 l Enci 38 11 and 13 Enci 4 2,60a and 60b l l l l d i v -n.

TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MIMINUM

                                                            -itEQUIRED C".'?:t:LS                CHANNEES           APPLICABLE                                                           bl'43'A"I TOT *d."0.

OF CHANNELS TO "I" 0"E"# LE MODES ACTION i1-04ELGv ,

                   -FUNCTIONAL UNIT

4. Steam Line Isolation

a. Manual Initiation p.

1/ste;= " nc 1/ste : 'i = 1/cp^rati~g 1. 2*--3* 21- g

1) I-Jivital Stc;; Linc stc;; linc l 0 2-25 l '

2) System 2 1 2 1, 2*, 3* 20 j 2 1 2 1, 2* , 3* 19

b. Automatic Actuation Logic and Actuation Relays 3 2 2 1, 2*. 3* 17

c. Containment Pressure--High-2 3/ steam line 2/stc;; linc 2/stc;; 1, 2* , 3'

17

d. Steam Line in ny stc;; line Pressure--Low Mne 3/ steam line 2/ste;; linc 2/stc;= 36

17

e. Steam Line Pressure--Negative in any ste : 1inc -

Rate-High Mne i t CPSES Markup of CTS 3N.3 3M 3-21 . 5/1537

_. ..- .- - _. = _ _ . .. - - . __. . TABLE 3.3 2 (Continued) ACTION STATEMENTS (Continued) ACTION;17.2 With the;3umbecofREBABLE mchannels llonellesstthan;the; Required Channelgigpetat$gn3gy,3rgceed proddeditklol]cwing 12 N-M M l conditig!mmelstagnign a) Re,6MlacedMMjttypedJusuHtten witNINtfulemissia b; N0tCMMMMEQF%M]1MRChe bspMBW W n M n A N2Husse#9anenAesttqs 4 ap!grJ N 1 3 2 m Otherwi.se?I M A W i!E132tg the_next X hour _s; ACTION 1B - With less than the tiini;;; Nu;&r of Required; Channels l 31 43 AM V i OPERABLE, within 1 hour determine by obxrvation of the associetcd gr;;;issivc annunci; tor windou(s) that the interlock 41 52 LG~W l is in its required state for the existing plant condition, er ' l apply Sgcificctica 3.0.3. oCbelinJGEi33jthinithe:next:6 42-14 M sf houts;andNEElwithinithelfojlowing;6; hours;

ACTION 19 - With the number of OPERABLE channels one less than the N g g;43;gg Required Channels OPEPXLC icquircant, restore the inoperable i l channel to OPERABLE status within 6 hours or be in at least HOT STANDBY within the next 6 hours and HOT SHUTDOWN within the l l following 6 hours: however, one channel may be bypassed for up to i l 4 hours for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE. l ACTION 20 - With the number of OPERABLE channels one less than the Tetet g3443;g g RequirediNumber of Ch;nxis, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STANDBY within 6 hours and in at least HOT SHUTDOWN within the following 6 hours. ACTION 21 - Sith th; nu;btr of OPEPXLE chenxis ex icss then the Total Nuckr of Chenxis, rcstcrc the inugrable chenxi to 20 ALs OPE"X LE st tus within 4" hours or dccler; th; ssociated 0 2-valv; inog rabic and takc thc ACTION rcquired by Sgcificatica 3.7.1.5. ACTION 22 - With the number of OPERABLE channels one less than the M4n4 mum f3 43 An Required; Channels OPEPXLE rcquirc; cat, restore the inoperable channel to OPERABLE status within 6 hours or be in at least HOT STANDBY within the next 6 hours; however, one channel may be bypassed for up to 4 hours for surveillance testing per 1 66 LS Sgcification 4.3.2.1 provided the other channel is OPERABLE. 0-3.3.j ] CPSESMarkup ofCTS 3M.3 3M 3-28 10/3088

CHANGE NUMBER HSBC DESCRIPTION 2 04 LG The requirements stipulated in ACTIONS a and b are moved to ITS Table 3.3.2-1, with explicit direction contained in the ITS ACTIONS Bases. 2-05 H "ct ;pplic;bic to CPSES. Sc; Ccavcrsion C -,.,;rison 0 2 05 Tebic (Encissurc 20).M6 CaggainmentM_6JiggMeJM NJMBBW!ad6.] WMMXBF - 1 < '

                                                                             ?.                          ,

x ' ?RLJG the temaapesetjgsstggestur -

1. . f Justelto inesseneuris msment;eurgggggin2gualml.ies Wit $1Econtatuant![adCore31terationslitegardles.siof M(BE].

2 06 LS 33 "ct ;pplic;bic to CPSES - TF -1: urc 30), " ona);UnjtE4(a11) c Convc sic oficurr & -[r i nn}0225 l TS; Tab]e;[3:3f2]amanuallinitiat,1on ofdindivi.duaEsteam linOsolatjon',11s"not an;ESFlunctionlend21tlis'.,therefor deletedf alongyithitts! ACTION;StatementI[21]1fromithe ESFASiTEZconsistent.yitif NURE6314313eyZM 2 07 LS 11 ["ctc (c)$ cur. cat TS Tebic 3.3-2 for the Stc= Linc Iscistion functional 'Jnits 4. .2. 4.b. 4.c, 4.d. ;nd 4.c is rcvised to state th;t the LCO rc uirc cnts ;re not applic;bic in "00:5 2 end 3 whcn the "SI'!s erc cicscd end dc;ctiv;ted.] Note [(g)] is added to current TS 0 2 07 Table [3.3 2] for the Feedwater Isolation and Turbine Trip Function [ Functional Units 5.a. 5.b] to state that the LCO requirements are not applicable when the [FIVs and bypass valves) are closed [and deactivated or isolated by a closed manual valve]i;[theteforelthereIisi,oineedifor n the associated actuation 11nstDugentation;toibeloperableD The314sdre;ofitheMMified;Valyes~ isis 0Hictent30 ensgelthe3s61ationlfunctiotf[isZcomplete. When these valves are closed [and deactivated or isolated], they are already performing their safety function. These changes : are consistent with NUREG 1431 Rev.1. l 2 08 H [New ACTION Statement 17.2 replaces ACTION Statement 17 in current TS Table 3.3 2 Functional Unit 5.b. New shutdown requirements are added for Action 17 new Action 17.1 and new Action 17.2.] These ACTION Statements, written to reflect the Applicability of the affected channels and for consistency with ITS 3.3.2 [ Conditions 0. I and K). are more restrictive, by one hour, than the current ACTION Statement [s] which invoke [ ] LCO 3.0.3 if the inoperable channel is not placed in trip within 6 hours. CPSES Description of Changes to CTS 3H.3 15 10BOM8

l I 1 I CHANGE NUMBER RSliC DESCRIPTION 2-20 A The Functional Unit for Containment Vent Isolation is moved to ITS 3.3.6. There are no technical differences introduced by this process. 2 21 LS 22 In current TS Table 3.3 2 , Action 17.1 replaces Action 17 for RWST Level Low Low. Action 17.1 allows a channel to be placed in bypass for i testing, which is less restrictive than placing the channel in the tripped position as required by the current TS. ! 2 22 A Not 'Jsed. ThelC]EfgEgefflabM[313:2]lisitechnically 0 3.3 63 l equivalentjto"IT5;eateG(b)Mab]e 3;3;21. l 2 23 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2 24 LS-19 The Required Action for an inoperable SI sequencer is revised per ITS 3.8.1 Condition F to extend the time available for restoration of an inoperable SI sequencer from 6 hours to 12 hours, i 2-25 k The rcquir;n .t for anxi xtu; tion of ; singic nin stc= isolati;I) volve is not en EST function, but i a nfety funtion for the SC" 0225 l l cvcat, end h;s bxn ;;;;d fre; caricat TS Table [3.3 2], con-istent with N'J REC 1431 Rcv.1. The EST function requircs isoletion of all l intact stex lixs. not individu;l lixs. OPEP2 ILI"I of individu;' i l lines is essessed under ITS LOO 3.7.2 with the Ca.piction Ti n :-

                          'iscu ncd in th; 3/4.7 p;;k;;c. Not'used 2 26    LS-21 The Required Action for an inoperable Control Room [ Emergency                          0 2 26 Recirculation] [ Manual Initiation, or SSPS] channel is modified to be preside ;ppropri;te utions with the nu;ber of OPEPR L: chenxis [tw;]

icn then the nu ber of Rcquired Channels, consistent with NUREG 1431 Rev.1. TheCproposed changeLwould_prov_ide;approprjate"actionsitolbe takenl"ilfiljetfieflishutting doimithelplant peC;1.0013EDI3Eifi[two] channels 1cfzCon_trollRooml[ Emergency; Recirculation]"[ Manual 3nitiation? or;SSPSEarelinoperableZ3 Depending on the initial mode of operation, the modified action requires either:

1) [CREFS] to be placed in its [ emergency recirculation mode (one train) and the other train declared inoperable and the Required Action for an inoperable CREFS train be taken.] or a plant shutdown to be initiated, or 1

2) immediate suspension of movement of irradiated fuel assemblies and Core Alterations. !

l l l CPSES Description of Changes to CTS 3N.3 17 1080/98

Page.11 cf 22 CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 APPLICABILITY TECH SPEC CHANGE DIABLO COMANCHE WOLF CREEK .CALLAWAY NUMBER DESCRIPTION CANYON PEAK No - not in Yes Yes CTS ACTION b.1. Equation 2.2-1, and the values for Total Allowance (TA) Z, and No - not in 2-02 current TS. current TS. A Sensor Error (5) are deleted, consistent with NUREG-1431 Rev. 1. No - retained Yes - Moved to Yes - Moved Yes - Hoved to 2-03 The Engineered Safety Features Actuation System Instrumentation Trip Setpoints to USAR. ITS 3.3.2 in ITS. Bases. LG are moved to a licensee controlled document. Bases. Yes Yes Yes Yes 2 04 The requirements stipulated in ACTIONS a and b dre moved to ITS Table 3.3.2 1. LG with explicit direction contained in the ITS ACTIONS Bases. Mc ,cc No ;;; Yes Yes 2-05 The Functional Unit for Containment?[ptegeJentilation] Isolation CTS [3-e- 0% 2 20 A.yes CN 2 20 ",.Yes H Table _3.3-4, Functional, Unit;2] is moved to improved TS 3.3.6. Improved TS 3.3.6 [edd; ccquic c.;; on t' c 0"C"""'L:"! cf th; _..;;i ..~..; p.. sc E0-2-OL l rediction r.cnitor; :nd] extends the Applicability for the [".au;l hiti; tim :nd "0" ESTAS. Containment: Ventilation Isolation] actuation logic to include during movement of irradiated fuel assemblies within containment [and Core Alterations; wp- - regardless.of.HODE). ~

No - retain %c Scc 0% 2- %; Scc CN Yes 2-06 Functional Unit 4.a.1) of current TS Tabl [3.3 32] as been deleted. !

I CTS. 25-A- Yes 2-25-A- Yes. LS-33 w_ Yes Yes Yes Yes 2-07 [Notc (c; i; c.cd-ficd for c.cccnt 5 Tath 3.3 2 for th; Stc= Li c !;chtten LS-11 runction to :tstc that th: LCO icq.t. .~..;; arc not ;pplic; tic ' ."00C0 2 ;-d 3

                             -~....~....,..m                       ,.mm.                        .. . ~ .. m ]. Note [(g)] is added to current T5                                                                                                                                                                                                        l020E l Table [3.3 2] for the Feedwater Isolation and Turbine Trip Function to state that the LCO requirements are not applicable when the [FIVs] are closed and deactivated [or isolated].

Yes Yes Yes Yes 2-08 [New Shutdown requirements are added for ACTION 17. new ACTION 17.1 and new H ACTION 17.2] These ACTION Statements, written to reflect the Applicability of the affected channels, are more restrictive, by one hour, than the current ACTION Statement [] which invoke [s] LCO 3.0.3 if the inoperable channel is not placed in trip within 6 hours. Yes - Hoved to Yes - Hoved to Yes Hoved Yes - Moved to ! 2-09 Separate ESFAS entries for the motor driven and turbine-driven auxiliary Bases, to Bases. Bases. feedwater pumps are no longer necessary. The only difference in the Bases. LG requirements (an SR 4.0.4 exception for response time testing of the turbine-driven auxiliary feedwater pump) has been addressed in the ITS by a Note in Surveillance Requirement 3.3.2.10. [] __ l i 10B0 M , CPSES Conversion Compariwn Tame - CTS 3N.3 t

                                      . - . _ _ _ . _ . _ _ . . _ . - - - - - - _ . - - . _ _ - _ _ _ _ - - . _ _ -              . . _ _ _ _ _ - - _ _ _ _ - - - . - - - - _ . _ _                          __ - -_ - - - - _ -_ __ -._                                                                       - _ __._-_.. _ _ - _.--________ - ~

Page 13 of 22 - CONVERSION COMPARIS0N TABLE - CURRENT TS 3/4.3 APPLICABILITY TECH SPEC CHANGE DIABLO C0HANCliE WOLF CREEK Call.AWAY NUMBER DESCRIPTION CANYON PEAK There Yes Yes No - see CN No - see 2-20 The Functional Unit for Containment Vent Isolation is moved to ITS 3.3.6. 2 05-M. CN 2-05 H. A are no technical differences introduced by this process. Yes No No No 2-21 In CPSES current TS Table 3.3-2. Action 17.1 replaces Action 17 for RWST Level LS-22 Low Low and Action 17.2 replaces Action 17 for SG Water Level - High High. N/ Ayes N/ Ayes N/ Ayes N/A 2-22 "ct U;cd. The, CTS [a] . note:of 3 Table [3.h2] is technically equivalent;to;ITS Yes l 0 3.3-( 3l A note (b) ATable 3.3.21. No already in No - already Yes Yes 2-23 This change revises ACTIONS [14. 27, 27a. 34. and 34a] in current TS Table 3.3-3 current TS. in current Ts. A to clarify that the 12 hour A0T to get to MODE 3 includes 6 hours for restoration followed by a 6 hour shutdown to MODE 3. Yes No No No 2 24 At CPSES, the Required Action for an inoperable SI sequencer is revised per LS-19 ITS 3.8.1 Condition F to extend the time available for restoration of an g inoperable SI sequencer from 6 hours to 12 hours. for ;;nual ;;tuctic , of ; ;in;;1; ;;i ;tc;; i;;l; tion v;lv; h;; "; rct;ined Ves NA Ves NA "c\ 2-2 i l 2 ?c ;que _..t M kun ;;v;d frc; cu. rent 5 T;bic [3.3 2]. ^"C"""ILIT of indi.idu;l 'inc; i; GW NA 2-Ofr 0;;;;;;d L. A. 15 LCO 2.'.2. Not used _ No - not in Yes Yes Yes 2-26 The Required Action for an inoperable Control Room [ Emergency Recirculation] [ Manual Initiation or SSPS) channel is mortified to provide appropriate actions current TS. LS-21 with the number of OPERABLE channels [two] less than the number of Required Channels. ! No Yes No No 2 27 The CPSES Action Statement for the loss of offsite power - start motor driven A auxiliary feedwater pumps is modified to require that if the Action Statements are not satisfied, the plant be taken to MODE 4 to exit the LCO Applicability. The CTS requires that MODE 5 be entered; however, because the function is only applicable in MODES 1. 2. and 3. the LCO would be exited prior to MODE 5. and MODE 5 entry is not a requirement. Yes No No No 2 28 This change moves DCPP information inserted by IA 118/115 on containment spray r LG and safety injection coincidence to the Bases. 10/30/98 CPSFS Conversion Comparison Tame - CTS 3M.3

            --             - ~ _ _ - _ _ _ _ - _ - _ _ _ - - _ _ _ _ _ _                                                                                             ___ _ ______               _ _ _ _     _ _ _ _ _         _ _              -" " - - - - - - - - - - - - -                               _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ___

i l l l I NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC) l CONTENTS (continued) LS-30........................................................Not applicable LS - 31. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c a bl e LS 3 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot aool i cabl e u LS,33.....................................................m cr -__r.._ .u.s_00 fa Ro.225 LS 34........................................................Not appin.ause

LS 35 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not appl i cabl e LS 3 6 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not used u- y". . * """' '- CA 3.3 009 LS 37. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not appl i cabl e LS 38 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot used v-y- ". . w o"u . '- CA.3.3 002 LS 39.............................................................. 61 LS-40.............................................................. 63 LS 41. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS . 42 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c abl e LS.43................................................................... 65 g;_44w-m.

                  .         e. s u . , u . u,u m       ,,m-,,m.

a_w . u u,u.y . . . .m,",". su , u'.".. .". . .~, .a na Not APP _l_icabl e

                                                                                                                  ._,-e m

mm o.3.3.j m.c. 66a LS;45 usu, _.._w y y a, u, oxy _uu, um u,, m , u.

                                                                                                                  ,,..uy u . y y2ytu ty g;gu.m.         .m, vn . .nw        wwm             u ms u . wo      .mwm    nur-m,u.       m. "v"v"    u ."nNot".a99 ~icable.
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LS 4a7 'u . u'e"u"u u'x"*xu."m"~u ."u u_*. . .x". . ~ .". m m'"u,w"u . . t. o. t'a99~lica.bl e

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g4 .a m.n,yyy m. s.mu . m.y usm, uu nt un wo

                                                                .s,_

uu u . ., u"u"u at' APP rNo_1ca.1 b_l e.

LS;4.9a"u~'w" ~uw"u"m'u*xu"u"u w"u'"w"w"um"u""u"x".n ru""u".wNot" APP

                                                                                                                                           ~    1c.abT 1        e N                        N                                     "

tra L. S_50"uu"mzux"nu~~"ume . . + "uu~u&~u"u.tua

                        -                                                            at                w".u.u"muoM9m                  PP.U_      cab  _N,
                                                                            "                                       v LS..:.._51_"u".u^'N".mz"e*u*"un a.m.w                                  . "+ u tu"usuu"m"".u z"u uu.uz"um _Not+#P1.1 cable LS; 5.72un*z"um"u"w em'"u               m u'"u"um"u*o"u.m uwatuu'"msNo._t'aDP1_1ca.b.
                                                                                                'Nvw                                                 _l..e.

N l LS~- 5~3 u"z"u"u*xu".. ."m'"usw"a~u"a.. *ve"u."zu w a'""w~z"uu"u uu*u"z.ot'a9P icabl.e

                                                                                                       ~*m' L. S_;54u"t. . .v.                       r m'"um"um"m".u'w                    -

m'e. u u u"mmuuu"u u"u_Not~u.a PPlicabl e. V. ' Recurring No Significant Hazards Considerations "TR" TR-1.................................................................... 67 0708 E,2 m..m.. . uu e m... w smm . w,., - y . , m _r-.- ,,.-.y..m m z u u m u u n.. m *. u. w u m

                                                                                                                              ,. y .           .,
                                                                                                                                           ..u*-   m.. 1 59 I

l t CPSESNo Significant Ha:ards Consideration - CTS 3N.3 2

1 l IV. 1 SPECIFIC _NOSIGNIFICANTf,AZARDS_ CONSIDERATIONS ! NSHC LS'33 0 2 25 10,CFR15d21kAlllATI.0N l FOR TECl#i1CAliCHANGESMTillf0SELLESSiRESTRICTIVE REQUIRENENTSJWITHINJ1EREltlICAC, SPECIFICATIONS 1 l BIfWR$9W@ith!it[AMllef.16353sh]3RE4]EmmusehM;oCindyi tdual steus2teggsolationssinganW11mgesagignitrys;tingsgese;eletedMonsivith 18ESMILw="*!.BR11: tom *_ selEliUNEEIEL5ht~JSf#sst192egstres]solgtjen;of as23lpigataneemm3.tmeicnotL~antlutenevtstusm_ sginosafetirme!!113ess;A.pupuoselithe tefielANSI1s!aastionnlingstgghoissels33mlimaetjene!L1RWtWa2Mariual inttgesamterzsystenMvellsteamline:1solat1MtDetatted jnitbejESFAS TS'and , setygsaray=%forlthe; automatic}1solagonifunction] l l l El l l C3 The proposed;TS change _s_hasibeenieyaluated;and;1tLhas_beenfdetermined thatLit l' invplyesino;signi ficant; hazards ;consj deration KThi sidetersj nation L has . .been j Performed;in accordance withithe3rj.tetialset' fort Ein;10;CFRl5.0.92(c) as quoted be]ow] I

                               !Ihe;Commi.ssion;may makelaifjnalidettraination.2pursuantito;the, procedures;in                                 i 50.;915that2a; proposed,8mendmentItoJan~operatingl]icenseifor;alfagility                                        l
                               ]1 censed,underl50 211b);olr 50j22iorlforla"testingXac1]jty;1_nvolvesino significant; hazards; consideration 21Eoperation;ofitheifacilityJ1Eaccordance with:the ~ proposed ; amendment!wouldinotJ, 1.'      InvolveXsignjficantijncrea_sejjnJhe:probabiljtyforJconsequences of.an accidentJprevious1_yley61uatedj"or 21      Create _the possjb111tyZoflalJ]ewioridiff_erentikindmofiacgj, dent from_any accident 2previouslylevaluatedKor 3:      Invol ve~alsignj ficantireductioniinia; margin ~of esafety;"

T_he;fo110wingLevaluation'isiprovided;forf thelthreeicategories of;the;significant I hazards; considerationistandard.s1 li Does1the_ change;1nvolveIalsjgnificant; increase 11n'the;probabiljty or f j consequences:ofian_ acejdentlpreyiouslylevaluat.ed? l 1 Overal_1 protection systenJperformance"wil_liremainJwithin2thelbounds;of the prevjously performediaccidentianalyses;sjnce no hardware;1 changes 1are; proposed. i

The on]y accident which creditsimanuallsteam 11ne~jsolation;is'theisteam
generator tubelrupturei.(SGTR) E Ihe: SGTRana]ysisfpresentedlin;the;FSAR assumes;that all;fourfsteam linesjare; isolated _ simultaneously;whenloffsite J j

i CPSES No Significant Ha:ards Consideration - CTS 3N.3 60a 10/30/98

i Iyc2 SPECIFIC.MSIGNIEICANT HAZARDS 2 _ CONSIDERATIONS 0 2 25 NS E M i33 . l (contjnued) power,;1sflostin:orderltoJna31minitheioffsite ,radjologica]lconsequences . Titt s3nalystsassumptionjis;Mtf11ed>y;the;systangewetetonte-function i ejscasens:abst!!2 Rut:stW!!!BRl#9 sages 34Mant2RecMmeRabuh33ttpGuw]eg!stletttatorsu l 1he e!RGBELK DEEMROM3RREDItsesipadetsen 1R;theDerLangageja!gigigamaggasseNn;tsut aumberletchtligggesitupegedJon equtgiment. m ayadito3Mg q MR M.E accident;siteetton"$7perefore7sthe proposed;tggggeg2dolagtjggg!IjpgEMgtitticast 1pcreaseI10the;probabjlity;or consequences pflantacetdetit~orevioujs revaluated; 2f Does:the[changelcreatelthelpossibiljty of;a:newior dtfferent kind _'of accident;prevjj!us]y_.eyaluated? Therelare # 1hardwareIchangesinorlareltherefany; changes;initheisethod;by M ich any;safetyitelated:ptantisystasjpetforms:1tsIsafetriunctionZiThelchangeM11 notlaffectfitheLnormalimethodioLRlantloperatjon;2No;neCaccidentJscenattosi transient;ptecutmotsrlf.allute;sischanismscor211mitingisinglelfailureriare introducedias EresultiorithirejngergIherefore;1the;proposedichangeldoes not:createXhemossibi!1trofxneer;differentikintof ~accidentitrocany prevjous]ypalgted] 31 Does1thisichangelinjtoltelalsjggificantireductionlinla:sargin Lofi.safety? The: proposed 3hangeldoes]!oEaffectithe: acceptance;ctiterja;forlanylanalyzed l event aThere36111beJeffect3!nJniamanner11n3#itchisafsty11tattsIgr ; itsitingisafettsystemisntt_ togs; ate:determinedpMitthumbeiantnffect on thoselplantisystensle=**tarnto3L!sureithe:accouplishmentgprotectipn functiongIheteM11.t!e3!altapaction;anrearginitpfisafetyi ermdCIEN0lSIGNIEICANEHAZARDSICONSIDERATION DETERNINATION sesed;on;the;above; evaluation;51tNs:concludedithat;the activities; associated with IISMC3Si33*;resultingifromithe3onversjogLto;thejjaproved;TSiformatisatisfyltheino signtitcant; hazards:considerationistandard.s;ofi10iCFRiS0;92(c)fland accordingly,ia nCsjgnificant hazards' consideration;fjndingits: justified) E i CPSES No Significant Ha:ards Consideration - CTS 3At.3 60b 108088

1 i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 2-26 APPLICABILITY: CP, WC, CA REQUEST: The Required Action for an inoperable control room [ isolation] [ manual initiation, l SSPS, or BOP-ESFAS] channel is modified to provide appropriate actions with the number of OPERABLE channels [two] less than the number of required channels. Comment: Provide a safety basis discussion for the proposed changes. Neither the DOC nor the NSHC provide specific justification for providing a no channels OPERABLE condition or for the actions required in that condition. FLOG RESPONSE: DOC 2-26 and NSHC LS-21 have been revised to provide additional justification. l ATTACHED PAGES: ! End 3A 17 and 17a Enci 4 47 l l l l l l I- l r i i e i

l l l 1 i CHANGE ! NUMBER NSHC DESCRIPTION l 2 20 A The Functional Unit for Containment Vent Isolation is moved to ITS 3.3.6. There are no technical differences introduced by this process. , l 2 21 LS-22 In current TS Table 3.3 2 , Action 17.1 replaces Action 17 for RWST l ! Level Low Low. Action 17.1 allows a channel to be placed in bypass for testing, which is less restrictive than placing the channel in the tripped position as required by the current TS. I ! 2 22 A Net U=d. TheJTSla];notle of1Tattl eJ3;3J2]ds;technjcaUy 0-3.3 63 I equivalent 1tol'IT5] note 3b)Mab]eJ.Ti2A i l 2-23 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2-24 LS-19 The Required Action for an inoperable SI sequencer is revised per ITS 3.8.1 Condition F to extend the time available for restoration of an inoperable SI sequencer from 6 hours to 12 hours. 2-25 A The requirc=nt for acauci actuation of a single main stc= isciation 0 2 25 valvc is not an EST function, but is a safety function for the S= cvcat, end has bcca acvcd fre; currcat TS Tobic [3.3-2], consistent l with NUREC 1431 Rev.1. The EST function requires isclation of all intact stc;; lincs, not individual lincs. 0l'ERASILITY cf individuci lincs is = scssed under ITS LCC 3.7.2 with the C;;pletion Ti;c :s discussed in the 3/4.7 p=k;;;. Not!Used 2-26 LS 21 The Required Action for an inoperable Control Room [ Emergency 0 2 26

Recirculation] [Hanual Initiatinn or SSPS) channel is modified t be with the number af R L a cnonn;is [twc]

v. - . . m. orr. vr. . m om....

icss than the numbcr of Rcquired Channcis, consistent with NUREG-1431 ) Rev.1. The:proposeCchangeM]d provide 2appropriatela.ctionsitolbe takerKid.931eu3tfishuttigdown;thelplantiperLtco;3.;o;3.21CEtwo] channel sTcf1ControLRoomf[ Emergency'RecirculationR[ManuallInitiath ( oriSSPSMare]nopetableJ/7Tepending on the init1al moae of operation, tne mooin ea ad vu iequires either: l 1) [CREFS] to be placed in its [ emergency recirculation mode (one train) and the other train declared inoperable and the Required Action for an inoperable CREFS train be taken ] or a plant shutdown to be initiated, or i

2) immediate suspension of movement of irradiated fuel assemblies and Core Alterations.

CPSES Description of Changes to CTS 3N.3 17 10/3088 i l

                                                        .       . . . . .-       . . - _ ~ _ _     - _ .     .. - ._.

i l l l CHANGE NUMBER RSBC DESCRIPTION TheselactionsT;Michligl@lthelectuatio[ofioneltta10fdCREQ]% t I 0 2 26 ' l andJnittstionMaheDp!E!stialgccepensatorislaseres fot[ege inoperabEtresGGiWiE9tDat!1clentlixCasinta10the h*1tatsstygghemagggja!as.; ! 2 27 A The Action Statement for the loss of offsite power - start motor driven l auxiliary feedwater pumps is modified to i I I

1 i , l l l l l l I CPSES Description of Changes to CTS 3M.3 17a 1030/98

TV. SPEClFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 21 ! 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE l REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Tf2cposed3hange M]d;pagidaI,wwppjate)qtionsitoMtgenMn2 ted:of T-226 l l Sk?38Dilhahola!stsecligg!PrJfJtMthannelsror.conggtiggom l Ut!IW!s!WJD$1st@g8R0'aggMMiangenrammessmTakese ! ageingg8CbAWhiQi>JaBemagaggy3taionagEEl3lgfJggiationdsfithe alpgedi!2iDiaspetMantiemmitsammImagem!e~trKt92fJIIEEEBLreis#IR l tagiamagasp;sentmanitaggitageggg);2com; ! In accoraom,e wiUi de r ~* TachMeal Soecificatinns +ha ";p Action if both required channels of Control Room [ Emergency Recirculation] [ Manual Initiation, or SSPS] are inoperable is to enter LC0 3.0.3 and take the plant to Hode 5. The proposed change would prevent unnecessary plant transients by requiring that

specified compensatory steps be taken to assure that control room habitability would I be maintained if an accident were to occur. Thus, depending on the initial mode of operation, the proposed actions [with less than the required number of channels]

would require either: i 1) the [ Control Room Emergency Filtration System (CREFS)] to be placed in its [ emergency recirculation mode (one train) and the other train declared inoperable and the Required Actions for an inoperable CREFS train be taken], l or a plant shutdown to be initiated, or.

2) immediate suspension of movement of irradiated fuel assemblies and Core ,

Alterations. The proposed TS change has been evaluated and it has been determined that it l involves no significant hazards consideration. This determination has been l performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

                    "The Commission may make a final determination, pursuant to the procedures in              1 50.91, that a proposed amendment to an operating license for a facility l

l licensed under 50.21(b) or 50.22 or for a testing facility involves a no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not: i 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant i hazards consideration standards: l l CPSES No Significant Ha:;ards Consideration - CTS 3N.3 47 19B088

 -     .    .    . -.          . = -   -       _.     - _ _ , ... - . . . . -__                   .  .-. _--

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 2-32 APPLICABILITY: CP REQUEST: These changes affect the ACTION STATEMENTS for inoperable undervoltage or degraded voltage relays. For all trip functions, new statements are added which require that the diesel generator, which was made inoperable by the inoperable undervoltage or degraded voltage relay, may be declared inoperable in lieu of entering LCO 3.0.3. If the number of OPERABLE channels per bus is less than the Required Number, one hour is now allowed to restore the channel to operability before compensatory actions are required. Comment: The one hour time period to restore at least one inoperabile channel to operable status (LCO 3.3.5, Actions B.1, C.1 and E.1)is moot when the attemate action to place the plant outside the applicability is within six hours of entering the condition. Restoring a channel to operable status is always an option, albeit in the first or the sixth hour. The Required Action D.1 one hour time period to restore one channel to operable status is inadequately justified. Retain CTS requirements to declare the affected bus inoperable immediately. FLOG RESPONSE: The changes to TS 3.3.5 that were agreed upon during the September meeting are reflected in the response to JFD 3.3-131. The LS-23 will be revised to discuss the safety significance of the change from entering LCO 3.0.3 to entering the action statements for an inoperable DG. l ATTACHED PAGES: l Enci 4 51 l 1 l l l .

TV. SPECIFIC NO SIGNIFICANT HAZARDS CONSZDERATIONS NSHC LS 23 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS The ESFAS loss of power undervoltage and degraded voltage relays are intended to detect a condition where the offsite power supply is either unavailable or is insufficiently stable to allow safe unit operation and initiate the sequences to shed the loads on the seN.7.tards electrical busses (when appropriate). start the diesel generators, and ioad the busses onto the diesel generator. If one of these relays was inoperable, the principal effect is that, in the event of a loss or degradation of offsite power. the affected diesel generator would not be successfully started and supplied to the appropriate safeguards bus: in other words, the effect would be the same as if the diesel generator were inoperable. In the structure of NUREG-1431. Rev.1., any subsequent actions required by the Technical Specifications would be made in accordance with those specifications concerning diesel generator operability. The proposed changes affect the Action Statements for inoperable undervoltage or degraded voltage relays. For all trip functions, new statements are added which require that the diesel generator made inoperable by the inoperable undervoltage or degraded voltage relay be declared inoperable, in lieu of entering LC0 3.0.3. In addition, one bane h now allowed to attaant to restore the channel to operabil' before _fected channe hjsideclarAdiinop hey _. M ;.i ., e nsatory 0 2 32 act s are required. The one hour completion time should allow 41; ti;;;; t; r- -ir ;;;;;;t failur;; cc,d takes into account the low probability of occurrence of n event during the 1 hour period which would require the diesel generators to sta on loss of offsite power. T.lLQtLtpntiallyisignificantlacet;of3he;goppseLchangeijs'tO11cCcontLnued spepttutfor at periodaf31m"J10ccordanceliitth:the: diesel; generator.Hechnical 8pt@fMptien,11n;11eofJnitiating:01st;shutdownJonco!Mance3rith tcO;310.3.. BecauseJeoperablelundervoltageloridegradedjoltage relaKMp3M31gefe#ect on th2el1pbflity"ontM;ensiteJewer;A11Atraation;systeelas~anlinopetele;di_esel sentestm10pproptiste3contalDumequ!!stIactionsIioccatempeotth the act:1egoverning ran;teperab1metenenstatotaMaarcasesmannecessary pligt_W:can:beJevoided31ong)(110!Octentiallfat3nadvertentjplant3t ip n0thossociated; challenges 3e;p1gsstattrsys_tems UISontinued,steactFstate opetetionzelsoinimites;distamancecoatholectrical:gtidrthereby;sinimizing' he potentia 11or: additional:1ossesloflanroffsite;powerisource; The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

                 "The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no CPSES No Significant Ha:ards Consideration - CTS 3N.3 51                               1020M8

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2-40 APPLICABILITY: DC, CP, WC REQUEST: This administrative change affects the manner in which the current TS 4.0.4 ! exception for testing the TDAFW pump is presented. This exception allows entry into MODE 3 I to perform the turbine driven auxiliary feedwater pump response time testing. In NUREG-1431 Rev.1, the current TS 4.0.4 exception from [ Table 3.3-2, Notation d and Section 4.7.1.2.b.2)] is reflected in the ITS SR 3.3.2.10 notes. Comment: The CN states that a note is added to the turbine driven auxiliary feed pump response time testing based on the existing 4.0.4 exception. It does not appear that CTS 4.3.2.2 includes a 4.0.4 exception for this function. Therefore the justification is unacceptable and the classification should be LS rather than A. ; Provide justification for explicit 24 hour interval and SG pressure allowance given in the note to SR 3.3.2.10. FLOG RESPONSE: ESF response time testing requires verification that each auxiliary I feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal. However, for the turbine-driven auxiliary feedwater pump (TDAFP), an exception to Specification 4.0.4 is provided for entry into MODE 3. This exception is provided < because in MODE 4, there is insufficient steam pressure to drive the TDAFP. The exception is converted into the ITS format via the NOTE to ITS SR 3.7.5.2 by specifying the appropriate conditions (e.g., minimum steam pressure and reasonable time for completion of SR). For , WCGS, the CTS 4.0.4 exception is applied to the TDAFP start instrumentation; however, the explicit allowance for minimum steam pressure and maximum time allowed to complete the SR is not explicitly shown. Because it is necessary to start the TDAFP to determine its response time, this same note is applied to the required RESPONSE TIME TESTING surveillance for the ESF instrumentation that starts the TDAFP. All other surveillances associated with the TDAFP start instrumentation are required to be current. ATTACHED PAGES: ) None

l I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3-02 APPLICABILITY: DC, CP, WC, CA l REQUEST: The requirements stipulated in ACTION [a] are moved to ITS Tables [3.3.7-1 and 3.3.8-1), with explicit direction contained in the ITS ACTIONS Bases. The 4 hour AOT for setpoint adjustment is eliminated. , l l Comment: Evaluate how the CTS requirement changes for each use in the ITS. The ) l 4-hour AOT for setpoint adjustment appears to be extended. How can it be that a TS is i deleted (moved to the Bases) and the justification is more restrictive. This change should be documented based on how the ITS treats a channel with the setpoint not met. ] i I l FLOG RESPONSE: DOC 3-02 M is revised to indicate that the CTS action that permitted I adjusting the setpoint to within the limit within 4 hours is deleted. As discussed in the ITS B 1 3.3.7 Actions Bases, if the Trip Setpoint is less conservative than the tolerance specified by the calibration procedure, the channel must be declared inoperable immediately and the appropriate condition entered. DOC 3-02-M is revised to state: ;

   " CTS 3.3.3.1, Action [a] is revised to delete the delete the 4 hour allowance to adjust the radiation monitoring channel Alarm / Trip Setpoint if the setpoint value has been exceeded. The CTS allowed a 4 hour window in which to adjust the Trip Setpoint to within limits before declaring the channel inoperable and taking the appropriate Action specified in the Table.             ,

NUREG-1431 requires declaring the channel inoperable immediately and entering the l appropriate Condition if the Trip Setpoint is less conservative than the tolerance specified in calibration procedures. The proposed change is considered a more restrictive change which reduces plant operational flexibility." ATTACHED PAGES: Encl.3A 20 l l I i i i

CHANGE NUMBER NSE DESCRIPTION 3 02 M .hc rquir;xat:, ;Sa ... GL Laj erc =xd to ITS Tabicb o.3 2 l [ .3.51 ad 3.2.71]. .;ith splicit directi= cataince in the TS ACTIC"5 Sex;. The 4 hour ACT for xtpcint adju; tant is cli;;;inated. CTsAprActicce13s_W) isle!tietsinitsutaLiaiancm3o ! accust3gstem.1ergtkapJgga!!gllttfAhe setpoiquggaejses H I . .- . g ; j u ' .1 Amassasagentin uhich30]R!UmstB!1 30m l channergesetangome me TehrJAWEfRIB alsamstety andjoutsta19.6391319PD81!Mut_W3ess ; consetwatpeitaset!t38e!J!!smajueceptedi130ntierettepryceduresa l Thoroposed_changelis3colL19e!3dX]otEtestrictivelct!ange)hich Q:Plantaperatjana12flaginnl.ity; 3-03 LG Not applicable to CPSES. See Conversion Comparison Table l (Enclosure 38). 3 04 M This change adds the Applicability for movement of irradiated fuel assemblies, consistent with NUREG 1431 Rev.1. [The current TS Applicability of "All" H0 DES does not cover the movement of irradiated fuel assemblies when the core is offloaded.] l 3 05 LS-14 ACTION Statement [28] for the [ Control Room Hakeup Air Supply] [ ] radiation monitors have extended Completion Times, from [1 hour] to 7 days for one required channel inoperable, consistent with NUREG-1431 Rev.1. 3-06 A ACTION [c] of current TS LC0 3.3.3.1 is revised to state the Specification 3.0.3 exception is [ deleted and to note that the Specification 3.0.4 exception is only needed for the RCS Leakage Detection System instrumentation]. The LCO 3.0.3 exception is not needed in ITS 3.3.7 or ITS 3.4.15 since Required ACTIONS are provided l with the appropriate remedial measures for all combinations of channel failures, including shutdown actions, or reference is made to the associated plant system TS for the systems affected by the inoperability of the radiation monitors. [The LC0 3.0.4 exception is retained for the j l RCS Leakage Detection radiation monitors, as discussed in ITS 3.4.15: l however, that exception is not needed for the Control Room Hakeup Air I Supply radiation monitors since their ACTION Statements allow continued operation for an unlimited period of time.] I 3 07 LS 16 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 3 08 H % 4plicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 3 09 LS 24 The Surveillance frequency for the performance of a CHANNEL OPERABILITY TEST for the radiation monitoring instrumentation channels would be CPSES Description of Changes to CTS 3N.3 20 10B088

l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3-05 APPLICABILITY: DC, CP, WC, CA l l REQUEST: ACTION Statement [38] for the [ Control Room Air Intake] (and ACTION ! Statement [30] for the [ Fuel Building Exhaust)) radiation monitors have extended Completion l Times, from [72 hours] to 7 days for one required channel inoperable. l Comment: Insufficient information is provided to justify extending the allowed outage time for one CRVS channelinoperable from [1][48][72] hours to 7 days. If the system l arrangement is such that each instrument channel is dedicated to a single CRVS train l (one-out-of -one starts one train), then the effect of a single inoperable instrument channelis similar to that of an inoperable mechanical train and the extended AOT may l be acceptable. If, however, the two channels are used in a one-out -of-two logic start both CRVS channels, a single inoperable instrumentation channel degrades the operability of both mechanical trains and the justification provided for the 7 day AOT is not germane. FLOG RESPONSE: The response to this comment is addressed under Comment Number l Q 2-16-LS-12 for Callaway, CPSES, and WCGS. l The DCPP control room is common to both units. The normal air intakes are separate, but are in close proximity to each other. There is one train of control room ventilation for each unit. l The pressurization air intakes are at opposite ends of the turbine building. There are two radiation monitors at each normal air intake either of which will initiate the opposite units I pressurization system. The system is designed so that if radiation is detected at one units l normal air intake due to a LOCA or other design basis event, the system starts the opposite units pressurization fans which take suction from the end of the opposite units turbine building. With this arrangement, a single monitor can be out of service without effecting the operability of the ventilation train. Loss of the second required monitor renders that train of control room l pressurization inoperable. The loss of the radiation monitors for a single train only effects that j train, thus it would be similar to a mechanical failure rendering a single train ir' operable. Since the loss of the required radiation monitor would be equivalent to a mechanical failure, the allowed outage time of 7 days permitted by CTS 3.7.5.1 and LCO 3.7.10 of NUREG-1431 for inoperability of a single train of ventilation is appropriate for loss of one trains required radiation monitor. LS14 has been revised to include this system description and justification for the 7 day AOT. In addition to the above, DCPP submitted a version of NSHC LS14 authored by one of the other FLOG members. The corrected copy is attached. ATTACHED PAGES: None

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3-13 APPLICABILITY: CP REQUEST: The proposed change would provide an ACTION STATEMENT for the case where the number of control room airintake radiation levelinstrumentation channels was two less than required number of channels. The ACTION STATEMENT would require that the air supply from the affected air intake be secured or that the emergency recirculation mode be initiated and maintained. Otherwise, restore one channel within 1 hour or shutdown to MODE 3 in 6 hours and MODE 5 in the next 30 hours. Comment: Provide justification explaining why the changes are more restrictive than CTS requirements. FLOG RESPONSE: In the CTS 3.3.3.1, no actions are provided for more than one inoperable channel. Normally, TS 3.0.3 would be entered; however, CTS 3.3.3.1 Action c. states that the provisions of Specification 3.0.3 are not applicable. Therefore, the same actions for one inoperable channel would be applied if there was more than one inoperable channel. In the ITS, the action statements provided for the situation where there are more than one inoperable channels are more restrictive than the actions required for one inoperable channel. Therefore, this change is classified as a more restrictive change.1 DOC 3-13-M is revised to reflect the preceding discussion. ATTACHED PAGES: Enci 3A 21 l l I 1 1 l l I

CHANGE NtN ER HS!E DESCRIPTION 3 10 LG Not applicable to CPSES. See Conversion Comparison Table

(Enclosure 3B).

l 3 11 M The ACTION STATEMENT for an inoperable gaseous radioactivity monitor l 03e l 1s modified to require that the inoperable channel be restored within 4 ! hours. If not restored, continued operation is permitted (similar to the current TS allowance) provided the containment Event isolation] l valves are closed. The change is more restrictive or administrative in 1 i nature in that no time limits for the completion of any actions are specified in the current TS. l l 3 12 A Not Applicable to CPSES. See Conversion Comparison Table l (Enclosure 3B). j 3 13 M The proposed change would provide an ACTION STATEMENT for the case where l the number of Control Room air intake radiation level instrumentation channels was two less than required number of channels. The ACTION STATEMENT would require that the air supply from the affected air intake , l be secured or that the emergency recirculation mode be initiated and j maintained. Otherwise, shutdown to MODE 3 in 6 hours and MODE 5 in the l next 30 hours. - i I n2the1CTE513;33Zanolactjons;;argprpAdedifo_rfggghtg;gne Lnopetable;ean9%IgormsUrg[s:slerwaaltgesingM10!nbletE_ D, l 313;331Mign3Sjistgg1thgtitheRovisions3f.Jpegif,jggignI}jal3 are;nonapp1tceBLMalpf!8Mh0Lancagjgns;fggge33perable ! ghanne13 sag goppljemighereMs!ote3hananEtapparable:thenne]z l Ir[theRthe,Majtatsunftts"l prow;1dcd' for,14heltt_tuntjosQdiere3herq amLeors?$bE'JphlfMegptt$1GtpgnplslateDM;tpsttigt.typ3!!m3lu! actionslensitgunstsensaisiperple3hannebshereforsthisi ._ 1 i

                                      *as s m w strictiveIchgnge; i

3-14 LS 29 Not applicable to CPSES. See Conversion Comparison Table l (Enclosure 3B). 3-15 M Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). l 3-16 A Not used{epglicabic to CPSES. Scc C;rvcraior, C.;,periser. T;ble x- m -002 n-.. -. 3M 4 The1CPSES;testrictjogs;bOpeDinglotithe:containeer!tiptessutelreljef 03n valvesy.sggir;found;jn;the: Radiation;nonitorjng3nstrtmentation specificatjon:ofithelCTSIsre; presented Jn;ITS%6;Eandithe!IIS ! Administr_ativCContrals Section%511 for;theMCME8gauseitMs3hange

only2elocates: 1nformationythin;thegechnicanspecitjeations7;and_no
technical 3hanges'are'jntroducedEthis change;1siconsidereditolbe l

administtativej CPSES Description of Changes to CTS 3N.3 21 10B088

              .             .       ._   - ..           .        -   - - _ = - _ - . . -       - .

l l ADDITIONAL INFORMATION COVER SHEET l l ADDITIONAL INFORMATION NO: O 3-17 APPLICABILITY: CP 1 REQUEST: The CPSES restrictions on opening of the containment pressure relief valves are moved from the Radiation Monitoring Instrumentation Specification in the CTS to ITS 3.6.3 and the ITS Administrative Controls Section 5.5.1 for the ODCM. Comment: I disagree that these changes represent moved items. The proposed l notes to 3.3.6 RA C.1 copies these allowances and restrictions. FLOG RESPONSE: DOC 3-17-A will be revised to reflect the ITS 3.3.6 Required Actions B.1 and C.1, as described in JFD 3.3-73. l l ATTACHED PAGES: Enci3A 21 1 Enci 3B 18 l ! i 1

_ - _ _ - . - _ - - - . - - . . - . .- - --. -.. - . . - ~ - - CHANGE NlABER HSE DESCRIPTION 3-10 LG Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38). 3 11 M The ACTION STATEMENT for an inoperable gareous radioactivity monitor 0 3 01 is modified to require that the inoperable channel be restored within 4 hours. If not restored, continued operation is permitted (similar to the current TS allowance) provided the containment [ vent isolation] valves are closed. The change is more restrictive or administrative in nature in that no time limits for the completion of any actions are specified in the current TS. 3 12 A Not Applicable to CPSES. See Conversion Comparison Table l (Enclosure 3B). 3-13 M The proposed change would provide an ACTION STATEMENT for the case where i the number of Control Room air intake radiation level instrumentation l channels was two less than required number of channels. The ACTION l STATEMENT would require that the air supply from the affected air intake , be secured or that the emergency recirculation mode be initiated and maintained. Otherwise, shutdown to MODE 3 in 6 hours and MODE 5 in the j l next 30 hours. Inithe; CIT 13;32MMjpnsiarKpmyidedifgt3pgi$hgpgg 0 3 13 inoperabJp;chaAneJEgoggDLW5;0jSitteWLdihplenteredsegyerRCT) 313.;3]Qcgjonfgjaig.wathgtthg grWisionsMfjSppcitigatig:3;0;3 are:not3ppMcablergfBgegft@Jhe~tameZac_t1pns?for29fOngpptgble l' channeDotRd;her;BipMgilfithere]saslaoreithanlont31poperabit3:hanneTJJ In.;the3TEithgM? statements;prov,fdsdlf_or;theltituation~)diateithere are morp3hanLongassWRIDCchgungis a!Esoreltestrictite3hanithe actionsystquired3nr3!h0MRable3hannelEghereforCthjs3hangeljs c]a.ssifjg~asf s'porpfgstrictly_e; change] 3 14 LS 29 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38). 3-15 M Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 3 16 A Not used! epplicabi- to CPSCS. Scc Cor.ncsicr. C scriser. T;bic DC ALL-002 n __ C .2_ ens w.~.un.. . ~ , . 3f12 A The:CPSES2estrictions enlopenjng;,of;the:containmentiptessure2elje- 0-3 U Valves:cuttent]Efstg!dljrilthe1 Radiation;MonitotjngJInstrumentation SpecfficatjonioD1heICTSlate: presented jnJTSJ;6.3;andithe;1_TS Adminfstrativ(controlsjection15;12critheicoCMasecapelthis change mir. relocates 3nfotsatjoojthinLthe3echnfce]ISpecLficationsRandino l [ technical l, changes 3re310ttoducedZthj gchangeli siconsideredito;be i admini.stratjve] CPSESDescription ofChanges to CTS 3M.3 21 10B088

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 18 Cf 22 TECH SPEC CHANGE APPLICABILITY DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK No Yes NeYes No 3 11 The C-PSES ACTION STATEMENT for an inoperable gaseous radioactivity monitor is 0-3-0) M modified to require that the inoperable channel be restored within 4 hours. If not restored. continued operation is permitted (similar to the CTS allowance) provided the containment [ vent isolation] valves are closed. The change is more restrictive or administrative in nature.in that no time limits for the cogletion of any actions are specified in the CTS. No - see No - see N/A No - see 3-12 Wolf Creek's use of the Applicability 'All" includes MODES 1, 2. 3, 4, 5. 6. and CN 3-04-M CN 3 04 M CN 3-04-M movement of irradiated fuel assemblies. No - See CN 3- Yes No - already No already in 3-13 The proposed change would provide an ACTION STATEMENT for the case where the 15-M in current current TS. M number of Control Room air intake radiation level instrumentation channels was TS. two less than required number of channels. The ACTION STATEMENT would require that the air supply from the affected air intake be secured or that the emergency recirculation mode be initiated and maintained. Otherwise, shutdown to MODE 3 in 6 hours and MODE 5 in the next 30 hours. Yes No No No 3-14 This proposed change adds an ACTION and allowed outage time of 4 hours for one LS-29 inoperable Containment Ventilation Radiation instrumentation or actuation channel to the DCPP CTS. Yes No No No 3-15 This change revises DCPP CTS ACTION 34 and adds new ACTION 36 to require M appropriate MODE changes or condition changes for the CRVS with one or two inoperable normal intake monitors. These actions specify a shutdown requirement for MODES 1-4 that is one hour less than LCO 3.0.3, and immediate action for l inoperability during fuel movement. Refer also to CN 03-08-M. CN 03-04-M and CN 3.3-51. hen /A NeN/A 3 16 Not used4!!S 3.3.5 for CC"" in;i da ';;;i,14 and ir'n;; ;~_... of ' r:di;^cd - VesN/A NeN/A bI!Nb N _II ""~ '.T ' I hI ,., b b ___ m

                                                    '"""'"~"""""""'"'"'"'"'"""'""~~""                                                                                                                                                                                                                                                                                                                l DC-ALL-0C2l
                    ".m".",.""..

T. . .'_. h, y. . _' ~ ^ No Yes No No 3 17 Jhe CPSES;restrjetions;on. opening of 2 the;containmentspressurelfelief3 velves A currentlyi found;in the3RadiationJtnitoting;InstruentattgCpecifiestierLof;the lQ-31 l CTStareh.MdndTS._3 6i31and 3 i theLIT3)lIsjnistratincontro]s;$ectionJ.5;1 _ [

            \        forethe:00CMi                                                                                                                                                                                                                                                                              #

w CPSES Conversion Comparison Table - CTS 3M.3 10BGM8

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 7-01 APPLICABILITY: DC, CP, WC, CA REQUEST: The requirements of current TS Table [3.3-9] are redefined on a functional basis with Required Channels. The point at which ACTION Statements are entered is unchanged. i l Comment: { [CP] Revise ITS T3.3.9-1 column to " REQUIRED NO. OF FUNCTIONS" ) FLOG RESPONSE: 1) The generic NSHC "A"(administrative changes) has been revised to better define administrative changes.

2) The CTS table markup has been revised as necessary to provide the correct column title.

DOC 7-01 A is revised to read as follows: The requirements of current TS Table [3.3-5) are redefined on a functional basis, ' with Required Functions, rather than on a per channel basis, consistent with other Section 3.3 tables in NUREG-1431 Rev.1. The point at which the ACTION Statements are entered is unchanged. [] j The conversion comparison table (enclosure 3B) is revised as follows to be consistent with DOC 7-01 A: The requirements of current TS Table [3.3-5) are redefined on a functional basis with Required Functions. The point at which ACTION l Statements are entered is unchanged. [] : 1 See also the response to Comment Number Q 3.3-24 for CPSES, WGCS and Callaway and 1 O 3.3-128 for DCPP. ATTACHED PAGES: Enct2 3/4 3-52 Enci 3A 21a Enci 3B 19 Enci 4 6

l l TABLE 3.3-5 REMOTESHUTDOWNMONITORING.b"U"EtHATIOd" _ o

                                                                                                     %B65tG1h i

t 1 1

MININWH REAB0F TOTAL h'O. C41ANNEG m--T"S"U"E!5 E0 GAT-10N OF-GHANNEM GPERABLE 6 Furfctions

1. Neutron Flux Monitors HSP 2 1 Wide Range RCS Temp. T, HSP WEeep 1/ Loop 2.

Wide Range RCS Temp.-Tn HSP 1/l::eep 1/ Loop" l 3. HSP 1 l 4. Pressurizer Pressure -1 O 1

5. Pressurizer Level HSP

6. Steam Generator Pressure HSP WSG 1/SG

7. Steam Generator Level HSP WSG 1/SG B-8,j Auxiliary Feedwater Flow HSP e/SG Rate to Steam Generator H e-ts 0 7 10

9. Condensate Storage Tank Level HSP 2 1

10. Charging Pump to CVCS HSP 1 1 Charging and RCP Seals -

Flow Indication 1 i HSP = Hot Shutdown Panel SG = Steam Generator The requirc ents Of "drdrer Ch=r.ch OPEPfSLE fer "id: R=ge RCS Tc p. T,

                                                                                                     ;1-31;A 4 ica.etc :hutdci.;n indication for Unit 2 cre rcviscd to 1/Leop for thrc; (2) of the four (4) RCS Leops. This rcvision is to ic=in in cffcct until CPSES Unit 2 caters tiOCE 4 at th; kginning of thc s=end refucling cutagc for Unit 2.

CPSES Markup of CTS 3M.3 3M 3-52 10BOM8

CHANGE NUMBER liS11C DESCRIPTION 4 01 R Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 5 01 R Not usedjepplicobic to CPSES. Scc Conscrsica Oc;;;porison Tcble (Encic;urc OS'. l Oc-a-op l 6 01 R Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 7-01 A The requirements of current TS Table r3.3 5] are redefined on a 0 7 01 functional basis, with Required Mnncl; Functionn) rather than on a per - channel basis, consistent with6her'. Sect 1on .s.s - ablesin 1UREG 1431 Rev.1. The int at which the ACTION Statements are entered is unchanged j] I CPSES Description of Changes to CTS 3N.3 lia 10B088

CURRENT TS 3/4.3 Page 19 cf 22 CONVERSION COMPARISON TABLE TECH SPEC CHANGE APPLICABILITY DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK 5;; M No M No NA g g 5 01 Not;used,0C"" LCO 3.3.3.3. 5;i;-i; :n;th..t; tion, i; rcl;;;ted t ; liann M(;; Ne a R _.;rcil;d d;m..t. !.'" ^5 07 Yes - See No No No 6-01 DCPP LCO 3.3.3.4. Meterological Instrumentation is relocated to a licensee Attechnent 21. R controlled document. pace 13. No - already in Yes Yes Yes 7-01 The requirements of current TS Table [3.3 5] are redefined on a functional basis 5 0-74 E with Required G Unctions Ehennels.3The point at which ACTION Statements are current TS. A entered is uncha g _/ No - already in Yes No - already No - already in 7-02 The shutdown requirement for inoperable Remote Shutdown controls is changed from current TS. in current current TS. H HOT STANDBY to HOT SHUTDOWN TS. N/A No N/A Yes N/A No N/A N 7 03 ';t 'J;;d. The CPSES listiof;functionsiptintided;bytthe, remote:shutdownfransfer l0-7-Onal LG switches,and controls,1simoved_to;the1Beses;j This change extends the Remote Shutdown A0T from 7 days to 30 days. No - already in Yes Yes Yes 7 04 current TS. LS 15 Yes Yes No - already No - already in 7-05 Consistent with the ITS. the modifications would clarify the requirement to be in HOT SHUTDOWN in 12 hours by replacing the requirement with a new requirement in current current TS. A TS. to be in HOT STANDBY in 6 hours and in HOT SHUTDOWN in the next 6 hours. Yes Yes Yes Yes 7-06 The Readout Location and Total No. of Channels columns in current TS 0-7-00 l LG Table [3.3-5] have been moved to the Bases of improved TS 3.3.4. {-} N/A N/A N/A N/A 7-07 Not used. No Yes No No 7-08 The CPSES requirement to submit a special report if the number of remote TR-2 shutdown monitoring instruments is less than the required number would be deleted from the CTS. This requirement is covered by other regulatory requirements. Clarification is provided that Channel Checks are only required for normally Yes,Ne- Yes Yes Yes 7-09 0-74 l LS 43 energized instrumentation channels by adding "for each required instrumentation retetned channel that is normally energized *, per ITS [SR 3.3.3.1 and SR 3.3.4.1] to cu rcnt TC. CTS [4.3.3.2.1 and 4.3.3.3.a]. CPSES Conversion Comparison Table - CTS 3M.3 IW3MF8

l III. GENERIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS "A" 10 CFR 50.92 EVALUATION FOR ADMINISTRATIVE REFORMATTING AND REWORDING 3 I _ . _ strative:changesIareRchanges3 hat;doJot3ffectioperatigg MarltsMaanner in' Wirichltheylantj sleperatedJeig;Zsimp]elre3sording Tolthe]lSgde]etion;ota T5;Whoselapp1 tcability;haslexpired deriuhtch]duplicatesygulattN7arlether 0701 requirements cot; wordy:hanges;to'Jacorpatateza :pteviougasplicit ynderstandi ofjtheR%ts These? proposed TS revisions includes /efoi m my anu reworoing he e m4uirements in accordance with the NUMARC Technical Specification Writer's Guide and the improved Standard Technical Specifications in NUREG-1431. l This is intended to make the TS more readily understandable to plant operators and other users. Application of the Writer's Guide will also assure consistency between specifications. During this reformatting and rewording process, no technical changes (either actual or interpretational) were made to the TS unless they were identified and justified. This proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

                "The Comission may make a final determination pursuant to the procedures in 50.91. that a proposed amendrnent to an operating license for a facility                    i licensed under 50.21(b) or 50.22 or for a testing facility involves no                     l significant hazards consideration. if operation of the facility in accordance               \

with the proposed amendment would not: 1 Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or d1fferent kind of accident frorn any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed change involves reformatting and rewording of the current Technical Specifications. The reformatting and rewording process involves no technical changes to the current Technical Specifications. As such, this CPSES No Significant Ha:ards Consideration - CTS 3N.3 6

i f ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 7-08 APPLICABILITY: CP REQUEST: The CPSES requirement to submit a special report if the number of remote shutdown monitoring instruments is less than the required number would be deleted from the l CTS. This requirement is covered by other regulatory requirements. Comment: CTS reporting requirements are deleted without a supporting NSHC evaluation and without explaining why existing requirements should be relaxed. In l ! addition, CTS requirements for TS actions based on less than the total number of l channels operable are deleted without explaining why existing requirements should be relaxed. I FLOG RESPONSE: NSHC designated TR-2 is added to Enclosure 4. l ATTACHED PAGES: l Enci 4 2,69, and 70 l l i i e 1 i l l l : l ; 1

NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC) CONTENTS (continued) LS 3 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c abl e LS 31. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not appl i cabl e LS 32. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e B -33..................................................... mm. .rr . 2. _.a,. w_,Ja 0 2 25 LS 34 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i c abl e LS 3 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e LS 3 6 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not used v--yy '. '. wo"u'. .. CA 3.3 009 LS - 3 7. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not eppl i cabl e LS 38..............................................Not used o-ry.wo"'i.- CA 3.3-002 LS 39.............................................................. 61 LS 40.............................................................. 63 LS 41. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 42 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . Not a ppl i c abl e LS-43................................................................... 65 w 3 u st21stA* 31.bm-mm..en-nnmn m n.-m &. L<Cabie 0 3.3.3 unu ununwaruurw.m .nw-wn.s uNot~ app 11c. .abl e. L.S. J. 5n e mv,.nL,u1*ner n. emyn=wyme* ?4rs

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7wy-m%,w em mwnn - * * -unn.m ununum~"u."nu.un*z'e'"u uuz m m" ~ 6.9 CPSES No Significant Ha:ards Consideration - CTS 3/4.3 2

1

v. RECURRING Ll0 SIGNIFICANT HAZARDS... CONSIDERATIONS 0708 NSHC]R-2 i 10RR;50.,92;EVALU6 TION l F_0R RECURRDlG TECHNICAL CHANGES lMIMPOSE;LESS:ltESTRICTIVE l

REQUIREMENISiWIMINJEEIECHNICAliSPECRICATIONS ik!EghangelttaccorD!se ldBll1RREN;WM"ilL&ementathsgrirement forla guessE.m.&toemeneratetantmenttend0tomacLeitche:mc wf11;be ; dl5EN1rD88phe3!sst1ML!iengsmatotizeCa liogw!disap 4 IlllOEUP88!L d 3EcheggChasMepig!ahuttedlantitihasl)een;detageiged;that;ttJnvolves l 1 nosentricentjazarete;fgThis determination:has:seenerformed in accordance1with:thelM: sat"fatth;1:130 CgiS0192(c1Eas;quotedibelow: ThelCamtss]OLWMO1lna]ldetermination::pucsuant:to the; procedures in 50.91Et%t:a; proposed:amendnent^to:an:operatlng:licensefor:a facility l.1censeu;under;50.21HbLOCL50:22*or'focla: testing; facility;1nv01ves no sign!ficantl hazards " consideration;"3(, operatlon ~of the;fac1litylin 'accordance With;the; proposed Jamendnentpould notl l' Involve:a:significant2ncrease:1n;the~probabilitylor; consequences of an accl dent 3nrenous]f:eva.luated, Toc

2) Create:ttlelpossjbLL1ty:oLa:new pcLdifferentlind of accident from; arty accf dent ~ previous]y:eya luated[or:

3; Involvela~signi ff cant:reductionitn1 margin:ofisa fety.1 The70110winglevaluatLonfsjprovided for*the:threeicategoriesiof the significant hazards 7 consideration".standardsj 1 Doesithe~changelinvolve alsignificant; increase;in the" probability;or l consequencesioflan.laccidentlpreviously evaluated? This; change; W purelylan' administrative ~ reporting changeland;cannot affect any accident probability:or' consequences? ,

2. DoesJ he: change; create;the' possibility.of..a;new or different kind of accident]from:any: accident;pr_eviously: evaluated?

l 1 l This. changejs;purelyjan administrative;. reporting' change and .cannot create. any i new accident _orlaffect any. accident;previously evaluated. L I t CPSES No Significant Ha:ards Consideration - CTS 3N.3 69 103088

                          .        .                         . _ -          .              . = -

l IV. RECURRING NO_SIGNIFICMT HAZARDS _ _ CONSIDERATIONS l l NSHC'TR 2 (. continued) 3.. Doesi.thisichangelinvolye X signif_icant reduction;1n;aisargin.of 0 7-08 safet$ I l ThisichangejsM]ylanladspfstrativefeporting', change;and doesJiotfaffect j an.y;marginiofisafety] IEZECZg!N0lSIGNIUCSOMutsnJGEIDERATION. DEIBMINRION f sesed;on;the;above evaluation 11t*is; concluded;that3heiactivitie.s: associated with ! NShEjlRi2";resu]tintfrom_thelon_versiondto3hejaproved]Slormatisatisfy theino significant_ hazards;oonsider_ation;st_andardslofl10 CFR;50.92(c);1and~accordinglyllafno

         $1gnificant hazards"consideratfogiffnding;1s" justified!

l l l l l l I i i i CPSES No Significant Hazards Consideration - CTS 3M.3 70 10B0/98 1 f I

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 7-08a APPLICABILITY: CP REQUEST: Unevaluated change Comment: CTS 3.3.3.2.2 LCO item 5 for " support systems required for the above l functions" is deleted without explanation. Provide a safety basis justification for relaxing CTS requirements. Based on 8/14/98 meeting Rev 0 is accepted. FLOG RESPONSE: The CTS markup is being revised to move the words "for 1) reactivity control,2) RCS pressure control,3) decay heat removal,4) RCS inventory control, and 5) support systems required for the above functions" to the bases for ITS 3.3.4. New DOC 7 LG is provided to describe and justify the change. 7-03-LG reads as follows: The list of functions provided by the remote shutdown transfer switches and controls is moved to the Bases. This list is merely clarifying information for the remaining LCO which specifies that the required remote shutdown transfer switches and controls be OPERABLE. i ATTACHED PAGES: Enct2 3/4 3-50 Enci 3A 22 Enci 3B 19 I Enci 5B B 3.3-146, B 3.3-146a, B 3.3-148 and B 3.3-152 l l l l 4

INSTRUMENTATION 1 63 A Q 1 A GEN REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION i 3.3.3.2.1 The Remote Shutdown monitoring instrumentation chenaci; functionsjshown ggg in Table 3.3 5 shall be OPERABLE. 3.3.3.2.2 The remote shutd=n transfer switches and controls of svsta 7,g3,gg en=nnnents cquired for 1; rc;ctivity control. 2) RCS pics;urc centrol. 2) dcca^ I ' 0 7-08a C=fcessel, 4) RCS inventory gentrol, ;nd 5) ;;ppert systc;; required fcg function;fshall be UPLHABLE.

                                                                     ~-       ---       -

APPLICABILITY: MODES 1. 2. and 3. ACTION:HNptel;? Separate? ACTION'e_ntrjQslal_]_owedJgrieachTunctioQrldirequiredltSB ;14tg 3 !E.controQ

a. With the number of OPERABLE remote shutdown monitoring channels less than the tiinimu; Chenacis OPEPXLE as required by Table 3.3-5, restore "7-04-LS1 the inoperable channel (s) to OPERABLE status within 7 30 days, oribe in; HOT _ STANDBY;within;theinext;6; hours;and be in H0T SHUTDOWN within 17-05 A 1 the next M 6 hours.

b. With the nu;bcr of OPE"J.SLE reeste ;hutdown eenitorini; chenacl; ic;s g7.gg.TRA th;n the Total Numbcr of Chr.ancis ;; rcquired by T;bic 2.3 5. within 50 d;y: resterc the inepcr;bic channcl(s) to OPEPO LE ;tetu; cr. pur;u;nt to Spccific; tion 5.0.2, ;ubmit ; Special Ecpert th;t dcfincs the correctivc ectica to bc tek n.

c. With one or more Remote Shutdown transfer switches, power, or control py.ggst circuits inoperable, restore the inoperable switch (s)/ circuit (s) to OPERABLE status within 7 30 days, or be in HOT STANDBY within the next byggq M 6 hours andKSillTDOWN:91th_ini,thp fo))otti_ngKhoug.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE

a. At least once per 31 days bi performance of a CHANNEL CHECK;pteach *7-09-LS~'

required _ instrument 3:hannellthat3sinormally; energized, and

b. At least once per 18 months by performance of a CHANNEL CALIBRATION.*

3M 3-50 10/3088 CPSES Markup cf CTS 3M.3

CHANGE NUMBER RSEC DESCRIPTION 7 02 H With Remote Shutdown required controls inoperable, the shutdown requirement is changed from HOT STANDBY in the next 12 hours to HOT STANDBY in the next 6 hours and HOT SHUTDOWN in the following 6 hours, consistent with NUREG 1431. 7 03 LG Not Und. The3,tstVifunctions3rovjded byXremote g,, sht!tduin M _ 6,.2andjxuptrols~1s;3lL3edM,3he same#23Ms3942pu!reiricMtgnes11aginettiairst t>CtsmM!!1mrDDBM!$hM1glr1lhetK*jgqged=gesete P9BE90L6Meetgr$1s#REiRNRJ. 7-04 LS-15 This change increases the number of days the Function (s) in current TS Table [3.3 5] and the [HSP] controls may remain inoperable before imposing mode change requirements from 7 days to 30 days. This is based on operating j experience and the low probability of an event that would i require evacuation of the control room. This is j consistent with NUREG 1431 Rev.1 (ITS 3.3.4 Condition A). l 7 05 A Consistent with the improved TS, the modifications would ] clarify the requirement to be in HOT SHUTDOWN in 12 hours . by replacing the requirement with a new requirement to be l in H0T STANDBY in 6 hours and in H0T SHUTDOWN in the next ! 6 hours. l r l 7 06 LG The Readout Location and Total No. of Channels columns in l l l current TS Table [3.3 5] have been moved to the Bases of improved TS 3.3.4, consistent with NUREG 1431 Rev.1, {-1 o.7,06 l 7 07 - Not Used. t 7 08 TR 2 The CPSES requirement to submit a special report if the l number of remote shutdown monitoring instruments is less than the required number would be deleted from the current TS. This requirement is covered by other regulatory requirements. 7-09 LS 43 The current TS require that CHANNEL CALIBRATIONS are l ! performed for instrumentation used in the Post Accident Monitoring [and Remote Shutdown] Systems on an 18 month l basis. Some of these instruments are then de energized i l and remain in this state until re energized for use in the management of plant events or for the performance of the CHANNEL CHECKS. CHANNEL CHECKS are performed more frequently than CHANNEL CALIBRATIONS for the purpose of detecting gross channel failures or excessive drift of one channel relative to other channels monitoring the same

 -                                       process variable. During the period that the channel is de energized, it is not subject to the failure mechanisms or conditions that typically lead to instrument failure or excessive drift. Recognizing that de energized channels CPSES Description of Changes to CTS 3M.3                   22                              10B088

CONVERSION COMPARISON TABLE - CURRENT TS 3/4,3 Page 19 cf 22 APPLICABILITY TECH SPEC CHANGE DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK NA Yc; Scc M:Ne NA No NA 5-01 Not used,00~' LCO 3.3.3.3. Scis;ic In:tr-..tttica is rciccatcd tc c 'im.ucc Ne lDC-ALL-004lr ! LN ^5 07 R ccatrclicd dcc _ ..t Yes See No No No ; 6-01 DCFP LCO 3.3.3.4, Meterological Instrumentation, is relocated to a licensee Attachment 21. , R controlled document. page 13. No - already in Yes Yes Yes 7-01 The requirements of current TS Table [3.3-5] are redefined on a functional basis [0-7-0 l~- with Required Functions Ch;.c.ci;. The point at which ACTION Statements are current TS. A entered is unchanged. [ ] No - already in Yes No already No - already in i 7-02 The shutdown requirement for inoperable Remote Shutdown controls is changed from in current current TS. current TS. N HOT STANDBY to HOT SHifTDOWN TS. M/A No N/A Yes N/Apio M/A 7-03 kt Uscd. The.CPSESLlist:of functions 2 2provided by.the remote shutdown; transfer 0 7-Ohal g switches.end controls;is.aoved,to;theiBasesd J No - already in Yes Yes Yes 7-04 This change extends the Remote Shutdown A0T from 7 days to 30 days. current TS. LS-15 Yes Yes No - already No - already in 7-05 Consistent with the ITS, the modifications would clarify the requirement to be current TS. in current A in HOT SHUTDOWN in 12 hours by replacing the requirement with a new requirement TS. to be in HOT STAND 8Y in 6 hours and in HOT SHlITDOWN in the next 6 hours. Yes Yes 7 06 The Readout Location and Total No. of Channels columns in current TS Yes Yes 0-7 4 l LG Table [3.3-5] have been moved to the Bases of improved TS 3.3.4. E--} N/A N/A N/A N/A 7 07 Not used. No Yes No No 7-08 The CPSES requirement to submit a special report if the number of remote TR-2 shutdown monitoring instruments is less than the required number would be deleted from the CTS. This requirement is covered by other regulatory requirements. Yes,Ne-- Yes Yes Yes 7-09 Clarification is provided that Channel Checks are only required for normally 0-7-0(~ l energized instrumentation channels by adding "for each required instrtmentation rete +ned LS-43 channel that is normally energized *, per ITS [SR 3.3.3.1 and SR 3.3.4.1] to cw . cat TS. CTS [4.3.3.2.1 and 4.3.3.3.a]. 103088 CPSES Conversion Comparison Table - CTS 3H.3

Remote Shutdown System B 3.3.4 B 3.3 INSTRUMENTATION B 3.3.4 Remote Shutdown System BASES BACKGROUND A safe shutdown condition is defined as MODE 3. With the unit in MODE 3. the Auxiliary Feedwater (AFW) System and the steam l generator (SG) safety valves or the SG atmospheric dump meljef valves (AD":0 M s} can be used to remove core decay heat and meet all safety requirements. The long term supply of water for the AFW System and the ability to borate the Reactor Coolant System (RCS) from outside the control room allows extended operation in MODE 3. If the control room becomes inaccessible. the operators can establish control at the rc; cts HotjShutdown Panel, and place and maintain the unit in MODE 3. Not all controls and necessary transfer switches are located at the rcrete - Hot CP-3.3-009 Shutdown Eanel. Some controls and transfer switches will have to be operated locally at the switchgear, motor control panels, the3)utdow[ttansferlpanel or other local stations. The unit automatically reaches MODE 3 following a unit shutdown and can be maintained safely in MODE 3 for an extended period of time. The OPERABILITY of the feHowife- required; remote shutdown 0 3.3 24 l cortrols and theLfollowipg] instrumentation functions ensures there is sufficient information available on selected unit parameters to place and maintain the unit in MODE 3 should the control room become inaccessible. The l cp.3.3 002

                          'teadoutHocationlfortheselnst_ruments'jfatithelHo,t Shutdow[~ faye 13HSP)]

The corttrols;11nstrumentationzanditransfe. r; switches 1are requiredfori i Core; reactivity;controli(initial;and long :ters) : i RCSjpres)urejcontroh 0-3.3 24

                             ;    Decay heat + removal'yia;.thefAFW System and the SG             - - - -

H 0 7-08a

                                                                          ' ' ' " ' ~ '

s.afetfvaihUjr]SdfRVs;Tand i RCSJjnventory;controli l (continued) I l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-146 10B088 l

Remote Shutdown System B 3.3.4 BASES

l

                           . SafjtymestmMthC4 hove:Tianctions Tiincleting                                  I seDEh!s_MER!!r29Lupa!!a&g!p1 Meter;MansttLM idl}jg, WM                                                                                l Fwhme?iFg MELW3                                                                                                                I TEME&smMS"G                                                                                                         J F:3IKAL~R :                                                          1 BEMK9ENT                    Z"EfEtlHWELS                                                         ]

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I I J i i J (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-146a 10B088 , l ! i

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r __ ,___ .. _L____, ., _ _ . . _, no. rn .n, v wivtu m u. s vi .y v. w. .w ... .u . p N . w. u.sy W. ..L. .w. u own i m - -- ir.'cr== - car. trol or - i:; ^"T.y.v'"' " 7.requi.re.d; controls - - argspedfiedJ[gefe!ygef The remote shutdown instrument and control circuits covered by this LC0 do not need to be energized to be considered OPERABLE. This LCO is intended to ensure the instruments and control circuits will be OPERABLE if unit conditions require that the Remote Shutdown System be placed in operation. (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 8 3.3-148 10/30/98

i Remote Shutdown System B 3.3.4 BASES cxprienc; and ;;nsistency with the typical industry rcfueling cut;;;. REFERENCES 1. 10 CFR 50, Appendix A, GDC l and 19.

                                              *j                                              0 7-08a I

i l l I (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-152 10BOM8

                           . - - -             .- -               -       . - -   .-     .          ~   .- - . -

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-122 APPLICABILITY: DC, CP, WC, CA REQUEST: ITS 3.3.1 AppEcability Note (b) for Functions 1,5,19-21 and Conditions C and K are revised to replace Achons requiring the RTBs to be opened with actions that ensure subcriticality is maintained (i.e., by fully inserting all rods and ensuring the rod control system is incapable of rod withdrawal) yet do not initiate a feedwater isolation (P-4 and low T ) in MODE 3, consistent with traveler TSTF-135. Comment: ITS T3.3.1-1 Note (b) can be accepted with modification by replacing "all rods not inserted" with "one or more rods not fully inserted." FLOG RESPONSE: The FLOG will adopt TSTF-135 Rev. 3, as discussed in response to Comment Number 3-LS-GEN. Footnote (b) to ITS Table 3.3.1-1 has been revised per the above, as indicated in the pages attached to 3-LS-GEN. In addition, NSHC LS-39 and the ITS 3.3.1 Condition C and K Bases have been revised to indicate some possible methods to ensure the Rod Control System is rendered incapable of rod withdrawal. ATTACHED PAGES: Enci 4 61 _

Enci5B B 3.3-38 and B 3.3-44 l ,

I i 1 { l

t l ! i l 1 i i 3

IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-39 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES E AT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Applicability Note [a] and ACTION Statements [5 and 9] for Functional Units a26e [1, 6-b-g3]R1,19, and 20] of current TS Table 3.31 are modified to provide an alternative to opening the reactor trip breakers (R1Bs) while still assuring that the function and intent of opening the RTBs is met. As currently worded, these ACTION Statements result in a feedwater isolation signal (FWIS) when in MODE 3 with a Tm less than [564*F.] A more generic action, which TR 3.3 006 ggl3Ni@tlactionEbeEtakgggjassures the rods are fully inserted and cannot be withdrawn, replaces the specific method of precluding rod withdrawal. The revised Applicability and ACTION Statements still assure rod withdrawal is precluded. This change does not involve any safety impact and is consistent with traveler TSTF 135. The proposed change allows more freedom in how rod withdrawal is precluded and is thus less restrictive. However, the intent of using physical plant characteristics to prevent rod withdrawal is not diminished. The specification now acknowledges that the Rod Control System can be e_f_Lectlygly_. disabled by means other than opening tgjgMbfdefenstgi_zir$QillMs;MJ ^ 03.3122l

       @MCT06%d= vspo tthEEmotor;MLelL11t0MHGEsetj.

This proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

                "The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated: or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed change does not alter the requirement to preclude rod withdrawal using physical plant characteristics. The specification does not allow administrative control or other means which could be conceived as less CPSES No Signljicant Ha:ards Consideration - CTS 3N.3 61 103088

     --    .-            .-                =- - - - _ . -                 . . .  -      --      . _- . . _            __ -

RTS Instrumentation B 3.3.1 BASES 1 h;ur t; egn the REs are reasonable, based on operating experience, to reach MODE 3 end egn the R5s from full m 3.3 oos power operation in an orderly manner and without challenging unit systems. With tre R"s egn end the unit in MODE 3 this trip

                              --        _ furetien

_ _ is_n; _lengr _ 7;_quired to bc 0

                                                                                .,"E"ZE.          _g.       g 63EMCERd WMbLl'h1.,..
                                    !            .        2   6 tl8R 14 @ lMetMi.

C.1-end C.2XakiMlb1SJ2 3.3 0 6 Condition C applies to the following reactor trip Functions in MODE 3, 4, or 5 with the R"s cissed :nd the CR0 (tod Control System capable of rod withdrawalter ;]'~rrie;orlooreZrods notifu1]yH!fse_rted:

                              .      Manual Reactor Trip:

RTBs:

                              .      RTB Undervoltage and Shunt Trip Hechanisms: and
                              .      Automatic Trip Logic.

This action addresses the train orientation of the SSPS for these Functions. With one channel or train inoperable, the m 3.3 cos inoperable channel or train must be restored to OPERABLE status within 48 hours. If the affected Function (s) cannot be restored to OPERABLE status within the allowed 48 hour Completion Time, the unit must be placed in a MODE in which the requirement does not apply. To achieve this status, R$jgigg l within the next hanc

b prov1 s sufficient

                            '6une w accomphsn tne action              a in an orderly manner. 'Jith the R"s egn, M 4                  v.,.,.<c.s   hese Functions are no longer required, 4

The Completion Time is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to perform the safety function, and given the low probability of an event . occurring during this interval. continued ,, CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3 38 JMM8 i

h i l l I RTS Instrumentation ) B 3.3.1

 '                                                                                                                                                                                                                                                            I BASES System capable of rod withdrawal                                                                          -
                                                              ,g.1m Nr With the unit in this Condition, below P 6,                                                                                                                                           ;

the NIS source range performs the 7.~ nit r ing i.ad protection TR 3.3 006 functions. With one of the source range channels inoperable. 48 hours is allowed to restore it to an OPERABLE status. If the channel cannot be returned to an OPERABLE status. MLo! Din c ' C M ? W o ; 1- .- 4%'<tiCA p]gLNglg.1 additional hour is allowed to .# .: ; 4 y WEgg 0 3.3 122 i

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arc egn, the core is in a more stable condition. and the unit cater:; Cenditics L. The allowance of 48 hours to restore the channel to OPERABLE status, and the additional hour to egn the 6 11lfG!BMH!0EDG!$fplSMe0BO ccMitfortgapabEg390f1thonsan are justified in Reference 75 I e ._J E e

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vvibeaaes a s svu s ussw w tbb ywa ".th s avus a us b ww w%s ma vys s u b i sy . (continued) 9 CPSESMarkup ofNUREG-1431 Bases -ITS3.3 .B 3.3-44 10B0A8

l , ADDITIONAL INFORMATION COVER SHEET l-ADDITIONAL INFORMATION NO: Q 3.3-125 APPLICABILITY: CA, CP, DC, WC

REQUEST: ITS SR 3.3.1.11 is modified by a Note that requires verification that the time constants are adjusted to the prescribed values. The addition of this Note is consistent with SR 3.3.1.10 and is required because SR 3.3.1.11 is used for the Power Range Neutron Flux -

High Positive Rate [] trip function which has a time constant associated with its calibration. Comment: SR 3.3.1.11 is applied to several functions that do not include time constants. Would it be better to reference SR 3.3.1.12 in these cases? t FLOG RESPONSE: SR 3.3.1.12 is not desired for this purpose since none of the FLOG plants have RTD bypass loops. i ATTACHED PAGES: None

                                                                                                                        .                t t

I 4 l

l. .

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-130 APPLICABILITY: CP REQUEST: Consistent with the current TS and the CPSES design, the Conditions, Required Actions and Surveillances are not applicable to the 6.9 kV Preferred Offsite Source Undervoltage function if the associated source breaker is open. When the associated source i breaker is open, credit is not being taken for the immediate availability of the 6.9 kV Preferred l Offsite AC power source. Comment: Show how this proposed allowance is provided in CTS. LOP instrumentation supports LCO 3.8.1 circuitry. ! l FLOG RESPONSE: CTS Table 3.3-2, Functional Unit 8a, footnote "f" provides the allowance j described in the Request. However, as agreed upon at the " September meeting," the relevant ! Note is more appropriately applied to the APPLICABILITY. l l ATTACHED PAGES: Enci5A 3.3-53 Enci5B B 3.3-156 i Enci 6A 14 Encl 6B 20 , i l i l 1 i I, i I

LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation

3.3 131 Q-3.3 131 LCO 3.3.5 Thee ]g channels per bus of the icss ;f volt;;; M Function and thee M channels per bus of the degraded voltage .;_lf Function shall be OPERABLE.

APPLICABILITY: MODES 1, 2. 3, and 4,

                                      .,<__...__2.m._n,
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0-3.3 130

                       .22: htf6%&?h?M%"MtMMMsh"-:-MM "- - - ' " - -F - ~ ~ t -'-M" ACfIONS
        ..................................... NOTES----- ----- -------- --- - --- - - -                                                                      <

g eparate Condition entry is allowed for each Function. 3.3-130 m ~_ _ =- 0 3.3 130 m CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 L'0TF. with one channel per bus The ir,c+crabic ch;nn:1 acy inoperable. be b>T, ssed for up to 4 hours for urveillance tcsting ;f other chenacis. Place channel in trip. 6 hours 1 CPSESMarkup ofNUREG.1431 - ITS 3.3 3.3-53 10/3088 l . . .. .

LOP DG Start Instrumentation , B 3.3.5 l l BASES j i ( p,crfor; its f;.r.cticr. cr. cr. LO" er igrcid i,;.;cr to the vitcl i l h ! mesm-neswheransnarahnermea liEGiBIBFMMWitLage 3.3 130 at00rce2reate61$ c3 Sed: men - Wfsttt1501t30e i 3 s20W E M & W E 1t MEEatem!!EBIDIRLetstigsmytarr21N90MCDictEettg sone 3n!kss!!!seasetter:msDat3 squired ~texge ; ACTIONS In the event a channel's Trip Setpoint is' found nonconservative with respect to the Allowable Value, or the channel is found inoperable, then the function that channel provides must be declared inoperable and the LC0 Condition entered for the particular protection function affected. Because the required channels are specified on a per bus basis, the Condition inay be entered'sbparately for each bus-as appropriate. A Note has been added in the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in the LCO. The Completion Time (s) of the inoperable channel (s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

n..--___ -. g, - g 7_ .

                           ~ ~ - - ~ ~ " * ' * " " - " " '

o.3.3 130 j Ll Condition A applies to the LOP DG start Function with one 0 3.3 131 l inninnini,iisss of voltcg; Mor[one degraded voltage l channel per bus inoperable. l l (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-1S6 10 BOA 8

 .  . ~.         _   _-                - . _ .      _ _.- _         _ - - . -          _ - - _ _ - -              - . - .   - _ -    __

CHANGE NUPBER JUSTIFICATION j l automatic loss of power DG start instrumentation to be operable in these modes. 3.3 130 Consistent with the current TS and the CPSES design the- 0 3.3-130 C.,~ . . .... . . ,, a i x, ,; er.; wr edll er.;;; ;r; T_ not applicable to the 6.9 kV Preferred Offsite Source Undervoltage function if the associated source breaker is open. When the associated source breaker is open. credit is not being taken for the immediate availability of the 6.9kV Preferred Offsite AC power source. i 3.3 131 TS Condition B is replaced with new Conditions B. C. D, and E. Condition C in the ISTS is changed to Condition F. The CPSES current TS have l specific actions for the various bus undervoltage and degraded voltage function. These actions allow an appropriate amount of time to restore an inoperable channel or declare the associated power source or bus inoperable and take action to isolate an inoperable power source. These j actions are a proper way to respond to the inoperable channels because the l actions result in taking the Required Actions in ITS 3.8 associated with the affected power source or bus. The new Conditions match the Actions of the current TS. ; 3.3-132 The trip setpoints for the loss of power diesel generator start . , instrumentation are moved to the Bases. This approach is consistsnt with a format allowed by a reviewer's note for the RTS and ESFAS ' instrumentation. 3.3-133 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 134 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 135 A H0DE change restriction has been added to ITS 3.3.1 Condition C per the matrix discussed in CN 102 LS 1 of the 3.0 package. (See the LS 1 NSHC in CTS Section 3/4.0, ITS Section 3.0 package). 3.3 136 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). g ..; j 1 , g ., . . A c, qn 4;n , , _.s ; ,- ..; a, .

                                                                                                        '9                cA 3.3-012 a,99 g

. M,mg L .; cp - .; -

                                                                                            ...,.. . , , . . j y.

CP 3.3-003 gemeistsacREEIRT.foGntt g ; w. 4 :;i t t.y EEER NetGlill110b1MDEE5FE.T$ enc 50g!t31NGCoglEISBEnh19 oc n 002 EOCM515958)1 M ""*"h1 cA 3.3-007 i N ; CPSES Dsferencesfrom NUREG-1431 -ITS 3.3 14 10B088

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3 Page 20 cf 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-128 This change revises ITS Table 3.3.4-1 to be consistent with Yes No No No DCPP CTS 3.3.3.5. 3.3-129 Consistent with the CPSES current TS the ITS requirement No Yes No No to have the Loss of Power Diesel Generator Start Instrumentation (ITS 3.3.5) applicable in Nodes 5 and 6 when the associated DG is required to OPERABLE by ITS LCO 3.8.2 "AC Sources - Shutdown" is deleted. In these modes. the Reactor Coolant System or Reactor Vessel cavity temperatures are low enough that the time available for the reactor operators to manually start the diesel generators is adequate. Thus, there is no need to require the automatic loss of power DG start instrumentation to be operable in these modes. 3.3-130 Consistent with the current TS and the CPSES design, the_ No Yes No No 6ditim:. ";g.i cd "ctie- =d S;. cwa . ;..- ;rc p;0;tisl _ ,_._ _ _ _ , . . . . _ . . _ _ , , , , _ _ _# EQ-3.3-13 p l not applicable to Ine 0.9 Kv Pf% .cu Cir..;u Loi m # Undervoltage function if the associated source breaker is open. When the associated source breaker is open, credit is not being taken for the imediate availability of the 6.9 kV Preferred Offsite AC power source. 3.3-131 ITS 3.3.5 Condition B is replaced with new Conditions B. C. No Yes No No D. and E. Condition C in the ISTS is changed to Condition F. The CPSES current TS have specific actions , for the various bus undervoltage and degraded voltage function. These actions allow an appropriate amount of time to restore an inoperable channel or declare the associated power source or bus inoperable and take action to isolate an inoperable power source. These actions are a , proper way to respond to the inoperable channels because the actions result in taking the Required Actions in , ITS 3.8 associated with the affected power source or bus. The new Conditions match the Actions of the current TS. i e CPSES Conversion Comparison Table -ITS3.3 10B088 4 s gegy-3.w 4m.e- eh_ k *#'

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-131 APPLICABILITY: CP REQUEST: ITS 3.3.5 Condition B is replaced with new Conditions B, C, D, and E.

Condition C in the ISTS is changed to Condition F. The CPSES current TS have specific l actions for the various bus undervoltage and degraded voltage function. These actions allow l an appropriate amount of time to restore an inoperable channel or declare the associated l power source or bus inoperable and take action to isolate an inoperable power source. These actions are a proper way to respond to the inoperable channels because the actions result in taking the Required Actions in ITS 3.8 associated with the affected power source or bus. The new Conditions match the Actions of the current TS. Comment: LCO 3.3.5 is constructed to ultimately declare the affected offsP.1 circuit I inoperable if LOP instrumentation is inoperable. As such, proposed Actions Note 2 and I the addition of proposed actions to declare the offsite source inoperable and open l breakers should only be required if iSTS action B.1 is not met. Explain why the iSTS l cannot be adopted. l l FLOG RESPONSE: As described in the response to Q 3.3-130, the Actions Note 2 is more . appropriately applied to the APPLICABILITY. The STS can not be easily adopted due to the unique nature of the CPSES design. The ITS markup provides the best application of the STS format to the CPSES design. The CPSGS design consists of 2 required offsite power sources per unit. Either power source is capable of 4 providing offsite power for both units. On a unit-specific basis, one source is designated as the preferred offsite power source, and the other is designated as the altemate offsite power source. Both power sources have redundant undervoltage relays upstream of the 6.9 kV Class ; 1E electrical distribution buses. If the " preferred" offsite power source was lost, the 6.9 kV l Class 1E buses would be energized by the "altemate" offsite power source. Only if the transfer the alternate offsite power source failed, or if the altemate offsite power source was also lost, would a signal be initiated to start the diesel generators. Therefore, if the preferred offsite power source was inoperable, it is acceptable to isolate it from the Class 1E buses and rely solely on the attemate offsite power source. As agreed upon at the " September meeting," some changes to the CPSES ITS markup are made to improve the clarity and consistency of the LCO and Required Actions ATTACHED PAGES: Enci 2 3/4 3-29 EnclSA 3.3-53,3.3-54 and 3.3-55

Enci5B B 3.3-153, B 3.3-153a, B 3.3-155, B 3.3-156, B 3.3-157 and B 3.3-158 4

4 1

TABLE 3.3 2 (Continued) ACTION STATEMENTS (Continued) ACTION 23 - a. With the number of OPERABLE channels one less than the Total Mumber af Chancis, operation may proceed '.r provided the inoperable channel is placed in the tripped condition within 6 hours, ad th; "ini;;; C5 ='- f: EPXLL c;quirs;.nt is .ct-~ -- 3 31 i

b. With the number of OPERABLE channels gless than the l M4Metst-gejgqMChannels 0"E"XL r;quir;nat.3tggtgggggagp;pg I declare Preferred Offsite Power inoperable, take the Action required by Specification 3.8.1.1 and open the 2 32 LS Preferred Offsite Power Breaker within 6 hours % 0-3.3 131 Y19.581 -

c. With the number of OPERABLE channels gg less than the M4Mous-gggjgggChannels 0"E"XLC r;quirgnat,6 declare Alternate Offsite Power inoperable, take the Action required by Specification 3.8.1.1, and open the 2 32 LS ternat ite Power B n 6 hours

                                                                                                                                   -3.3-131 m

. hjk ' i,;ctj :.: 's '- X; L .,- - L1 l l

d. With the number of OPERABLE Channels 33 less than the i

                                     ;inima;;; ReMEMEChannels m - . y.
                                       ?w e,pM %                  .

n- w.n . - 7.x.. .SStxtli gl l declare the appropriate Train A.C. Emergency Buses

inoperable and take the Action required by 2-32 LS

] Specification 3.8.3.1 for the buses not fully energiz . .. V .4 ll 0 3.3131

                                          .,+.a..

a ;g.- p. .. .

e. With the number of OPERABLE Channels g less than the /K i

e4nimum N,hannels 0"E"XL g ph.y m ;. 8: y. : w_. . m ; r;;;irennt.M AV y 9 declare both Offsite Power Sources inoperable, take the Action required by Specification 3.8.1.1, and ed bus 2-32 ts open both offsite 0 3.3 131 within 6 hours i B13155HREllE

                                          , 3 . + .; y , ../.; .w.n J

e CPSESMarkup of CTS 3N.3 3M 3-29 102M8

I

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LOP DG Start Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation 3.3 131 Q.3.3-131 LCO 3.3.5 %ree Eg channels per bus of the L-g volt:gegpMctoMMle , Function and three tg channels per bus ofTe tfegraWdToT69e M Function shall be OPERABLE. APPLICABILITY: MODES 1. 2. 3. and 4 I tL - .- .. ..J & J M/S J. --__.J.-J &. L- Mrif*fi A BI P L.. tPM 9 8 81 -AP q *, I nisusa uwavhauwww wu ua a squ a a wu hv uw vi n.sv 1wh6 uJ a.vu .e.w.h. riv 3 v;- g .g ' Sources - Shutdc.rs. " MG-mg1-5i225NgE15?i=[W&x-hiL: tit-B%-1g.gifi?.515 i Bg3ppJiggle?fdrT6:91kfLPreferred m0ffsiteTSourcLUndervoltagelunt:tiorOsheri 3.3 130 lR$$$$MX$E@ffelb[88M51 Slope @ Q 3.3 130 ; Lv, ., .u.. ... . .w. . ._. . . . .-. w 7:.~=_,,:.w. . . . . :":.T,,.m,=,r,.v,

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l ACTIONS ,

  .......................................-NOTES-------------                                                                                                ---- -
                                                                                                                                                                                                 \

gj Separate Condition entry is allowed for each Function. j

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                                                                                                                                            . _ _y . ,."-.m.- "_ _m _ _"'9 0-3.3 130 CONDITION                                           REQUIRED ACTION                                               COMPLETION TIME 4

A. One or more Functions A.1 "0T" m3;31E'd } with one channel per bus The inspcrabic chenaci s.cy T inoperable, be bypassed for up to l 4 hours for survcillance testing of other chenacl . il Place channel in trip. 6 hours I r i CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3 53 10B088 l l l

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  't CPSESMarkup ofNUREG-1431 - ITS 3.3                              3.3 54                                                    103088
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GE Required Action and Cf.1 Enter applicable Immediately: associated Completion Condition (s) and Time not met. Required Action (s) for ,

i the associated DG made 1 inoperable by LOP DG ' . start instrumentation. 1 Y SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 ."arfer . C"."* L CiiECK. Egggg 12 hours ?.5M.1 SR 3.3.5.2 58:1 zE W WM m 7x i . .

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. BllBREEB211 dei CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-55 10B088

1 l ! LOP DG Start Instrumentation ! B 3.3.5 I B 3.3 INSTRUMENTATION B 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation BASES BACKGROUND The DGs provide a source of emergency power'when offsite power is either unavailable or is insufficiently stable to allow safe unit operation. Undervoltage protection will generate an LOP start if a loss of voltage or degraded voltage condition occurs in the R $ M switchyard. Th; ; er; t.;; LO" start si;=ls, ;= for each 4.15 k'! vital b ;. ]Rtmltage pf3tectio@solateCthe 619hy;WCfMml_theloffsithduelto;3ou]3:eDtvoltage~or bus;desta*****=**wntermewittggitnacsCof_; bus y4wg w _- - - D. WMC 1s _ ._. ew,_3rwg yw e apptW .s

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                               !          reduaisembty#1 tert 2EEslan!eacrotahstset4sov216ss Witani l

l (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-153 10/3088

                                              ~             .                 -   -        -.      -   -_.    . --

l ( LOP DG Start Instrumentation l ! B 3.3.5 ; 1 1 l l BASES l

                          !      .:   f.. X f: ;,: ' c -)Diegt~MWWBh(Did                                    0 3.3-131 I l                                 . , - . .e1        <- - . 7 . . i ,..

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_ ';i 6 * ; i::" X .: ;l , Thicc undcrvoltogc releys with invcrse ti;c characteri: tics arc providcd on cach 4100 Cic;; IE in:tru; cat bu: for detecting a sustaincd degr:dcd voltasc condition er ; ic;; cf bu; volt;;c. The relays er; cdined in a two cut of thrcc logic to scacrate An LO" signal if the voltegc is bcicw 75% for a short tiac or bcicw 00% for ; ica; ti;;. The LOP start actuation is described l in FSAR. Section 8.3 (Ref. 1). Trio Setooints and Allowable Values The Trip Setpoints agtflassetated;tlee[ del _afCused in the relays are based on consistentNithjthe analytical limits presented in FSAR Chapter 15 (Ref. 2). The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account. , The actual nominal Trip Setpoint entered into the relays is normally still more conservative than that required by the i I t l l [ (continued) CPSESMarkup ofNUREG-1431 Bases -1153.3 B 3.3-153a 10B088

LOP DG Start Instrumentation B 3.3.5 BASES account for each individual component of loss of power detection and subsequent actions. The required channels of LOP DG start instrumentation, in conjunction with the ESF systems powered from the DGs, provide unit protection in the event of any of the analyzed accidents discussed in Reference 2 in which a loss of offsite power is assumed. The delay times assumed in the safety analysis for the ESF equipment include the 10 second DG start delay, and the appropriate sequencing delay. if applicable. The response times for ESFAS actuated equipment in LCO 3.3.2, "Enginxicd Safety featurc Actuation System 'ESFAS' Instru;catation " include the appropriate DG loading and sequencing delay. The LOP DG start instrumtmation channels satisfy Criterion 3 of-the NP,0 Policy Statcnnt.110CFR50.~36(c),(2M,11)J LCO The LC0 for LOP DG start instrumentation requires that two} channels per bus of both theptWoltaqq IcU 0 3.3 131 Tdltagt and degraded voltage Functions snais oe urtKABLE in 1, 2, 3, and 4 when the LOP DG start instrumentation supports safety systems associated with the ESFAS. In MODES 5 and 6 the [thix] channels aust bc OPEPXL: whencycr the associated 00 is required to bc OPEPELE to casurc that the automatic start of the 00 is availabic when r.adcd.itherelij CP-3.3 ED l

                                                   $ilf.fic_                      i t[LtitigeE8VeDableI4WEthat'iR34tlDalytt8tt90the Qge@GCtQccept.4blg] Loss of the LOP DG Start Instrumentation Function could result in the delay of safety systems initiation when required. This could lead to unacceptable consequences during accidents. During the loss of offsite power the DG powers the motor driven auxiliary feedwater pumps. Failure of these pumps to start would leave only one turbine driven pump, as well as an increased potential for a loss of decay heat removal through the secondary system.

APPLICABILITY The LOP DG Start Instrumentation Functions are required in MODES 1, 2, 3, and 4 because ESF Functions are designed to provide protection in these MODES. Actuation in "00E S cr S is rcquired whcxvcr the rcquired 00 must bc 0EPXL 30 that it can (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-135 10/3088

LOP DG Start Instrumentation B 3.3.5 BASES perferr., it; furiti;r, er, ;r, LO" er i;;r;id pc.;;r to th; vital bits-ADIO DDMM 0 3.3 130 the:6:9;*V;BR9ttetMBBIEEEWDM50Gdomageiergelsene SkfctM' .33 closed 70st M setIdtt#N BB8E m iobrce 153!ot~ t!eingMeng3oJ!qeygperpttshe~imftirttemtND Eng causelartsglltggggggggtEggr!aERDd3DeT@HRTed3ource undervojinggeglaioggentfagomsstrpenr.jple] ACTIONS In the event a channel's Trip Setpoint is found nonconservative with respect to the Allowable Value, or the channel is found inoperable, then the function that channel provides must be declared inoperable and the LC0 Condition entered for the particular protection function affected. Because the required channels are specified on a per bus . basis, the Condition may be entered separately for each bus as appropriate. A Note has been added in the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in the LCO. The Completion Time (s) of the inoperable channel (s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

                           . m m a-=. m_ - a m u. s u.m u m                                              u ..               _n
                           . _m._ m-m--.                                                            - n ---

f.i W i i ? w: e. = =. - y : +-- + .? 2Y FL.n=;

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bf991R99HE AJ, Condition A applies to the LOP DG start Function with one l o.3.3 131 3

                          @ryo].tagg less of volt;Orgforiggg degraded voltage l

channes per Dus 1noperable. (continued) I CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-156 10B088

l i LOP DG Start Instrumentation ! B 3.3.5 BASES I A Ot; i; ;dded to ellow byp;;;ing = irep;rebi; chenaci for up t; 4 h;;r; for ;;rcillace tc; ting of Otter ;henrel;. Thi; 11;;= = i; = d; wter; bga;;ing th; charci dec; not ;;u;; =

                           ;;t;;ti = =d Wter; et 1 = ;t two ~C etter ch= =1; or M                                  '

r mitoring th;t per;rcter. The specified Completion Ti:r.; =d ti; ;110.;;d for bg;;;ing en; chen=1 er;7di reasonable considering the Function remains fully , OPERABLE on every bus and the low probability of an event occurring during these intervals. B.1? B':f r end B:212 Condition B applies when er; then =CtxAh loss of voltage-ee r;r; th= =; degraded voltag; channels on ; ;ingic bu;ithe Preferred M [s.itelyoltagelSon_ ard 4s inoperable. Required Action B.1 requires restoring 11 but one c, to OPERABLE status. The 1 hour Completion Time should allow am time to repair most failures and takes into account the low probability of an event requiring an LOP start occurring I during this interval. ! l 81 M. EMM ._ ect.19 1!! 1s_tegmere!Ogscan!agmatteMm4Mid!r#7mEc!@t - 2!L . 21i lors.limatissasizestnummarantssesnswastesre~sostiffied starn med? pkI7TC3EEBERIEDfEJE r w etenenr amusemmermaammarreannwas "k

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                                                                                                                         =
                                                                                                                         .t i

l-(continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-157 10/3088 :

l l LOP DG Start Instrumentation ~

 .                                                                                                                                                  B 3.3.5 J

BASES

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a M955525EE19E1$N.100T831 i IM i i 1 1 j (continued) I ~ CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-158 10B088

I i l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-132 APPLICABILITY: CP, WC l REQUEST: The trip setpoints for the loss of power diesel generator start instrumentation are l relocated to a licensee controlled document. This approach is consistent with a format allowed l by a reviewer's note for the RTS and ESFAS instrumentation. COMMENT: {CP} - revise submittal to adopt ISTS format. FLOG RESPONSE: The Allowable Values for the loss of power diesel generator start ;

! instrumentation are retained in the ITS. The trip setpoints for the loss of power diesel generator                   j start instrumentation are moved to the Bases. The words "with setpoint Allowable Value" has                          ,

l been restored to SR 3.3.5.3. ATTACHED PAGES: i EnclSA 3.3-56 i l l l 1 l l i 1 i I h i F m

1 l \ LOP DG Start Instrumentation 3.3.5 I i i i 1 1 l SR 3.3.5.3 Perform CHANNEL m imTim with .ctp; int 18Eltghs "12 l All;;d,1- V;1" ' as follows:

                                                                                         ,                                            t l

l

a. [ unoervon.

M fsite sourc age w;n e, v:..., Allowable

                                                                                                                       ~j7 J

! Value N 2^12 Y with ; ' 3.3 132 tiz il;y of [0.0] i [ ] ^= end. 0 3.3 132 L:s: of volt; g Trip Satpoint 2 2^'5 Y with a tix clay of [0.0] 2 [ ] x;;ad. #4 4 18t2 l , mesa bl 811etrete'T6ffs X1tedtepilgtluridervolt. 73,3,33 g 811ornab1LyalgisgiptyIand21390022 gg,g ciet 6.9 kv Class 1E bus undervoltage BU S-PS ~M Allowable Value 21935 V and 5 3450 V with ; tia iley of [0.S] 1 [ ] x;end. yggg chit .9 kV Class IE bus degraded voltage .iv 4 Allowable Value t 5933 V with a tix ,

                                    - . .,. _.,, u ro...o,; . ,6 , _____;

2,

                                           .                          a m..                                        E3;3-8324
                             .      480 V Class 1E bus low grid undervoltage                                        15 8; Allowable Value 2 443 V with : tix ilay                                         '-
                                     ., ro e,       , , ,     _____2 vs (v.wJ A L          J .rwwvu ro .

m feig 0 V(lpsK3L egraded voltage Allowable alue a 4.sd Irw.th ; tix iley of ,E7 O [0.8) i [ ] second. j I 1 PONE.1 Ferif FAols!IE3tLE I ESE3EliEBSG2MES2%Witgle11mitG2ej;1tjg 5.JMJGEEDE ! 3 3-31

                          )F M ]                                                           E8SI!

0 3.3 55

I 1 l l l CPSESMarkup ofNUREG-1431- ITS3.3 3.3-% 10/3088

i ! ADDITIONAL INFORMATION COVER SHEET I ADDITIONAL INFORMATION NO: Q 3.3-135 APPLICABILITY: CA, CP, DC, WC .i i

l REQUEST: A MODE change restriction has been added to ITS 3.3.1 Condition C per the matrix discussed in CN 1-02-LS-1 of the 3.0 package. ] Comment: Reject - The ITS proposes generic changes to the STS that are not ; included in an approved TSTF. The Justification is inadequate. ! Note: This WC ITS markup was not shown as a red line addition . FLOG RESPONSE: The rationale behind JFD 3.3-135 remains valid, as discussed in LS-1 of the ) 3.0 package. As a result of discussions with NRC staff, the FLOG has clarified the note to make , it more user friendly. No change to the JFD is required. j ATTACHED PAGES: Encl. 5A 3.3-2 ! Enci5B B 3.3-38a l I l I l I i l l l 4i a

RTS Instrumentation 3.3.1 l t l ACTIONS (continued) : CONDITION REQUIRED ACTION COMPLETION TIME i 0 35 l summmmmmmmmes m )

                     .i n ,-
                              *h M                                     C.1 Restore channel or train to               48 hours 6..     .                  .

OPERABLE status. Pw-+ .

                   * .a-f53EE~T5 2

C. One channel or train C.23 Og , 23131t14g 4948jhours 3.3-122 inoperable. M 171t$ert TR-3.3 006 WTERNRfC i OE EMI - Gifia ISESummeGhnro.1 : NelDmmam!1119!! L@NkMIDTMM mannen i l l l . 1 I-Ii CPSESMarkup ofNUREG-1431- ITS3.3 3.3-2 10/303 8 $

RTS Instrumentation B 3.3.1 BASES

s i

i 1

i l i l lla f

i

[ -> l l' continued D !i l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-38a 10B088 l

   -        ..    -          -                        - - - .  . . - . . - - _ . . - . _ . - . . -   . . - . = .

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CA-3.3-005 APPLICABILITY: CA, CP, WC i REQUEST: Revise RTS Bases to clarify Si input from ESFAS and revise Bases for TADOTs in SR 3.3.1.14 and SR 3.3.2.8. l ATTACHED PAGES: , Enci 5B B 3.3-28, B 3.3-58, and B 3.3-120 e i i l l it a

i

RTS Instrumentation B 3.3.1

! BASES l H0DE 1 above P 9. All four channels must trip to cause reactor trip. Below the P 9 setpoint, a load rejection can be accommodated by the Steam Dump 6 Systeng. In H0DE 2, 3, 4, 5, or 6, there is no potential for a load rejection, and the Turbine Trip-Stop Valve Closure trip Function does not need to be OPERABLE.

17. Safety In.iection Inout from Enaineered Safety Feature Actuation System The SI Input from ESFAS ensures that if a reactor trip has not already been generated by the RTS, the ESFAS automatic actuation logic will initiate a reactor trio,l CA 3.3 005 l uponany(utjatsjsignal mai, initiates SI. This is a condition or acceptability for the LOCA. However, other transients and accidents take credit for varying levels of ESF performance and rely upon rod insertion, except for the most reactive rod that is assumed to be fully withdrawn, to ensure reactor shutdown. Therefore, a reactor trip is initiated every time an SI signal is present.

Trip Setpoint and Allowable Values are not applicable to this function. The SI Input is provided by relcy NggRin the $$$gl@lMitgg3gRbpjESFAS. Therefore, there is no measurement signal with which to associate an LSSS. The LC0 requires two trains of SI Input from ESFAS to be OPERABLE in H0DE 1 or 2. A reactor trip is initiated every time an SI signal is present. Therefore, this trip Function must be OPERABLE in H0DE 1 or 2, when the reactor is critical, cad must bc shut dcar. in the cycat of ca cccident. In H0DE 3, 4, 5 or 6, the reactor is not critical, and this trip Function does not need to be OPERABLE.

18. Reactor Trio System Interlocks Reactor protection interlocks are provided to ensure j reactor trips are in the correct configuration for the current unit status. They back up operator actions to ensure protection system Functions are not bypassed during unit conditions under which the safety analysis assumes the CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-28 10B088

r : RTS Instrumentation B 3.3.1 BASES ti; t;;t will nrify the ret; 1;; cagn;; tion for ' low fre; the care t: th: ." ".:. The Tr;;;;rcy is justificd by th: :::s;ption of : 10 enth calibr: tion intervel in the deter;inction cf the ;;;nitud; cf eqtHpent drift in th; setpcint nely:i:. l l SR 3.3. Ll3 l ] SR 3.3.1.13 is the performance of a COT of RTS interlocks every 18 months. l l The Frequency is based on the known reliability of the interlocks and the multichannel redundancy available, and has been shown to l be acceptable through operating experience. SR 3.3.1.14 SR 3.3.1.14 is the performance of a TAD 0T of the Manual Re r Trip. RC" Orc:dar P :itian and the SI Input from ESF " CReactotsT#o31glh@SIBMpndtgggagegrjp3ltghg}p mis i 3 j TADOT is performed every [10] gimontns. l Theba._ __-mm_n R*++Usha11 independently verifytheOPERABILITYo'~thedag[qWifg$gyndervoltageand i shunt try -- --

                                                     --- --* ;ecnonu;; Yor th; "; nuel R;;@

(?g .sactionMhe Reactor Trip Breakers and Reactor Trip sypass creaKers. The Reactor Trip Bypass Breaker test shall include testing of the automatic undervoltage trip efelettsg. The Frequency is based on the known reliability of the Functions and the multichannel redundancy available, and has been shown to be acceptable through operating experience. The SR is modified by a Note that excludes verification of l setpoints from the TAD 0T. The Functions affected have no setpoints associated with them. l l SR 3.3.1.15 l l SR 3.3.1.15 is the performance of a TAD 0T of Turbine Trip Functions. This TAD 0T is as described in SR 3.3.1.4, except that this test is performed prior to reactor startup. A Note states that this Surveillance is not required if it has been performed within the previous 31 days. Verification of the Trip Setpoint does not have to be performed for this l l CPSES Markup ofNUREG-H31 Bases - ITS 3.3 B 3.3-S8 10B0/98

_,__.--.__.q ESFAS Instrumentation B 3.3.2 j BASES SR 3.3.2.8 SR 3.3.2.8 is the performance of a TADOT. This test is a check of the Manual Actuation F art on tri CA 3.3 005 j 1 MFW l - , , . ~. y. 1

                                                                                                                                                                ,s
                                                             ,,...,.                                 +          ,
                                                                                                                                           .. . . . ,o                    '

b .., . A . c: . ;.. . . ' . . , . l; ! . ', . . *- Twb36p ' is per ivi meu ( gism.- _;ca .;...... ~ . _ ..... unction is tested up

a every 3 months.

   ,                                                        to. ;nd ireluding, th; ;;;; ster rcl;y coils. In sea                                                                0 3.3 G 1 insterces, th; test includc:; ectuation of th; cad dcvic; (i.e.. pa;;;p starts, v;1vc cycles, etc.). The Frequency is adequate, based on industry operating experience and is consistent with the typical refueling cycle. The SR is modified by a Note that excludes verification of setpoints during the TADOT for manual initiation Functions. The manual initiation Functions have no associated setpoints.

SR 3.3.2.9 SR 3.3.2.9 is the performance of a CHANNEL CALIBRATION. A CHANNEL CALIBRATION is performed every 28 months or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The a test verifies that the channel responds to measured parameter within the necessary range and accuracy. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit specific setpoint methodology.-The differeric betuc;n the curicnt ";s f;und" valucs ;nd th; previous ~

test *;s left" values ;;;ust bc consistcat with the drift all;w;nce 1 u ,cd in the sctp; int athcdelsgy.

The Frequency of M months is based on the assumption of an M month calibration interval in the determination of 0-3.3-G J1 the magnitude of equipment drift in the setpoint methodology. a ' This SR is modified by a Note stating that this test should include verification that the time constants are adjusted to the prescribed values where applicable. Whent3GD TR-3.3-004 is y, r y . ' , : . % . . 9 - - w.. .p<- c.f .:. . y . p .c h .J gj 'j. E' ...is u .3 .. ., . . . . . , . . g . :. _ . . j . . . . tigg i p -. n . - . y j ; _ .;,'t 4 . . ' . y j . (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-120 10B088 l _ _ _ - _ _ _ _ - _ _ - _ . _ _ _ _ - _

1 ADDITIONAL INFORMATION COVER SHEET 3 J 1 ADDITIONAL INFORMATION NO: CA-3.3-016 APPLICABILITY: CA, CP, WC REQUEST: Revise JFD 3.3-41 since the change is not consistent with these FLOG plants' l current TS. i ATTACHED PAGES: . EnciBA 4 Encl 6B 7 [ I i I

CHANGE NUMBER JUSTIFICATION 3.3-34 Not applicable to CPSES. See Conversion Comparison Table , (Enclosure 68). 1 1 3.3 35 Not applicable to CPSES. See Conversion Comparison Table l (Enclosure 6B). 3.3-36 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 37 Several ITS Required Action Notes are modified to allow a channel to be placed in bypass for surveillance testing. [This change, incorporating bypass test instrumentation, was approved for CPSES through Amendments 47 and 33 for Units 1 and 2, respectively.] 3.3-38 The CPSES design uses the N 16 based overtemperature and overpower i protective functions. Several changes to the setpoints, Required I Actions and Surveillances of NUREG-1431 are required to maintain the current licensing basis. 3.3-39 Not applicable to CPSES. See Conversion Comparison Table l' (Enclosure 6B). 3.3 40 This change adds "and actpoint edjustaant" to ITS 3.3.1 Conditica E. 0 3~3 40 Mmilar to the Not; for Ocaditica D. Sctpcint adjust cat is u rcquired by th; Pcquircd Actions of other ;pecifications. The cicrity :nd con;istency of th; ;pccification is cabenccd by adding this note to Condition C. in the :;;c manncr :: Condition D. Eot;used] l 3.3 41 ITS 3.3.1 ConMHnn L is deleted to match tne plant specific design cA-3.3 016 l n c inc currcat TS fo the source range neutron flux function in Mode 3 , 4 , m ., ; m.. we Kod Control System incapable of rod withdrawal and all rods not fully inserted. Under these conditions, the source ; range instrumentation does not provide a Reactor Trip System function. The source range channels provide only indication [ ] when in this Applicability. Requirements related to the source range neutron flux l channels in Modes 3, 4 and 5 when all rods are fully inserted and are not capable of being withdrawn have therefore been [ relocated outside of technical specifications]. This change is consistent with traveler TSTF 135. 3.3 42 This change deletes ITS 3.3.1 Condition N per traveler TSTF-169. Condition M is appropriate for Function 10.a to prevent sequential entry into Condition N followed by M and exceeding the evaluated Completion Time in WCAP-10271 P A. Supplement 2, Rev.1. With this change, there is no need to list separate Functions 10.A and 10.b and combining the Functions eliminates Applicability questions similar to the Condition M vs. N concern above. 3.3 43 This change revises ITS 3.3.1 Condition R Notes 1 and 2 per traveler TSTF-168. The 2 hour A0T should not be limited to only UVTA/STA CPSES Differencesfrom NUREG-1431 -ITS 3.3 4 10B088

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NtREG-1431. SECTION 3.3 Page 7 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-36 ' Revisions reflect revised BDMS setpoint in current TS. No - not in current No - not in current No - not in current Yes (current T5 per TS. TS. TS. OL Amendment No. 94 dated 3-7-95) 3.3-37 Several ITS Required Action Notes are modiff'ed to allow a Yes Yes No - not in current No - not in current channel to be placed in bypass for surveillance testing. design or TS. design or TS. [This change, incorporating bypass test instrumentation, was approved for CPSES through Amendments 47 and 33 for Units 1 and 2 respectively.] 3.3-38 The CPSES design uses the N-16 based overtemperature and No Yes No No overpower protective functions. Several changes to the setpoints, Required Actions and Surveillances of NUREG-1431 are required to maintain the current licensing basis. 3.3 39 Improved TS Table 3.3.7-1 is changed to be consistent with No - not in current No - not in current Yes Yes current TS Table 3.3-3. The Actuation Logic was split to TS. TS. reflect the SSPS, witn e.!y MODE 14 Applicability, and BOP-ESFAS portions and associated SR requirements in the current TS. 3.3-40 "dd ccd xtpci-t cdpur to ITS 3.3.1 Ocaditica C, VesNA VesNA VesN4 Ve q ci;ilcr to thc Not; for Conditica 0. jbt',ysed 0 3.3-LO 3.3 41 ITS 3.3.1 Conditinn ' "i'"* O match tne p... No - see CN Yes Yes Yes specific desigCrd t':: ca m .^T r the Source 3.3-123. Neutron Flux Function in nuut.a a. *, and 5 with the Rod Control System incapable of rod withdrawal and all rods ~ l CA-3.3-0 .6 l fully inserted. Under these conditions, the source range instrumentation does not provide a Reactor Trip System Function. The source range channels provide only indication [ ] when in this Applicability. Requirements related to the source range neutron flux channels in e' HDDES 3, 4, and 5 when all rods are fully inserted and are not capable of being withdrawn have therefore been (relocated outside of the technical specifications). CPSES Conversion Comparison Table -ITS3.3 10BOM8

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP-3.3-ED APPLICABILITY: CP REQUEST: Various changes that do not impact the technical content of the submittal or other FLOG members. ATTACHED PAGES: Enci2 3/4 3-4 Corrected MODE note reference 3/4 3-13 Removed strike-out 3/4 3-53 Deleted "not" Enci5A 3.3-12 Corrected SR note 3.3-37 Corrected footnote (g) 3.3-46 Deleted extraneous JFD marginal note Enci5B B 3.3-1 Grammatical correction B 3.3-2 Deleted brackets and added wording for consistency B 3.3-9 typographical correction ., B 3.3-11 Corrected paragraph heading B 3.3-12 Corrected name of trip function B 3.3-46 Deleted paragraph because the Action was "not used" B 3.3-52 Corrected power level B 3.3-54 Grammatical correction B 3.4-155 Typographical correction B 3.3-163 Grammatical correction l B 3.3-175 Deleted COT discussion (moved to the applicable SR) B 3.3-176 Paragraph heading correction j B 3.3-179 Added COT discussion l i l l l l I I l J

.mm _. m. s - -m . _ _ _ __ _. __ _ _ TABLE 3.3-1 (Continued) EACTOR TRIP SYSTEM INSTRUMEhTATION Hl!GIILM MMM M' TOTAL "0. C".'"" L5 C".'??'! LS APPLICABLE FUNCTIONAL _llE1I 0F-CHANNELS TO " LIP 0"E"m'"LE MODES ACTION

16. Turbine Trip

a. Low Fluid Oil 3 2 2 l' 6gg 1,11,g Pressure Q-3.3-02

b. Turbine Stop Valve 4 4 4 l' ION Closure

17. Safety Injection Input 2 1 2 1, 2 13 from ESFAS

18. Reactor Trip System Interlocks

a. Intermediate Range 2 1 2 26 7 Neutron Flux, P-6

b. Low Power Reactor Trips Block P-7 gg

1) " 10 Input 4 W pfe itta,10 2 3 1-2 73 kJp24tlGbd

                  -2) " 13 Input                                      2                                                                                                   1              2           -1          7-                     --

c. Power Range Neutron Flux, P-8 464 2 3 1 73

d. Power Range Neutron Flux, P-9 4M-$ 2 3 l' 31 7m

e. Power Range Neutron Flux, P-10 434 2 3 1, 2 7 g ,g g^-

fg[urbMt.F1g!@jLtagL$Pressute]P213Fi2?sEEFJ2ingMMT&dgiFJi3215CygagfeitN! 3 shi5kl&W

19. Reactor Trip Breakers 8 2 1 2 1, 2 8-11 u

                                                                                                                                                                                                                              - - nw ~ ' mg' 2                                                                                           1              2       3',  4'.

9 l 05-3.3 ED l MEW KGFCtDPELMBRERKUtgfMtV51tyge p_distnarttE!pyteshj!rtsm; n

PJf1TeactCperjRTB ,- MSl%ymcau c = teacn n m nuwa man m%u

20. Automatic Trip and 2 1 2 1, 2 13 Interlock Logic 2 1 2 3', 4*, S* 9 CPSESMarkup ofCTS3N.3 3N 3-4 10B088

TABLE 4.3 1 (Continued) REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES FOR

                                                                                                         ,                  CHANNEL             DEVICE                                                          WHICH                                                 _

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE II-4EARi FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS PIGUIRED

18. Reactor Trip System Interlocks (Continued)

c. Power Range Neutron N.A. R(4) R N.A. N.A. 1 Flux, P 8

d. Power Range Neutron N.A. R(4) R N.A. N.A. 4 Flux, P-9

e. Power Range Neutron N.A. R(4) R N.A. N.A. 4-2 Flux, P-10

19. Reactor Trip Breaker N.A. N.A. N.A. M(7,41) N.A. 4r24'd'd* [U32;LGQ NewtRWetoMNIA_MXANTAIDPfallitliA?fi3ffff M(7)i?I!ffrdL11K!@M"E Td6 setvoltageganitstemstMg g,1497,*

LZRJiechBiseg

20. Automatic Trip N.A. N.A. N.A. N.A. M(7) 4dd'd'd' and Interlock Logic

21. Reactor Trip N ./4. N.A. N.A. M(7.15) N.A. 4'A'A'd'A' fil 3t+@4 Bypass Breaker f F16) Acil u p u CP-3.3 ED CPSESMarkup of CTS 3N.3 3/4 3-13 10/30M8

                     ~
                -______2_~ L - -__ _ _-_-______ _ ______-_-_ - . - - _ _ _ - - - _ - _ .                               -               .- . _ .       - . _ - .--                                .                        _ _ - .                              _    . - - _ _ --

INSTRUMENTATION 1 63 A ACCIDENT MONITORING INSTRUMENTATION Q 1 A GEN LIMITING CONDITION FOR OPERATION 3.3.3.3 The accident monitoring instrumentation channels m shown in Table 3.3 6 shall be OPERABLE. . APPLICABILITY: MODES 1, 2, and 3. ACTION:

a. As shown in Table 3.3 6.

b. The provisions of Specification 3.0.4 are not applicable.

INEW1 $eparate3ondition,"t!!tpr,1CaMelesTorleach7functiog IIMI SURVEILLANCE REQUIREMENTS 4.3.3.3 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:

a. At least once per 31 days by performance og CHANNEL CHECKMg .57 -

9 h M 2118:3sEgGLiting%tha131 dEIREBtL1mj,

b. ' At least once per 18 months by performance of a CHANNEL

                 , CALIBRATION.*

8-09 LG Q 3.3-20

   '       0;r.teiraint Area R;di; tion Cligh "eng;) Cl'f""CL CALI"J1ATIC" ;;y ;;nsist Of en

4. ci;;tronic calibration Of the ;h;n .;1. not including the itect;r. for reng;
d;;;d: s abov 10 "/h and a en; point calibration ch;;k of the it;;ter b:lw 10 "/h

           .;ith n inst:lled er p;rtsbic U-         scur;;.

1 I a I CPSESMarkup of CTS 3N.3 3M 3-53 10B088

1

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) 1 SURVEILLANCE FREQUENCY i l SR 3.3.1.4 - - - - --- --- NOTE------------ ------ - This Surveillance must be performed on the l reactor trip bypass breaker 35ghe~3ccsi g,gaggg , MahW$2ittjpM prior to placing the l bypass breaker in service. 31 days on a Perform TADOT. STAGGERED TEST BASIS . SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.1.6 -- ----- --- ----- --NOTE --- - -- - --- ----- Not required to be performed until 72 hours 2 m3AJ after achf6vigjpgull,1blign"tiekHtionsMth p3 3,97 3 THERMAL POWER 4s a 50 3 % RTP. Calibrate excore channels to agree with incore E EFPD Em823 detector measurements. SR 3.3.1.7 - --- ---- - - -- NOTEE --------- - - ------ 1] Not required to be performed for source range instrumentation prior to entering MODE 3 from H0DE R until 4 hours after entry into MODE 3. cP-3.3 ED U # m .= ' r- .. W '. " )lalitR$_10d Mgggj thatiingw3gtam_' E t W it . teqd)NkFstate3 font t41ttttnes Perform COT. E days WA821 i i-CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-12 103088 L

ESFAS Instrumentation 3.3.2 Table 3.3.21 (page 4 of 10) Engineered Safety Feature Actuation System Instrumentation 1 APPLICABLE NUDES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE N _). 2 $ . ..i.. FUNCTION COWITIONS CHANELS COEITIONS REQUIREENTS VALUE88

4. Steam Line Isolation (continued)

b. Automatic Actuation 1.2"'. 3"' 2 trains G SR 3.3.2.2 NA NA Logic and Actuation SR 3.3.2.4 Relays SR 3.3.2.6

c. Containment 1. 2"'. 3"' 43 D SR 3.3.2.1 [6i8,1psjg 6 e.6-36 g g.p$g Pressure - High 2 SR 3.3.2.5 6-61 ps+g SR 3.3.2.9 g3 3%j 0" 2.2.:.1"

d. Steam Line Pressure 1. 2 "', 3 per D SR 3.3.2.1 6% M (1) Low 3*'"' steam SR 3.3.2.5 L593.5 ps4g* ENE line SR 3.3.2.9 psig'u 0" 2.2.2.1" till ggg

                                                                                                           @8 3       4          '

MW" . Ognt21 (2) Negative Rate - High 3"' 3 per D SR 3.3.2.1 {3]8g"3 e419 ps4/ses** gg steam SR 3.3.2.5 M1 line SR 3.3.2.9 4Eh6 M 3'E.f 5" 2. . .10 pe+/see

       ."igsta;riu "Ta                  4#%a*            a-per                9        :" .:. .:               w              m          fr.343dE4 Sts;. Lir.;;;                                   steen                         ;" 2.2.2.5
                                                          +4ne                         0" 2.2.2.0 0" 2.2.2 !"

Oi xid...; .;it' 4 r3*r 4-pee 9 " 2.2.2.1 i (5:0.0;"" ; [552 *" 7,,, L;.; L;;.; 3** 4eep 0" 2.2.2.5 C" 2.2.2.0 C" 2.2.:.1" (continued) (a) ";.-i s;r'; L t;. Wit b i'i; i;;;1-..;th= si .t;i . sly ".lhati; hh; ir...dir; = R ty,. i ". 0;.dj _ t: i h ;; .;;d by t'.; r.'t . -.;.

                                                                         '.         n. t, y ,2.g.; H t w 3833rM                                             i N                                                                                                                              3.3-63 (b) Above the P 11 (Pressurizer Pressure) Interlock m]Mg3@gcggd.

0 3.3 63 l (c) Time constants used in the lead / lag controller are ti a M seconds and te s 5 seconds. . l (g) Below the P 1 res Pressu [egy CP 3.3 ED 4 (h) Time consta ilized in the rate / leg controller is s seconds. (1): Except when all NSIis i- ,- - . . - ..c. , .. ; p..f ; .areclosed2Lnd M 4 ? CPSESMarkup ofNUREG-1431 - ITS3.3 .3.3-37 10/30M8 l

PAM Instrumentation 3.3.3 CONDITION REQUIRED ACTION COMPLETION TIME 7 7 i F. As required by Required F.1 Be in MODE 3. 6 hours m Action E.1 and CP 3.3-ED referenced in f AND Table 3.3.3 1. F.2 Be in MODE 4. 12 hours l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME j i G. As required by G.1 Initiate action in accordance Imediately Required Action E.1 with Specification 5.6.8. and referenced in Table 3.3.3 1. l l I i l 1 l l i

CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-46 102088

RTS Instrumentation B 3.3.1 B 3.3 INSTRUMENTATION B 3.3.1 Reactor Trip System (RTS) Instrumentation BASES BACKGROUND The RTS initiates a unit shutdown, based on the values of selected unit parameters, to protect against violating the core fuel design limits and Reactor Coolant System (RCS) pressure boundary during anticipated operational occurrences (A00s) and to assist the Engineered Safety Features (ESF) Systems in mitigating accidents. The protection and monitoring systems have been designed to assure safe operation of the reactor. This is achieved by specifying limiting safety system settings (LSSS) in terms of parameters directly monitored by the RTS, as well as specifying LCOs on other reactor system parameters and equipment performance. . The LSSS, defined in this specification as the Trip Sctpcints 81LoWahleJalg, in conjunction with the LCOs, establish the threshold for protective system action to prevent exceeding acceptable limits during Design Basis Accidents (DBAs). During A00s, which are those events expected to occur one or more times during the unit life, the acceptable limits are:

1. The Departure from Nucleate Boiling Ratio (DNBR) shall be maintained above the S;fety Limit (SL) value to picvent .

departur; frea nucleate b;iling (0"0);3epEtiLreErgi[i llRh!R%fEIG1Migt,92Dl@BE11 git]

2. Fuel centerline melt shall not occur: and

3. TheRCSpressureSE3}jul f 2750 psic M 9 CP.3.3-ED l shall not be exceeded.

Operation within the Sh limits of Specification 2.0. " Safety Limits (SLs)," also maintains the above values and assures that offsite dose will be within the 10 CFR 50 and 10 CFR 100 criteria during A00s. continued CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-1 10B088 ( l i

i RTS Instrumentation B 3.3.1 BASES BACKGROUND Accidents are events that are analyzed even though they are not (continued) expected to occur during the unit life. The acceptable limit during accidents is that offsite dose shall be maintained within an acceptable fraction of 10 CFR 100 limits. Different accident categories are allowed a different fraction of these limits, based on probability of occurrence. Meeting the acceptable dose limit for an accident category is considered having acceptable consequences for that event. The RTS instrumentation is segmented into four distinct but interconnected modules : illustrated inTigurc [ ],ng cP 3.3 ED gescribeg3g3!LelFSAR, Chapterj7h(Ref.1), and as identified below: 1

1. Field transmitters or process sensors: provide a measurable electronic signal based upon the physical characteristics of the parameter being measured:

2. Signal Process Control and Protection System, including 3_he i

                                !) Mag lgkE(gstrunggatjg'endLEgttig Anoleg "retection                         !

System, Nuclear Instrumentation System (NIS), field i ' contacts, and protection channel sets: provides signal conditioning, bistable setpoint comparison, process algorithm actuation, compatible electrical signal output to protection system devices, an board / control room / miscellaneous indications -

3. Solid State Protection System (SSPS), including input, logic, and output bays: initiates proper unit shutdown i and/or ESF actuation in accordance with the defined logic, !

which is based on the bistable outputs from the signal l process control and protection system; and i

4. Reactor trip switchgear, including reactor trip breakers (RTBs) and bypass breakers: provides the means to interrupt power to the control rod drive mechanisms (CRDMs) and allows the rod cluster control assemblies (RCCAs), or

                                 " rods," to fall into the core and shut down the reactor.

The bypass breakers allow testing of the RTBs at power. continued i CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-2 10B088 l

l RTS Instrumentati8n i B 3.3.1 BASES I APPLICABLE shutdown rods or control rods A - 1 m- -

                                                                                       >7 SAFETY ANALYSES,5       jagT1gl. If the rods cannot be withdrawn from the core                            l LCO, and                gggm, there is no APPLICABILITY           need to be able to trip the reactor, because all of the rods (continued)            are inserted. In MODE 6, neither the shutdown rods nor the control rods are permitted to be withdrawn                  TR-3.3 006 and the CRDMs.are disconnected from the control rods and shutdown rods. Therefore, the manual initiation Function is not required.                                                         ,

l

2. Power Ranae Neutron Flux l l

The NIS power range detectors are located external to the I reactor vessel and measure neutrons leaking from the core. ! The NIS power range detectors provide input to the Rod l Control System or.d th; St:= C;ncreter '00) ',icter Level l

                             -.mv.        .,,m... Therefore, the actuation logic must be able to withstand an input failure to the control system, which may then require the protection function actuation,                         ;

and a single failure in the other channels providing the . protection function actuation. Note that this Function also provides a signal to prevent automatic and manual rod i withdrawal prior to initiating a reactor trip. Limiting l further rod withdrawal may terminate the transient and ) eliminate the need to trip the reactor.

a. Power Ranne Neutron Flux-Hiah The Pcwer Range Neutron Flux-High trip Function ensures that protection is provided, from all power i levels, against a positive reactivity excursion )

leading to DNB during power operations. These can be ) caused by rod withdrawal or reductions in RCS j temperature. The LC0 requires all four of the Power Range Neutron ; Flux-High channels to be OPERABLE. 1 In MODE 1 or 2, when a positive reactivity excursion could occur, the Power Range Neutron Flux-High trip must be OPERABLE. This Function will terminate the ; reactivity excursion and shut down the reactor ! prior to reaching a power level that couldfNggt frfWASM8D])Reye]3,1 damageED the fuel. I CP 3.3 ED n MODE 3, 4, 5 or 6, the NIS power range detectors cannot detect neutron levels in this r:lige. In these MODES, the Power Range Neutron l Flux-High does not kk CPSESMarkup ofNUREG-H31 Bases -D53.3 s J.3-9 10/30M8

.n

RTS Instrumentation B 3.3.1 BASES SAF m ANALYSES, 3. Power Neutron Flux Rat APPLICABILITY The Power Range Neutron Flux Rate trips use the same (continued) channels as discussed for Function 2 above. I CP 3.3 ED

                                  ._..__a____u_.___      n....   . u a n _2. . .. n__

The Power Range neutron riux-mgn Positive Rate trip Function ensures that protection is provided against rapid increases in neutron flux that are characteristic of an RCCA drive rod housing rupture and the accompanying ejection of the RCCA. This Function complements the Power Range Neutron Flux-High and Low Setpoint trip Functions to I ensure that the criteria are met for a rod ejection from the power range. The LCO requires all four of the Power Range Neutron Flux-High Positive Rate channels to be OPERABLE. In MODE 1 or 2, when there is a potential to add a large amount of positive reactivity from a rod ejection accident (REA), the Power Range Neutron Flux-High Positive Rate trip must be OPERABLE. In MODE 3, 4, 5, or 6, the Power Range Neutron Flux-High Positive Rate trip Function does not have to be OPERABLE because other RTS trip Functions and gladministrative controls will provide protection against M positive reactivity additions. Also, since only the shutdown banks may be withdrawn in MODE 3

                                 '4, or 5, the remaining complement of control bank worth ensures a sufficient degree of SDM in the event of an REA.

In MODE 6, no rods are withdrawn and the SDM is increased ~ during refueling operations. The reactor vessel head is also removed or the closure bolts are detensioned ._ preventing any pressure buildup. In addition, the NIS power range detectors cannot detect neutron levels present in this mode,

b. "; cr "=2 ": tra n= '!ich istin Ltc r.

Oc ";;;r " s;; " stren Fl u lligh L;;tiv; Mt; Trip fuxtien ;narn that pretati;n is presid;d for =ltipl; i T M di e . C i d ..; . '.t 7.1 7. A ;T l Kl . ; Ilti- - id , 47@ x;id,.r.t ;;;ld enn le;;l 'la p ;hing th;t W;uld j r;;it in = use.xrv;tiu; 1;;el :"O. l E " is d; fired = the ratic of the heat f1= required tc cau:;c a 0"S at a pe-ti;;ler le;etien in th; cer; to th; le;;l hGt fi n. I continued CPSES Markap ofNUREG-1431 Bases -IT$ 3.3 B 3.3-11 198038

I I RTS Instrumentation B 3.3.1 ! BASES SAFETY ANALYSIS. The "4" is indicative ;f the orgin to 0".S. ti; credit is LCO, and t;kca for the epcration of this functicr for th;x red drep APPLICABILITY eccid;,ts in which the leal C = 3 will bc grater then the ] (continued) 44e h , The LOO rcquircs all four .";W^r "ag; "cutre , c1. .m II u__.AJ.. M.A. L __-1 A. L. AnrM ant e 5 3 MA7 . J, y_L.

                                                        . Evbyub5TL Isu b5                hs .w. .. E , J. bw wh VI bivwbb e In tiODE 1 er 2, whcr. thcic is p;tcatial for ; sultiple red drop occidcat t ;ccur the ";;;r ",;,9; ficut on                                                                     '

f*1. . m It u__.AJ,.. n... A J, y _.._A Lm Anrn a n t r t

                                     . 4 un  7.J, yL,4 sVWyu b . y b       .Tu b5 b5              ,U J b ub      W, 63W7Wbb.           .55
                                     .unar-i. ,n , ,,A,, e e                __ e                   n . .- -

v. ., m b.L,e. . . ns. , ,vs--u,s..A.___.

                                                                                                                 ,b           . .c1,..m on        e.: J.,_L, ,

fics;tiv; " ate trip function decs not have to bc ; 0"E"","L bccoun th; ;;rc is not critical and Ot?" is i not ;;nccrr. ^130 sinc; only the shutdown b=ks acy be withdrow. in l100: 3. 4. Or 5, the r acining co ,plaat of catrol bank worth cn urcs ; sufficient m ____ _, ,_ _, e __ osv. ss. m. enu. ... .b.L.s. m s.. __. _ _ n,r .

                                                                                               .. . . . , m.            v. u. .nne
                                                                                                                        ...       m   v,     ...

reds arc withdrew. and the rcquired 50". is increased during rcfucling spcrations. In Oddition, the !!IS powcr reng; detectors connet dctcct acutron icvcis y, s. .,s. . Ab J.....L.J.._,

b. .u.nne m. ,

4. Intermediate Ranae Neutron Flux CP 3.3 ED

                             .The Intermediate Range Neutron Flu Jgt) l rip Function ensures that protection is                                               aded against an                              i uncontrolled RCCA bank rod withdrawal accident from a subcritical condition during startup. This trip Function provides redundant protection to the Power Range Neutron Flux-Low Setpoint trip Function. The NIS intermediate range detectors are located external to the reactor vessel and measure neutrons leaking from the core. The NIS intermediate range detectors do not provide any input to control systems. Note that this Function also provides a signal to prevent automatic and manual rod withdrawal prior to initiating a reactor trip. Limiting further rod                                                                             !

withdrawal may terminate the transient and eliminate the need to trip the reactor. The LC0 requires two channels of Intermediate Range Neutron Flux to be OPERABLE. Two OPERABLE channels are sufficient to ensure no single random failure will disable this trip Function. continued . CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 .B 3.3-12 103088 L

RTS Instrumentation B 3.3.1 BASES channel, and the low probability of occurrence of an event during this period that may require the protection afforded by the Functions associated with condition M. The Required Actions have been modified by a Note that allows placing the inoperable channel pmr in the bypassed condition for up to 4 hours while performing routine surveillance testing of the other channels. The 4 hour time limit is justifiedinReference-75 N.1 and N.2 Not[tJsedECenditi;n " applies to the ",c;; tor C;; lent flow-L;w singic Leop) reacter trip function. With enc chenaci ir,egreble. th inegrebic che rici ;r.ust be placcd ir, trip withir, e L..__ ,, &L_ _L____1 _____i L. ___m___a .. nnenan.c _i..._ __ v g uvut ep . AI barb wa sus se rw s wus ss av b ww I w e bvs wu bv vu bsv7wun. .p bu bu d vt

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t#Rtat2tWDm2EthatR13l3tEK'RERBtRElLY,MERABIZ Egys3!t91LX!B89K3RVROP't0MHt1NIREINIDOWIWaf'D6 a ttL4Legalemmtgr.itiup11htwitmn'stema!Er.1muts2ThC! i hers7anetepitrplat*2WateperalREERamEMRuthEtttoped WIRH1190ldQlE3."MpfralMggriTm l Bushif2eEIRERBERWEEM i (continued) 1 i 4 ) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-46 IW3W18

i i i RTS Instrumentation j B 3.3.1 i BASES ! power is = 15% RTP and that 12 3$1hourg 4e allowed for performing the first Surveillance after reaching 15% RTP. At lower power levels, calorimetric data are inaccurate. The Frequency of every 24 hours is adequate. It is based on unit operating experience, considering instrument reliability and operating history data for instrument drift. Together these factors demonstrate the change in the absolute difference between NISEN36 and heat balance calculated powers rarely exceeds 2% in any 24 hour period. In addition, control room operators periodically monitor redundant indications and alarms to detect deviations in channel outputs. SR 3.3.1.3 SR 3.3.1.3 compares the incore system to the NIS channel output every 31 EFPD. If the absolute difference is 2 3%, the NIS channel is still OPERABLE, but must be readjusted. If the NIS channel cannot be properly readjusted, the channel is declared inoperable. This Surveillance is performed to verify , the & fM f13q); input to the overtemperature e Ull16 Function. ! Two Notes modify SR 3.3.1.3. Note 1 indicates that the excore NIS channel shall be adjusted if the absolute difference between the incore and excore AFD is a 3%.4 2- 6.i[i@i.-d 0 3~3 96 ote 2 clarifies th e Surveillance is required only if reactor l CP-3.3 ED power is RTP. and that 24 hours is allowed for I performing 1rst Surveillance after reaching 19 $0! / RTP. The Frequency of every 3) EFPD is adequate. It is based on unit operating experience, considering instrument reliability and operating history data for instrument drift. Also, the slow changes in neutron flux during the fuel cycle can be detected during this interval. l l SR 3.3.1.4 ! SR 3.3.1.4 is the performance of a TADOT every 31 days on a STAGGERED TEST BASIS. This test shall verify OPERABILITY by actuation of the end devices. l 1 1 CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-52 10/3088 i

RTS Instrumentation B 3.3.1 BASES The Frequency of 92 EFPD is adequate. It is based on industry operating experience, considering instrument reliability and operating history data for instrument drift. SR 3.3.1.7 , SR 3.3.1.7 is the performance of a COT every E921 N days. l A COT is performed on each required channel to ensure the catire i channel will perform the intended Function. Setpoints must be within the Allowable Values specified in Table 3.3.1 1. The differcacc betw=n the currcat "as found" values and the previous test "n icft" v;1acs ;;;ust bc consistent with the drift all;w;=c used in the setpcint E thedclegy. The setpcint she M bc icft ;ct censistcat with the ass; ptics ;f the currcnt unit i spccific actpoint ;;.cthedelogy. ! The "as found" ;nd "as icft" valucs ;;;ust also be recordcd and rcvic cd for cen;istcacy with th; =s;;;;ptica cf Pcfcrcacc 7X SR 3.3.1.7 is modified by g!g@gege Note 3jthet provides a 4 hour delay in the requirement to perform this Surveillance for source range instrumertation when entering MODE 3 from NODE 2. This Note allows a normal shutdown to proceed without a delay for , testing in MODE 2 and for a short time in MODE 3 until the RTBs are open and SR 3.3.1.7 is no longer required to be performed. If the unit is to be in MODE 3 with the RTBs closed for > 4 hours this Surveillance must be performed prior to 4 hours after entry into MODE 3. .. O b: c .. w 3 . c br. ::+) P W h 48 /,' N.$ 7 /,j *

                                               . . - ^ 1) ;;) f  ' . ,l   '
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- f.; .A.W cP 3.3-ED

                         . 'm.ht-#U -:a" - - -M.(* ~.

fe..?.x ro The Frequency of E90} g days is justified in Reference EU SR 3.3.1.8 SR 3.3.1.8 is the performance of a COT as described in SR 3.3.1.7. emgt Mggit is modified by a thEBRie~) lote that this test shall include verification that the P-6 and P 10 interlocks are in their required state for the existing unit conditiong - - - - " - - " ~ ~ ~ ~ NIElt!N. The Frequency is modified by a Note that CPSES Markup ofNUREG-143I Bases - ITS 3.3 B 3.3-S4 102088

1 LOP DG Start Instrumentation B 3.3.5 BASES i l account for each individual component of loss of power detection and subsequent actions. j l The required channels of LOP DG start instrumentation, in l conjunction with the ESF systems powered from the DGs, provide ; unit protection in the event of any of the analyzed accidents l discussed in Reference 2, in which a loss of offsite power is assumed. The delay times assumed in the safety analysis for the ESF equipment include the 10 second DG start delay, and the appropriate sequencing delay, if applicable. The response times l for ESFAS actuated equipment in LC0 3.3.2. "Enginccred S;fcty l Featurc Actuation Systc;;; (ESFAS) Instra catatiqn." include the l appropriate DG loading and sequencing delay. The LOP DG start instrumentation channels satisfy Criterion 3 of the NRC Policy Statsant.30CE,tSOL36(c)RH19] LCO The LC0 for LOP DG start instrumentation requires that Ethrfe pil$ channels per bus of both the underMtag; icss of o.3,3 131 voltesc and degraded voltage Functions shall be OPERABLE in H0 DES 1, 2, 3, and 4 when the LOP DG start instrumentation supports safety systems associated with the ESFAS. In H0 DES 5 and 6, the [thre;] chenrels ;r.ust bc OPEPXLE 2crever the essociated 00 is rcquired to ha OPEPXLE to ca;ure that the cute;setic start of the 00 is ;;;ilabic s ca nu dcd.3 hereIfs CP 3.3-ED SWf_1c14Dt,sMgGHilab]ggLich]$haMDetitl103tartDfithe / m_ mm&_1 _ __wg LOS5 OT me LUP UU 5 tart umentation Function could result in the delay of safety systems initiation when required. This could lead to unacceptable consequences during accidents. During the loss of 4 offsite power the DG powers the motor driven auxiliary feedwater I pumps. Failure of these pumps to start would leave only one turbine driven pump, as well as an increased potential for a loss of decay heat removal through the secondary system. 1 APPLICABILITY The LOP DG Start Instrumentation Functions are required in H0 DES 1, 2, 3, and 4 because ESF Functions are designed to provide protection in these MODES. Actu tica in "00C S cr 5 is i required screver the required DC ;;;ust bc OPEPaLC so that it can (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-15S 10/30/98 m_ _. _ _

l l Containment Purge ad if.;;;t g!Lt11gBl Isolation Instrumentation ' B 3.3.6 i B 3.3 INSTRlMENTATION B 3.3.6 Containment Purg; ad Exh=;t MIsolation Instrumentation BASES BACKGROUND Containment purg ad exha;t jientilstgen isolation instrumentation closes the containment isolation valves in the Me+ CM PurgehPggg!agd"gogejejantitrgssure

  ,                     Belief System) ad the Shutdow Pu se Syste;;;. This action isolates the containment atmosphere from the environment to minimize releases of radioactivity in the event of an accident.

The "ini Purge ggggjggg1Trg_sstar#IRqr11pf System may be in use during reactor operation and the Shutdown gggainagg Purge System will be in use with the reactor shutdnwn " nim lijdtogegBRgCWgg3Mm3suppjeselgarKAV*tqq7fprh ^ _ e1:ecttigagigegeoggeestgategr .wwlL8TSMme dilutic!E18!i toBAeuneWolminyKMGM Eg!tModes3 throughmaggasseggemNre3magwesWJrtth3:he ., MCEPtidEIMBEMEBRMEM@ MERE 11(DEL 1M!E Containment purg; ad cxhs:;t ggj]gjpg isolation initiates on ; ad automatic grm safety injection (SI) signal through the ! Containment Isolation-Phase A Function. or by manual actuation l. of Phase A Isolation n ( c W 33igtsgien30GRd;41ngent i Sgttf. The Bases for LCO 3.3.2. " Engineered Safety Feature i Actuation System (ESFAS) Instrumentation." discuss these modes of l initiation. Four0ng Bit #1f5Eltnradiation monitor 4ng ch==ls are H also provided as input to the containment purge =d exh=st 96 R 11 M isolation. The four chenmis RgtggMmeasure! containment radiation at two gg locations. B R M biterl$3ples TatMstian chaal 1:; ; untai._.nt ;ra g;_e unitor. =d the othcr thru Inure redi;tien in ; : spic of the centsinnat purg; cxhmst. The thicc purgc cxha:t redi;tica detr.cters erc of thicc different typa . gucca;. partical;tc. ad iodin .eniter;. All four dctccter:; will resped te ;;;;;t scat:; th;t reic=c radietion to centair.xc.t. llcwacr. ;relyx:; hac not ban conducted t; dsenstretc th;t all credibic cunts will be dctccted by ;;ere th = 0x waiter. Thcicforc. for the purpex; cf thirs LC0 the (continued) l 1 3 i CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-163 10B0A8

CREFS Actuation Instrumentation B 3.3.7 BASES

2. Automatic Actuation Looic and Actuation Relays (continued)

Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 1.b., SI, in LCO 3.3.2. The applicable MODES and specified conditions for the CREFS portion of these functions are different end less cP 3.3 009 restrictive than those specified for their SI roles. If one or more of the SI functions becomes inoperable in such a manner that only the CREFS function is affected. the Conditions applicable to their SI function need not be entered. The less restrictive Actions specified for inoperability of the CREFS Functions specify sufficient compensatory measures for this case. Q 3.3-78 estMwitfahadititahei

                                                                                      ~
                                                                                        ~

3. Control Room Radiation The LC0 specifies tw rcquired Centrol nes;; f,t;;;;s@erc nediatien "eniters ;nd two required Control Room Air Intake Radiation Monitors W Rintake to ensure that the radiation monitoring instrumentation necessary to initiate the CREFS remains OPERABLE.

O CP 3.3 009 ttlWittSidpMBnfteclLM WMDictEfot!EIEEliMEB18Moul For sampling systems, channel OPERABILITY involves more than OPERABILITY of channel electronics. OPERABILITY may also require correct valve lineups, sample pump operation: cad filter : actor egration, as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety analyses. cP 3.3 ED i nummemmeen G; e--.memene ' 666.

4. Safety In.iection Refer to LC0 3.3.2 Function 1, for all initiating <

Functions and requirements. { CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-175 10/30/98 i

CREFS Actuation Instrumentation I B 3.3.7 BASES APPLICABILITY The CREFS Functions must be OPERABLE in H0 DES 1, 2, 3, 4 CP 3.3 009 M [r.r.d during C0"E ALE"ATIONS] and movement of 1rradiated fuel assemblies. The Functions must also be ! OPERABLE in H00ES M when required for a waste gas a.3.3.g.1 i decay tank rupture accident, to ensure a habitable environment for the control room operators. ACTIONS The most common cause of channel inoperability is outright failure or drift of the bistable or process module sufficient to exceed the tolerance allowed by the unit specific calibration procedures. Typically, the drift is found to be small and results in a delay of actuation rather than a total loss of function. This determination is generally made during the performance of a COT, when the process instrumentation is set up for adjustment to bring it within specification. If the Trip Setpoint is less conservative than the tolerance specified~ty the calibration procedure, the channel must be declared inoperable immediately and the appropriate Condition entered. A Note has been added to the ACTIONS indicating that separate Condition entry is allowed for each Function. The Conditions of l this Specification may be entered independently for each Function i listed in Table 3.3.71 in the accompanying LCO. The Completion i Time (s) of the inoperable channel (s)/ train (s) of a Function will i be tracked separately for each Function starting'from the time the Condition was entered for that Function. ; l A. and M CP-3.3 ED Condition A applies to the actuation logic train Function of the CREFS, the radiation monitor channel Functions, and the , manual channel Functions. If one train is inoperable, or one radiation monitor channel is inoperable in one or more Functions, 7 days are permitted to restore it to OPERABLE status. The 7 day Completion Time is the same as is allowed if one train of the mechanical portion of the system is inoperable. The basis for this Completion Time is the same as provided in LCO 3.7.10. If the channel / train cannot be restored to OPERABLE status, one-th0BffB33ECREFS train must be placed in the emergency radiction pr;tectier.EBc14Eg1LTRl mode of operation. This accomplishes the actuation instrumentation Function and places the unit in a conservative mode of operation. CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-176 10B088 m

1 l l CREFS Actuation Instrumentation B 3.3.7 BASES should read approximately the same value. Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something i even more serious. A CHANNEL CHECK will detect gross channel I failure: thus, it is key to verifying the instrumentation contimes to operate properly between each CHANNEL CALIBRATION. Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal. but more frequent, checks of channels during normal operational 'use of the displays associated with the LC0 required l channels. SR 3.3.7.2-A COT is performed once every 92 days on each required channel to ensure the entire channel will perform the intended function. This test verifies the capability of the instrumentation to provide the i CREFS actuation. The setpoints shall be left consistent with the l unit specific calibration procedure tolerance. The Frequency is - based on the known reliability of the monitoring equipment and has i been shown to be acceptable through operating experience. D SR 3.3.7.3 M SR 3.3.7.3 is th; perfernnce of en A"UATION LOCIC TEST. The trein b;ing tested is pined in the bpass cenditien, thus picuating inedactcat ;ctuation. Through the sc ieuto ctic

                         ' t;;;ter, ;11 pe;;ibi; 1;;ic edin; tion;;, With ;,nd without
                           ;.pplic;ble gr.;issivas, era tested for exh pr;tation furation.

In ;;dditi;n th; Ester r:1;y Gil i; pul;c t;sted for cer,tinuity. Eis arifies th;t th; logic ;;;;dules ;rc OP rJ.0LE nd thccc is en inteet v;1t;;;; signi p;th t; the a:;tcr rci;y coils. This test is perfe.ied enry 31 d;ys on : STA00EREO TEST BASIS. The Ircqu acy is justified in '.C'T 10271 P A, Suppicni.t 2, R;;.1 (R;f.1). CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-179 108038

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP-3.3-001 APPLICABILITY: DC, CP REQUEST: CN 12-06-LG for CTS Section 3/4.6 indicated that calibration details required by SR 4.6.4.1.b '(4.6.4.1 for DCPP) were moved to the ITS Bases for SR 3.3.3.2. The Bases description of those details was inadvertently omitted in the submittal and is being added now. ATTACHED PAGES: Enci 5B B 3.3-145 l l

'A

PAM Instrumentation B 3.3.3 BASES during normal operational use of the displays associated with the . LCO required channels. N ganammamannessmmwers.wa c: . : . u .a Jm

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e_ -._M - JEe- -- n=rme . D!!EDanmanaD_se_OpenufgeerJsE#3aRAGA9881 SR 3.3.3.03 A CHANNEL CALIBRATION is performed every Ig months, or approximately at every refueling. CHANNEL CALIBRATION is a complete ch.eck of the instrument loop, including the sensor. The test verifies that the channel responds to measured parameter with the necessary range and accuracy. This SR is modified by a Note that excludes neuteen detecters. ,j The calibr: tion Ethed for neutren det;;ters is ;p;;ified in the "e:;cs di LOO 3.3.1 c;;ter Trip Syst;;;; ( !

                                 ~_""-,                              ---_"TS)         -                         Instrun.,tation."                __

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ADDITIONAL INFORMATION COVER SHEET - ADDITIONAL INFORMATION NO: CP-3.3-002 APPLICABILITY: CP REQUEST: l CN 7-06-LG for CTS Section 3/4.3 indicated that the readout location of remote shutdown instrumentation would be moved to the Bases for ITS 3.3.4. The Bases description of the ) location was inadvertently omitted from the submittal and is being added now. ATTACHED PAGES: Enci5B B 3.3-146

~.

\ 4 4-

Remote Shutdown System B 3.3.4 i B 3.3 INSTRUMENTATION B 3.3.4 Remote Shutdown System BASES BACKGROUND A safe shutdown condition is defined as H0DE 3. With the unit in H0DE 3, the Auxiliary Feedwater (AFW) System and the steam generator (SG) safety valves or the SG atmospheric dump tejjef valves fABVsM&tig can be used to remove core decay heat and meet all safety requirements. The long term supply of water for the AFW System and the ability to borate the Reactor Coolant System (RCS) from outside the control room allows extended operation in MODE 3. If the control room becomes inaccessible, the operators can . establish control at the rente Hot?!hutdown Panel, and place I and maintain the unit in MODE 3. Not all controls and necessary transfer switches are located at the reste Hot Ehutdownganel. Some controls and transfer switches will

CP 3.3 009 have to be operated locally at the switchgear, motor .

control panels, th6TshotdDFdnitrinsfMIDggj] or other local ' stations. The unit automatically reaches H00E 3 following a unit shutdown and can be maintained safely in H00E 3 for an extended period of time. The OPERABILITY of the ggleggg3 lERRretHremote shutdown 0 3.3 24 i controlg and thB M instrumentation functions ensures there is sufficient information available on selected unit parameters to place and maintain the uni in , rol room become iraccessi CP-3.3 002 l EENcDERs6MBaltchti!~M naamsman . i Cotgrgil!BttWigyR3RitMB(frHtMEghdMgiters)J

                               !    BCE39s6 0 3.3 24     l i     ogay2eatnesMA]EE9itheWWSystesTaEthe:SG g                       gg                                  0-7 08a    l 1     emnasemmmutums (continued)

CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-146 102088

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP-3.3-003 APPLICABILITY: CP REQUEST: Revised Enclosures 2,3A and 3B of CTS 2.0, and Enclosures 5A,6A and 6B of ITS 3.3 to reflect new overtemperature N-16 trip setpoint parameters recently approved for CPSES Unit 2 in CTS LA 55/41 and submitted for Unit 1 in LAR 97-003. DOC 2-08-A was added to Attachment 5 (CTS markup for 2.0) and JFD 3.3-138 was added to Attachment 9 (ITS markup for 3.3). ATTACHED PAGES: Attachment 5: enci 2 - page 2-9,2-10 and 2-11 3 enci 3A - page 1 enci 3B - page 1 Attachment 9: enc! SA - page 3.3-23 enci 6A - page 14 enci 6B - page 21 _ 0

TABLE 2.2-1 (Continued) TABLE NOTATIONS NOTE 1: Overtemperature N-16 c ;;,yg N = K - K2 f1+ 15 T, - T,*] + K (P P2) - f (aq) i 3 t 1+ 25 Where: N = Heasured N-16 Power by ion chambers. T - Cold leg temperature. F. T,' = 560.5 F for Unit 1, 560.8 F for Unit 2 - Reference T, at RATED THERMAL POWER, . K = 1.150. i K, 4 d173 W.,F for Unit 1

                                                                                       = 0.0135/T Tor Unit 2                                                                                                                                                                                                                                         h((003 i

CPSESMarkup efCTS2.0 2-9 10B0/98

= :w 2 x == :.u: .x. u . , .; : = x , -. , . _ _ ___ _ _ _ TABLE 2.2-1 (Continued) TABLE NOTATIONS (Continued) LOTE 1: (Continued) s. It_td = The function generated by the lead-lag controller for Tc 1+ t,5 dynamic compensation, ti. tr

                                                                                                   - Time constants utilized in the lead lag controller for T,.i 210s, and 1, s 3s, t

w 02 08-A

K3 ~ CP-3.3-003

                                                          =                                         0-000899pjp;d;
                                                                                                          .voo7^0/p;i                                  C'psig r Unit  2 for Unit 1 P               =                                         Pressurizer pressure, psig.

P' E 2235 psig (Nominal RCS operating pressure), S - Laplace transform operator, s , and f (a q) is a function of the indicated difference between top and bottom halves of detectors of the power-range t neutron ion chambers with gains to be selected based on measured instrument response during plant STARTTJP tests such that: CPSESMarkup ofCTS 2.0 2-10 10B088

TABLE 2.2-1 (Continued)

TARIF NOTATIONS (Continued)

NOTE 1: (Continued) For Unit 1 (1) for q, - q, between -65% and . J0.t f (a q) = 0, where q, and q, are percent RATED THERMAL i POWER in the top and bottom h the core respectively, and q, + q, is total THERMAL POWER in percent of RATED THEIW I. POWER, (( (ii) for each percent that the magnitude of q, - q, exceeds -65%, the N-16 Trip Setpoint shal - automatically reduced by 0.0t* of its value at RATED THERMAL POWER, and for each percent that the maani u of q, - q, exceeds . ' he N 16 Trip Setpoint shall be i (iii) automatically reduced by its value at RAltu mtNMAL POWER.

             *gNo setpoint reduction is required for the span of the al indication.

[ For Unit 2

                                                                                                                                                                            , f (a  q) = 0, where q,' and q, are percent RATED (1)                                     for q, - q, between -65% and +h5                                                                        1 POWER in the top and bottom ha ves of the core respectively, and q, + q, is total THERMAL POWER in percent of RATED THERMAL POWER, E

for each percent that the ma itude exceeds -65%, the N-16 Trip Setpoint shal (ii) 1 automatically reduced by ._ , of its value at RATED THERMAL POWER, and

(iii) for each percent that the magnit xceeds M the N-16 Trip Setpoint shal automatically reduced b@_4 of its value at RAltu mtNMAL POWER.

fli52Wwii_L--_. =wnmmus- -s7MAMCBt10ft! , NOTE 2: The channel's maximum Trin waai span.for Unit 2. t exceed its computed Trip Setpoint by more tha gi of span for Unit 1 o @ lAi66%) 1 2-n is'3sw crsesua,s.,e .1as u C -_____ ___ _._ _ _ ___ _ _ _ _______ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-70 APPLICABILITY: CP l l REQUEST: The PAM instrumentation list is modified to reflect the CPSES design and current TS. I Comment: The heading to ITS Table 3.3.3-1 references a non-existant Condition J.1. Provide a corrected ITS page. Table 3.3.3-1, F11 is added as is Note (b). Provide a safety basis discussion for these changes to CTS. FLOG RESPONSE: The words "and J.1" are removed from the column heading in ITS Table 3.3.3-1.

ITS Functional Unit 11 with required number of channels 2N is equivalent to CTS LCO 3.6.4.1 l which requires that two independent containment hydrogen monitor trains (with at least one l channel per train) be OPERABLE. Note (b) states that a channel consists of two sensors per train and that a channelis considered OPERABLE if one sensor is OPERABLE.

A " train" as discussed in CTS 3.6.4.1 is equivalent to a " channel" as listed in ITS table 3.3.3-1. in both documents "2" are required. . A " channel" as discussed in CTS 3.6.4.1 is equivalent to a " sensor" as discussed in ITS table 3.3.3-1 note (b). In both documents, only one is required per " train" (CTS) or " channel" (ITS) for the respective " train"/" channel" to be OPERABLE. Because the CTS and ITS are equivalent and only the terminology has changed, no additional justification is required;for this change. In addition, the CTS list of functions is retained in the ITS Table 3.3.3-1. Specifically, the requirement for Auxiliary Feedwater Flow Rate and Steam Generator Water Level (Wide Range)is retained. ATTACHED PAGES: l Enci SA 3.3-48 and 3.3-49 Enci5B B 3.3-128, B 3.3-139, B 3.3-141 and B 3.3-142 i l l

PAM Instrumentation 3.3.3 Table 3.3.31 (page 1 of 2) Post Accident Monitoring Instrumentation CONDITION . _ _ _ REFERENCED FROM FUNCTION REQUIRED REQUIRED 3.3-70 0-3.3 70 CHANNELS ACTIONS E.1 V&V

1. Icwcr Rong; ".cutren Flux Litua.llggggg 2 F BQtalltWanlCM

2. Scurc; Rang: "cutren Flux 2Subcoo11og 2 F ll0@.t&t

3. Reactor Coolant System (RCS) Hot Leg a 1 per loop F CP 3.3 007 l Taperature JWideIRangel L1

4. RCS Cold Leg Temperature ~ jpide~RggeJEUm). e i per loop F

5. RCS Pressure (Wide Range) 2 F

6. Reactor Vessel Water Level 2W G ~.

7. Containment Sump Water Level (Wide Range) 2 F

8. Containment Pressure (W4de }rttet99dipg 2 F Range)

E2 SMBES$1MLN gi@tSte8J B MM 9: Contair.;;nt Ocletion '.'eh; .";sition 2-pee F M n = p:th *"*

10. Containment Area Radiation (High Range) 2 G

11. Hydrogen Monitors 28 F

12. Pressurizer Egg Level 2 F

13. Steam Generator Water Level (WMe umER 2 per steam F l Range) generator

14. Condensate Storage Tank Level 2 F (continued)

CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-48 102088

PAM Instrumentation ! 3.3.3 Table 3.3.3-1 (page 2 of 2) s Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM 3.3 70 REQUIRED REQUIRED 0 3 3 70 FUNCTION CHANNELS ACTI E

15. CoreExitTemperature-Quadranti 2(*) F

16. Core Exit Temperature - Quadrant 2 2(*) F

17. CoreExitTemperature-Quadrant] 2(*) F

18. CoreExitTemperature-Quadrantj 2(*) F

19. Auxiliary Feedwater Flow

                                ._; AFW Flow                                                                                       2 per steam                                F generator                                                           3.3 70    ,

, g -

                                                                                                                                                                                   -f                    0-3.3 70 l 8FiflgCgLdi}$gg~Ae!!ggg]3@g                                                              1;Qggch3g OtftlfdMMORa!! gel                                                                 staanJgenetRtor                a (a)             %;t . ; quired for i cletion velv^^ J.0;; ;- ;;ieted F ratration i; i ci;ted by

t 1;;;t era cle;-d end da ctiv;ted = ten ti; velv;. ci;;;d = n;;l v;1v;. blir.d%3330'Il

                              'l ars;;.          cr cha'a velv; with flow thrn;h th; valv; ;;;; red.2,; sate.

ggr[Iggots"$8WptabEBR mtggggggNettt RE B orspitE M P e M O r c 1. ;? . A .A~ ..i.e.c % j , gggggi. (b) Only er.; p;itics indi;; tion cher.ral i; required for gratretien 'l;W pth; l

                              ..,Au..-..,.,..
                                                      . , ~  2,,sa
                                                                -  A.u.,      ,.;
                                                                                         ..u.  . ,.- ---
                                                                                                     .. . ,  . 2, . . A. s. . . wu. - .,. ~- ,. .
                                                                                                                                                           -              w         _.

QKya._ MN Md m i t

           - (c)            . A channel consists of two core exit thermocouples (CETs).

i n-.2-..- .. at A . v L1. e e e 1 .L.11 L. ---_J J E-- .- L . ._ J A .. _----..-..A. 1J.A. M l nw w s w . e syv ww . suwsw w.w.w A wi su s a ww w w. rwww a ve w wwi s vi s a w wa . swww a au s y wv i saw. fis a11 n - -. 1 . A - - . . r*. . J J. 1 n-r v._- a 2-_A..._-_A. __; j gas nia nwyusu6viJ wusww 6.si. syp n a s sa ws w w.s wa . unw j . tn\ a19 n - -. 1 . A - - . F. 2 J- 1 n-r t'.A----.. s --- v . .- - n a . L - . - - .1 4 gs / nia nwyu u u svi g wusww A.si. wussyvig 4 irvis agp n s isa 6a u w.s wa in enerde a; with th; unit *; " sulatery Ouid; 1."7. S;f;ty Evalu tion ",;prt. i t . CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-49 10/3088 j i 4

PAM Instrumentation B 3.3.3 BASES ! M The specific instrument Functions listed in Table 3.3.31 are discussed in the LCO tgtgeg. APPLICABLE The PAM instrumentation ensures the operability of SAFELY ANALYSES Regulatory Guide 1.97 Type A and sel_ec_tejdon-Type ~A Category 11 l variables so that the control room operating staff can:

                         . Perform the diagnosis specified in the emergency operating procedures (these variables are restricted to preplanned actions for the primary success path of DBAs), e.g., loss of coolant accident (LOCA):

[ l . Take the specified, pre planned, manually controlled actions. l for which no automatic control is provided and that are required for safety systems to accomplish :beir safety function; j . Determine whether systems important to safety are l performing their intended functions: t . Determine the likelihood of a gross breach of the barriers to l radioactivity release; i i . Determine if a gross breach of a barrier has occurred: and

                         . Initiate action necessary to protect the public and to estimate l                             the magnitude of any impending threat.

PAM instrumentation that meets the definition of Type A in Regulatory Guide 1.97 satisfies Criterion 3 of the OC clicy Statement m ]. It!$g;[gg Category i ), non Type A, instrumentation must be retained in TS because i it is intended to assist operators in minimizing the consequences of accidents. Therefore, felectEd Category i CP 3.3 009

1. non Type A variables are important for reducing public risk g 6 T,E pf21g g Epl36( M DBU).

(contin $d) CPSES Markup ofNUREG-1431 Bases -3.3 B 3.3-128 10B088

l l PAM Instrumentation B 3.3.3

BASES l 1

d Two OPERABLE channels - N f Core Exit Temperature are required in CP-3,3-009 i each quadrant BRERFBEt; praii indication of radial

_,.u. _ _ _ , _ _ , .- __ . . _ _ ______

2 2. i. _2. .. < . . 2. ._ _.

                                                                           .v.         ..     . . . . .           .          ys .          . . . .       ._2. ._n_.. . . .

4' n_.__

                                              .________A_A w y. b ,wa s ww            u . .Ly

a. . .. _ _v._~.A.L.w.

a.

                                                                                                               . v_ww. ib .
                                                                                                                                     . a _ c    s wwww. osau Ja_A.             L 2.v..A2__

u o s vi . s;; ;try w;; ;;nsiired in iterainin- the spaific as;ber er.d 1;;; tie. praiid for dieg ;;is of local ;;re prabl;;;. .crefor;, tu; r=d;;ly ;;l;;tcd ther;;;;uplcs

ere n;t: afficient to x;t the tw; therrxeuple: per

, char.cl r;quir;.nnt in any qu; drat. W tw; therex euples in cach chanci u;t ;xt the addition;l r quir;xat th;t ene-i; locat-d ac;r th; ;;nter of the cr ad th; othcr

,                                             nn- the ar; perinter, such th;t the p;ir of 007 Sit
                                              ,_         ___..                  ,_s,__                      _.s,.,                   -                                __.2,__

v ou . ... , . u-ys u .. . .. _ _o._ .. .. .. a.u.

                                                                                                      .~ . ou               .      .--ys ....__--_-..u
                                               ;;res: their arc quadrant. Two sets of two thermocouples ensure a single failure will not disable the ability to i                                               determine the R$egRicfcofB:orO@TV4 radial t;;ycroture seed 4ent.                                                                                                                                   -

i-j CETsT&TRO@Ptje]1npo_tItF2tM~50tuf6011 rid Itonit_ofj

19. tretuisteamm8 tor y o.3.3 70 g AdttMEhm&EidERMPEE2drit!MbPERSHMEatstrast:EWat fable 4

i

Wg .,s L c. . + t ' ' wt ..

                                                                                              .                                       ./..#.-
                                                                                                                                       . .                      m 3;;.
                                               ,                     v . .. '. t - . . / D i* '. d t:T * : .i et r G'h ' .s. d 7 td g,.'J4r q .,.. . .                         .
                                                                                            <: - g , .;f g . . z . ;.                                    .
                                                                                                                                                                            . . , , g.

3 g; T. L .: 7? ? ; e, y .. A _ ; . i . g , ;.% , . .v E -

                                                                             .:                . . .. .           1,   -               Flow             is   provided                  to monitor operation of decay heat removal via the SGs. M

{ ,n / ,e :' . ; '. ' '-'g..y

                                                                                                                                                                .'. .'g ,y . , .
                                                 ' 0, " . Q                                                               .        s     ,'-

4

t. . . -

1 p;.... . . . . . . . . . . . . w.3,~ .

. - . ; e ,, .. 3w The AfV Flow to each SG is determined from a differential pressure measurement calibrated for a range of 0 gpm to M00lllgpm. Redundant monitoring capability is provided bytwoindependenttrainsoffl3Riinstrumentationforeach SG. Each differential pressure transmitter provides an I input to a control room indicator and the unit computer.

Since the primary indication used by the operator during an j I (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-139 10B0M8

 .~            . _      __      _   _        . __ _                   _-        . _ . . _ _       _._ _     _      ._

l PAM Instrumentation , j B 3.3.3 i l BASES i l instruments and methods, and the low probability of an event l requiring these instruments. Note 2 has been added in the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification ) may be entered independently for each Function listed on ) l Table 3.3.31. The Completion Time (s) of the inoperable ! channel (s) of a Function will be tracked separately for each l Function starting from the time the Condition was entered for that Function. KNZChKikiirVM3sbje3I53 pWspetsfBitDXteriM1petaipepxor;peran 3sg 0-3.340 H sr.,1. :.^pitheT,onosuon;may_ne;enostes separ_ ate 13 forleacKMporssteas11ra.i.,,. ;;.;.,;z. -(Isfappropti_atej u 1 Condition A applies when one or more Functions have one required l channel that is inoperable. Required Action A.1 requires ! restoring the inoperable channel to OPERABLE status within 30 days. The 30 day Completion Time is based on operating, i j experience and takes into account the remaining OPERABLE channel (or in the case of a Function that has only one required channel, other non Regulatory Guide 1.97 instrument channels to monitor the Function), the passive nature of the instrument (no critical automatic action is assumed to occur from these ! instruments), and the low probability of an event requiring PAM instrumentation during this interval. Rup1,geltajpegreattie iepl61t6tfaliescomitttMB3M . l SEi-Ml*OXpi@tEnBGhi! l [M1 6 M CP-3.3-009 Condition B applies when the Required Action and associated ! Completion Time for Condition A are not met. This Required Action specifies initiation of actions in Specification 5.6.8, i which requires a written report to be submitted to the NRC

                                                                   . This report discusses

! the results of the re;t c:us cv;1 action of the ir,eper:bility er.d idcr.tifics preposed restorative actions. This ; tier. is opproprietc IIDINWutRtidD0fRhe'9rjeplminedMterateethod:#f ls6h1613tTNNiH130in lieu of a j shutdown requirement since alternative actions are identified before loss of functional (continued) CPSES Markup ofNUREG-1431 Bases -3.3 B 3.3-141 103088

l l PAM Instrumentation B 3.3.3 BASES capability, and given the likelihood of unit conditions that would require information provided by this instrumentation. Ca.1 Condition C applies when one or more Functions have two inoperable required channels (i.e., two channels inoperable in , the same FunctionGone regelredA"channelTand'one? required CoreiExitlemperature'channellinoperablh;o? required _Tm channeliand onelrequired15 team line'PressUrb chariiici im 3 the aunMated: loop'irmrarahlQrisni;GenacW.egr;Q1 U,C )McT3;ECl_ M dCTrGG d ~0Gd Odi D r.oCllNGi,CrGbkor' *0-3.3-70

          - ' " E cT ratalf Kequired Action c.1 requo es restoring

one channel in the Function (s) to OPERABLE status within 7 days. The Completion Time of 7 days is based on the relatively low probability of an event requiring PAM instrument operation and the availability of alternate means to obtain tae ;

required information. Implementation of_,theZpreplanned ) al_t.ernate; method l, ofisonj torjngTper_Specif1 cation;51618.ii s tequi refprjiorltolexpi_ratiofqfithe".Compl eti.onlRmeli - CP-3'3-009 l i Continuous operation with two required channels inoperable in a Function is not acceptable because the alternate indications may not fully meet all performance qualification requirements aplied to the PAM instrumentation. Therefore, requiring

                  'tratiot, af.' one inoperable channel of the Function limits the risk that the PAM Function will be in a degraded condition should an accident occur. Condition C is modified by a Note that excludes hydrogen monitor channels.

[L1 Condition D applies when two hydrogen monitor channels are inoperable. Required Action D.1 requires restoring one hydrogen monitor channel to OPERABLE status within 72 hours. The 72 hour Completion Time is reasonable based on the backup capability of the Post Accident Sampling System to monitor the hydrogen concentration for evaluation of core damage and to provide information for operator decisions. Also, it is unlikely that a LOCA (which would cause core damage) would occur during this time. (continued) B 3.3- M 2

~.

i l l' ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-73 APPLICABILITY: CP REQUEST: The CPSES CTS actions for inoperable functions are retained in the ITS. Comment: To retain the CTS Action, manual initiation must be listed with T3.3-2 Action 15 equivalent actions in the ITS. FLOG RESPONSE: As agreed upon during the meetings held between the NRC staff and the FLOG members during the week of September 14,1998, the ITS 3.3.6 Condition B, Required Action B.1, Condition C, and Required Action C.1, including all associated Notes and completion times, have been revised to more accurately reflect the CTS requirements in the ITS format. l Similar changes are made to ITS Table 3.3.6-1. No changes to the CTS requirements are necessary. ATTACHED PAGES: EnclSA 3.3-58 and 3.3-59 , Enci5B B '3.3-166, B 3.3-168 and B 3.3-169 e i l i I

                     ..               --                .- .      - .                  .__.                     . . . . .        ~   ___ - -           . - . . - .                  _.   -.-

Containment 3dnCHg33l Purs; and Ed.cust Isolation Instrumentation ? 3.3.6 ACTIONS (continued) CONDITION REQUIRED ACTION CONPLETION TIME B. ------- NOTE......... .amummmmmmmmmmmmmmes famedtetely 4 .x Only applicable in MNm ggggg '~~ MWtm MODE _1, 2. 3. or_4 3 mummamanummmmmansumes

a n u -L. 2s.: .2 .:.ir?

                                                                                                            . ;. . . 3L..a                                                 pq q
                                                                    -    A.. n e . :.
                                                                                . . .                                   .0*

Ei M - One or more&congg

                  '~ gn_,.gilgManj!                           B.1 Enter applicabic Cerditions erd R; quired Actions of M.

r.. _ _ , 2. ._ _. ._g M ays

        .-~             .   ..m.... ..
                                                   ..                .m.rn.
                                                                                .....,                .r.__.m.._2.._._.m_._..

____ ___..., __ ..~___;2 N !

        --tuati--Trains                                      \        ;_;;;;$;_ i,,;,.,.;_ . f;[.[t                                                                               +

inoperable. RggGWe$23BeliM 3 3 72 gggg 0 3.3 73

        %                                                             1$916 M 410t 93908) tainment T'.;; er ;r.;re r:di; tion .                                                                    purs; :nd
        ;;.enitorin; ch;nacis
        ,______u._.

eh isolation valvd[ _ E, gig

         .. r..                                                   u                          - - -

E , ir.ep;reble -y .;;istion R$NU.t#C66)iNEtht) instru;;ntation. I

               .1       t,   7 . .Lg n   v R        '.s      m $ t :..t a

C; quired Action and

        ...,_2.a.~_sr.___.,,._s.2..__..

r2__ - .s n __

         . s sum   .e. r..i s

2. bx 2. ._ _.#. .s met-(continued) s.

I a: CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-$8 10B088

Containment';Evas "ur;; cred " hau:t a Isolation Instrumentation WWPS E 3.3.6 ACTIONS (continued) , 1 CONDITION REQUIRED ACTION COMPLETION TIME C. - M .' ; - c .. - d . u m

                       . J ' & L. f.i;.. :                       ;
                                                                                     ~'
                                                                                                . ] . g.R L . . .;

3 73

   - mm    ..<

a.4.u. 7 a - mmHnN

                                                                                           . ;s y : 4,g ;.                                                    r h', g.,y me =H=Tja                                                  agtme!BfEMa11;3M                                                                                               ]

klATf" syv 5 6 } Or.ly pplicabic duri--

M*ET 3 1 00"C AlT""'T!0'E cr C.1 Place and maintain Immediately

       ; n.~_r.t eof                  irradict f                containment                       3BERJt%n
      ..w.
                 .. ..         ,s2,w.. . .u u, s     . a bs   .,

r , e u... ...u.u.... m ub valves in 03;$ 72A. closed position.

     ;;,, tai n.ste

( - BB - l n_. ._ --_. e.._.ss._. . I Vssu v3 ursvs w a wilw b I vi ad

     ..u          _ _ . . _ - - _ . _ . _ . . . ,         e ,   r_z._           .._,,..u,.                    c._ sus._.          ,--n..,..

su a ha s vssw vi serva w urvue suu 5 wE bli kw a up5 awuvsw w vsau s bavsse s avai~ u a u bw s J p.-gg-ea

             . . . a _     A. J -      ..&..&J._                ._J        M....J_.J               A AJ            . .,                                          aA W e7. kw.m va. uw bvissu b a w u w bu u bivis                         ustw aswqu s a ww n w b ivisa v3

b. u ..s. 2_~___.u,.

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                                                                .rn , n www           . . , . , ..     .e.,_.~__.m ww. s b     u a s     .

n-__m_. . _. . ,._

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                                                                ..L....A              J . 1.a a _ . . . , . . .

was suu d h s av a u b a vi s vuswwd

     ,... ._ ---- _ . n . u ._                                  ..J.          ,_-_.u,.u..                          a..,.u._

a sv vi asevs w s uw a u b s vu s suvuww eesvywa uwzw WJ eav3u bavis

         -_u        _2__         .t.__.,.                       2 _ _.              m . m ._

serva a e kv1 ss# vs aus 53 sw I d I I ud b u names ~s s b u b a vi s . J.

          ~- - - _ w.w. u. L , 3 e.

E m gg m ,o ..w .,3 4 Mmmate0.9

                                                                                                                                                          \                    i R         ired Action and                                  ammmmmmmmmmmmamamenne 3 3 72         l associated Comp1 etion                                    naammmmmmmmmmmmemmum                                                                                           !

Q 3.3-73 ; Time for Condition A no - : met. nummmmpummmmmmmmmmen l M y .- .a.

                                                                       .,i~         ..,,t~..n                                                                                  1
                                                                   .t .

CPSESMarkup ofNUREG-1431- ITS 3.3 3.3-59 10B088

    .- . - =         _ . - - - .      .  .-             -            . -                            . _ -           - - . -..                          - - - .                  -          -

. Containment "ur;; ;nd Sh;ust EtREEMRI Isolation Instrumentatitn B 3.3.t.

BASES such a manner that only the Containment Ptege m 1 Isolation Function is affected, the Conditions applicable

to their SI and Phase A isolation Furictions need not be entered. The less restrictive Actions specified for i j inoperability of the Containment Ptege m Isolation Functions specify sufficient compensatory ,

I i measures for this case. i

3. Containment Radiation i

The LC0 specifies fote egf; required tgWitjsg honttodng channels of r;di; tion e.. iter; to ensure that the radiation , monitoring instrumentation necessary to initiate ! Containment Ptege [qgt$13%)gg Isolation remains OPERABLE. l For sampling systems, channel OPERABILITY involves more

!                                         than OPERABILITY of the channel electronics. OPERABILITY

', may also require correct valve lineups, ggl sample pump 1 operation, ;nd filter ; tor eg ; tion, as well as detector OPERABILITY, if these supporting features are necessary for trip to occur undar & conditions assumed by the safety

analycac M - _ _ _ y _

                                               .]. f b' . . n . e ct. .:q e a n ._ qf (.y . q ,.. ' c.:a fr i -

t - 2 0 3.3-73 4 4. Containment Isolation-Phase A Refer to LC0 3.3.2, Function 3.a., for all initiating Functions and requirements. _ y ; .. . .

g_m ......y

                                                                                                                                      - .. ~        :                   M                      l
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i I (continued) CPSEShfarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3166 10B088

Containment "urg; ;nd Shoust ]LentDaf_1pr.! Isolation Instrumentation B 3.3.6 , l BASES (continued) separately for each Function starting from the time the Condition I was entered for that Function. A.1 Condition A applies to the failurc of en; cent;ir.;;.r.t purg; h -lation radiation monitor channel g3pIREtgqgK m g ggglffgigghW. Since the fair containment radiation monitors meastreg the2cntaiggPDtugdphere3ndTDtDtldesm f afgnal diffcrent per;.;,.tcra, failurc of a singic chenrel the

excessReIgrjp settf8g may result in less of degtagj]the radiatic, monitoring Function for c;rtain recnts. Consequently, the fe4kd channel must be restored to OPERABLE status. The 4 hours ailowed to restore the affected channel is justified by the low lidelihood of events occurring during this interval-end recognit4on that on; er ;;re of the r;;;ining ch;r.rel- .;ill respond te r.;;st re nts. IL1 Condition B applies to all Containment "urg; and Exhaust Vent 11attini IsolatipsfutogMC%$uatioqiggiciend'7 Z$ deTays ruratiensind addresses une u am voencauon or tne Solid State Protection System (SSPS) and the master and slave relays for6** *he#lFunctionL/ a .. . . ;3sc Ir.c Tei .s.-e 07 uitip;c recie::;r. eenitoring che.ncis. er the in;bility t; restcr a single fail-d thenrel to 0"C""."LE status in the tiec

                               ,,_.._2   m_                             . ,

j .

                                ..-...o,w.,__>._2..__. ..m. om      . m... m W W h 3tEtht!

jl g b w h n e r 4 a - < .,L. w s If a train is inoperable.6ti;1: chenrels ;ra inep;rab 3.3 73 or the Required Action and associated Completion ilme of Condition A are not met, operation may continue as long as the Required Action for the applicable Conditions of LC0 3.6.31 ! met for each valve made inoperable by failure of isolation instrumentation. KMD%fMBddett?t03MEREKMetttUtentiissestafemenWst C]dEe4H00rJ$hi4 6 MWlAWEXIM IDED8BWp_s2ftER!Blamiscammstsamtatsmanettswega RettS3tf3th6MC.M A Note is added stating that Condition B is only applicable in H0DE 1, 2. 3, or 4. (. (continued) CPSES Markup ofNUREG-1431 Bases - HS 3.3 B 3.3-168 103088

l l Containment Pur;c and Exh= st IgS S Atigg Isolation Instrumentation B 3.3.6 l BASES (continued) C.1 and C.2 Condition C applies tn "!! Cont;inant~ : Par;; x, ahnst Isol;;tir ruxtions and eddres= ; the tr;in cricatation l l a' of th 00PS ad th; = ster ad ;leve rclays for thcx Tunctions. It lz eddicsx:; the f;ilurc of ;;;ulticle _D;; diction

                                   - - - Mori= "=' t ritne inability to restore ; single failed                                            I jilgT_6 channel to OPERABLE status in the time                                                         l allowed for Required Action A.I. If tr;in is inegr:bic.                                                 '
                                   ;;;ultipic churcis arc ir.egrebic, or the Required Action and

, associated Completion Time of Condition A are not met, operation , l may continue as long as the Required Action to place and maintain j l i containment purg; sad cxhou';t gentilatforj isolation valves in ( l their closed position is met or the applicable Conditions of , t 0 3'3 73 1 l LCO 3.9.4, " Containment Penetrations," are met for each valve l made inoperable by failure of isolation instrumentation. A , _ note r a11oir4heTcontainsight"WMrelfervaWertstronened l

                                   ;;yjp="';, .1 iER.d inieJplianceMthTDasecur . uent detlitorMig3pitudethtatjanWsiin7PartT .' heIE)CMg a Cumpieu en n me ror these Required Actions is Immediate,1y.

l l A Note states that Condition C is applicable during CORE , ALTERATIONS and during movement of irradiated fuel assemblies i within centainment. ! 1 i

SURVEILLANCE A Note has been added to the SR Table to clarify that i i REQUIREMENTS Table 3.3.6-1 determines which SRs Ot;herithdEESEiRliRONSE

! 11 7 f .d+W4 A M c . -apply to which Containment I rur;c ad Exhou:;t M Isolation Functions. M o 3.3 55 mm m m

                                    ,,7    p ; . s m .L ; ;

SR 3.3.6.1 Performance of the CHANNEL CHECK once every 12 hours ensures that a gross failure of instrumentation has not occurred. A C"." L C"CCK is ner;;;;11y ; capri:;= cf th; gr=;tcr indicated on ene ch=xi t; ; :;i;;;il;;r pera;ter = ;thcr ch=xis. It i'; bacd on i the ;nu;;;ption that instruant chenxis ;;;;nitoring the ;=c paracter -hould read ;ppr;xi;;;;tely th; == v; luc. Signific=t dcvi;tions bctuc= the two instruant chanxis could bc = ; 4ndication of c=cnive instrunnt drift in enc of the chenacis , - er of s=cthing cycn ;;;;r; nricus. A CHANNEL CHECK will detect # (continued) U l l, j- CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-169 10B088 l

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-78 APPLICABILITY: CP REQUEST: The modifica' ions to the improved TS are consistent with both the intent of the improved TS and the CPSES CREFS design and current TS. Comment: Revise the Note to Required Action B.2. Copy the Note to proposed Required Action A.2. j l {CP) Add NUREG actuation logic and actuation relay surveillance test requirements for CREFS actuation. FLOG RESPONSE: The Note in Required Action B.2 has been revised to adopt the STS format The revised Note is also applied to Required Action A.2. Because the CREFS logic consists of a ' single relay, there is no setpoint to be verified during the performance of a TADOT per SR 3.3.7.6. The surveillance SR 3.3.7.2 (a Channel Operability Test) was added to the Automatic Actuation Logic and Actuation Relays Functional Unit. These actions are consistent with those agreed upon at the meetings held between the NRC staff and the FLOG members during the week of September 14,1998. ATTACHED PAGES: Enci5A 3.3-62, 3.3-63 and 3.3-67 ., Enci 58 8 3.3-175 1 'i I 4 f 1

I I 1 4

i CREFS Actuation Instrumentation 1 3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Emergency Filtration System (CREFS) Actuation Instrumentation LCO 3.3.7 The CREFS actuation instrumentation for each Function in Table 3.3.71 shall be OPERABLE. APPLICABILITY: "00E 1. :' 3. 4. 5. a d 5 During c';c. ant ;f irr:diated fuci :::cablic . b3 3OJI [0uring 00"E ALE"AT!0"S].M3KtplabTeX3j'731; ACTIONS ........................................ NOTE -------- --- - - - -- -- ----- -- - - Separate Condition entry is allowed for each Function. CONDITION REQUIRED ACTION COMPLETION-JIME A. One or more Functions A.1 ---- NOTE-- ----- with one channel or "1 cc in toxic g;; U B-PSVM train inoperable. pretcction cdc if

                                                       ;ut = tic tr=:fer tc toxic 90: protection Edc i; in;pcr:bic.

Place enc C"JTS trein g g 7 days e f .:- .. y a ; 9 1 .1 W in g^"7~ emergency rediation protection MERWifletidd mode.

3 ,- c .: , g. F08R1055 M

                                                     ._ _ _- _an. . . .-m
                                                                                                                     )

Q MlM 71 dam [.[3f78 L: lc V im Rh6fBn.\ angnBatsunngnintseri (continued) CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-62 10B088

i t CREFS Actuation Instrumentation l 3.3.7 ACTIONS (continued) CONDITION RE0VIRED ACTION COMPLETION TIME B. One or more Functions NOT Place in the toxic gas FB;PS$1 with two channels or two trains inoperable. protecticr. ;cdc if cutomatic transfer to toxic gas protection acdc is inoperabic. B.1.1 Place one CREFS train Immediately 1B-PS M in emergency radiation prcincticr. Lecirculation mode. 6N_Q B.1.2 Enter applicable Immediately Conditions and Required Actions for one CREFS . train made inoperable by inoperable CREFS actuation instrumentation DE B.2 E~ -R e-iNult:c--tm Tic 3BTEdi11YEdIF0Victid6s 78 3ellmM311cChGtJ2 3- [ 3 73 6 5MRNiges=streett41 A A 4 truh4 Abb5V N.k % 5_ U3 !V b # VI 5_2V) u.mm.m .- 2,o f=48%r<mFV45kl5_456hu % m3 W u s 'J k. . m_,m wn. . vu ., _ n--vs e -w;-ya Immediately Placc both trains in 1Y3.3W84 c crgency radiction protection acde. Secu're7th_e CotittoTIR6ehiIh8Relip]ift

                                    }g@ly;faYl:freiEthEnff6cted B1EinthKB]

l CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-63 10/30/98 { i

                                          .          =                                    . -             -          - .        .

CREFS Actuation Instrumentation 3.3.7 Table 3.3.7 1 (page 1 of 1) CREFS Actuation Instrumentation i i M TRIP " T ' T ' 5FWimg REQUIRED SURVEILLANCE '~~~"~ SETPOINT FUNCTION 6 CHANNELS REQUIREMENTS j

1. Manual Initiation 1;2 M 2$2 2 trains SR 3.3.7.6 NA Nf}I3hl l

2. Automatic Actuation Logic and 1;T2DC4E5; 2 trains @ZI3;7; NA Actuation Relays and,$nfa} = .,... .-

3.3 78 SR 2.2.'.! Q.3.3 78 SR

3. Control Room Radiation

. c atr:1 R x; '.ts :/~.. Ee3 {.;.g.'.j

                                                                                              ; ::: ;a,'"         e3,3 734 S"  3.2.' '                                            l b--a . Control Room Air North 13;9Zi;*5l                2            SR 3.3.7.1       ; ::: ;"/5r Intak                    and 67[(a)                           SR 3.3.7.2        IM XIQd            K3.3478 5         l SR 3.3.7.7          WJ1sl                              l h3cntt913 Dos: ail 50uth      1332fL51                  2            $R33;3;7;3        114)QR8 E g g itatak                    anot,Ual                             grJALg              pCJAn1           ES$ M
                                                                             $Rv3"J21]

1 1

4. Safety Injection Refer to LEO 3.3.2. *ESFAS Instrumentation,"

Function 1, for all initiation functions and requirements. 90 I!stMrto9ter!EpfdrrettateChtLysspD11es2 p.Sqppy l l CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-67 102088

CREFS Actuation Instrumentation B 3.3.7 BASES

2. Automatic Actuation Loaic and Actuation Relays (continued)

Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for CSFAS Function 1.b., SI, in LC0 3.3.2. The applicable MODES and specified conditions for the CREFS portion of these functions are different end ic33 CP-3.3 009 restefet4ve than those specified for their SI roles. If one or more of the SI functions becomes inoperable in such a manner that only the CREFS function is affected, the Conditions applicable to their SI function need not be entered. The less restrictive Actions specified for inoperability of the CREFS Functions specify sufficient compensatory measures for this case. w...,.__ ~-...,=~n_ _.,,_- =.1 %

                                .,i.- m
                                 ..,, _ , .      %.-m                    w - . ..

_m-_ _ . .,.,_.. - m.ac.=n%s. a -n . m..c,. 1 0 3.3 78 l

3. Control Room Radiation The LCO specifies tw; regir:d Centrol R;;;;; At;;;;;phcra Radiati;n "eniter; and two required Control Room Air Intake Radiation Monitors pg2rit;Aird to ensure that the radiation monitoring instrumentation necessary to initiate the CREFS remains OPERABLE.

E CP 3.3 009 x; ; a.a .-- .,.s. . L.; 3 ; y ae,,m f c ' ; J 4. . ~ .4 ,p For sampling systems, channel OPERABILITY involves more than OPERABILITY of channel electronics. OPERABILITY may also require correct valve lineups, sample pump operation;- i sad filter r.;;ter epcration, as well as detector ! OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety analyses. rummewr -mus.n m - s , mu % sam m es-swammr-ara CP 3.3 ED m c.,m--.u.m.s.-,w-sm m. l 6

4. Safety In.iection i Refer to LC0 3.3.2. Function 1, for all initiating i:

l Functions and requirements. CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-175 10B088

l i

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-79 APPLICABILITY: CA, CP, DC, WC REQUEST: Add Applicability columns to ITS Tables 3.3.6-1 and 3.3.7-1 to reflect current TS with varying Functional Applicabilities. Comment: Revise submittal to adopt TSTF-161, Rev 1 format. List " core alterations" applicability and "during handling of irradiated fuel" as separate applicability footnotes. {DC} The applicability for Containment Purge and Exhaust isolation is broader than required by CTS 3.3.2. This change is neither identified nor discussed. {DC} ITS Table 3.3.6-1 applicability for the Containment Radiation Function is duplicated. It is not necessary to provide an applicability statement for function 3 if applicability is provided separately within function 3, in this case for function 3.a. {DC} The required number of channels for function 3.a under applicability condition (a) is inconsistent with the markup of CTS section 3.3.2. {CP} Explain the design justifcation for not including Table 3.3.6-1 Note "c" in the l applicability for actuation logic and relays. Specified logic must support radiation . isolation function in the table. If the logic supports Phase A isolation (T3.3.6-1, F4) then it should not be listed in this table. A single listing of the logic in ESFAS table 3.3.2-1 is acceptable. {CW} CTS T4.3-3 F9a,9b and 9c shows a markup (strikeout) of applicable conditoins without evaluation. Provide a revised markup and evaluation of proposed CTS changes. CTS T3.3-3 F9a,9b and 9c shows no changes to applicable conditions. These differences are not evaluated. {CW} CTS T3.3-3 Actions 26 and 26"" are used in ITS T3.3.6-1. Changes to these CTS requirements are neither identified nor evaluated. FLOG RESPONSE: Comment 1: In response to the first comment, ITS Table 3.3.6-1 has been revised to reflect TSTF-161 Rev.1. Applicability footnote (a) has been divided into *(a) During CORE ALTERATIONS" and "(b) During movement of irradiated fuel assemblies within containment." No changes to current TS Table 3.3-3 Functional Unit 3.c or to the ITS 3.3.6 Bases are required. For WCGS, DOC 3-20-LS-51 was initiated to revise CTS Table 3.3-6, Functional Unit 1.a. to revise the Mode of Applicability from "All" to "1,2,3,4, During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment." The mark-up of STS LCO 3.3.7 Applicability in Enclosure SA shows the strike-through of "During CORE ALTERATIONS" under JFD 3.3-79. That JFD has been revised to discuss the rationale behind the strike-through. Since ITS Table 3.3.7-1 includes all MODES 1-6, the LCO is applicable any time fuelis in the reactor vessel. Since CORE ALTERATIONS involve activities conducted while fuel is in the vessel, including this in the LCO Applicability is unnecessarily redundant given the definitions of CORE ALTERATION and MODE. This same approach was taken in ITS 3.7.10. DCPP has also made changes to the ITS 3.3.7 Bases to correct and clarify the applicability. No changes were required for other FLOG plants' ITS 3.3.7 Bases.

l l Comment 2: For DCPP, applicability footnote (s) has been revised to state "During movement of irradiated fuel" since CTS 3.3.3.1 requires the CVI to be operable in MODE 6 that includes CORE ALTERATIONS. This is consistent with ITS 3.3.7 and 3.7.10 as revised and as discussed above. : Comment 3: The duplicate applicability has been deleted and the sub-function "a" has been incorporated under the main function "3". In addition, the title of the function has been revised to

    " Containment Ventilation Exhaust Radiation Gaseous / particulate" since for DCPP a single monitor accomplishes the monitoring for gaseous, particulate and iodine radiation functions for           ,

detection of a fuel handling accident as explained in the ITS 3.3.6 Bases. This title is also i consistent with the CTS terminology. Comment 4: CTS Table 3.3-3 has been marked up for clarity to show the MODE 6 and channel requirements of Table 3.3-6. In addition, a new DOC 2-51-LG is used to move the descriptive channel identifiers to the ITS 3.3.6 Bases. Comment 5: For CPSES, other changes to ITS Table 3.3.6-1 are also addressed in response to this question. The footnote (a) has been incorporated into Table 3.3.6-1, Functional Unit i directly, rather than by reference. Subsequent footnotes have been re-lettered. Further, the notation describing the strike-out of STS Functional Units 3.b.,3.c. and 3.d. has been revised to reference JFD 3.3-79, rather than JFD 3.3-73, as contained in the original CPSES submittal. Comments 6 and 7: These comments were resolved during meetings with NRC staff on , ! September 16 and 17,1998. However, Reference 6 is silent on the resolution of comment 7. Changes to CTS Table 3.3-3 ACTION 26 for ESFAS Functional Units 9.a. 9.b, and 9.c are identified on page 3/4 3-21 and insert 3/4 3-21 in Enclosure 2 and are evaluated under DOCS 1-04-LG,1-43-A,2-16-LS-12, and 2-26-LS-21 (see also responses to comments on the last two DOCS). No DOC is needed for the **** note in CTS Table 3.3-3 since that note is consistent with ITS 3.0.4 (i.e.,3.0.4 does not apply in MODES 5 and 6). ATTACHED PAGES: Enci5A Traveler Status Sheet,3.3-61 and 3.3-61a Enci6A 9

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 l l TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-19. Rev. 1 Netincorporated NA Not NRC epproved os of E TR-3.:-004 B .

                                                         ..._u..
                                                            ..      .n. _. . _ - -
                                                                                   .,  Emanumm mmmmme N EE W.

Tai r , r,cv. :xcrprated 3-3-34 QQ : i TSTF 37, Rev. 1 Not Incorporated NA ITS 5.6.8 s'till addresses PAM 1 reports. Sections after ! ITS 5.6.7 were not renumbered. ! TSTF-51 Not Incorporated NA Requires plant specific ) reanalysis to establish decay j time dependence for fuel handling accident. TCP 01 Not Incorporated NA [ ] AllcW;bic " Gluc 3 TR 3, 3-005 l for ic= cf volt;;c =d degraded voltagc will rcain in the TS. TSTF 111. Rev. 1 Incorporated NA TSTF 135 M L] Partially 3.3-41 Trevcler is tsc broad l TR-3. l-006 E Incorporated 3X43 scope in n:turc; 3ili90] should have bcca 3133?i] several :cparctc travcicrs. 3.3 93, Partion; cf the travcicr that 3.3-95, significently clorify E.;33g operability rcquircz ats have 3.3 122, bcca i nciperated. 3JF142 TSTF-161 _y_H

Incorporated 3.3 79 h69ii[by3he3RC ---_g o.3. 79 g A

TSTF-168 Incorporated 3.3 43 6ppfcKd;bljtj0!IE go.3, 43 g 4 I TSTF-169 Incorporated 3.3-42 @pbMRtl ibrJtE!EICE gin.3, ;.003 g W9G-406M-Jfg Incorporated 3.3 49 go.3, 49 g piiTE2Errcp;;cd Incorporated 3.3-107 WOC ."ini-Croup Action o.3. 107 g travcicr Itcc f145.

ContainmentLVefitf]at104."urg cr.d Shaust Isolation Instrumentation J 3.3.6 Table 3.3.61 (page 1 of 1) Containment *m ".ra; ;rd EnM;;; Isolation Instrumentation

                                                                                                                      , ' :]..[ ;}

M F1JNCTION N EDER REQUIRED CHANNELS SURVEILLANCE M REQUI E NTS

                                                                                                                      ~OL 7 m                                                                TRIP SETPOINT                  >;

1. Manual Initiation 1H3CFTife) O(4f:llef90 MIL'_2---

2:an_ __ _ _ _. ;i ivr oli --

                                                                          -_ .17and--Nha[

72 3.3 77

                                                               " 2.3,0.0;4]               m                           0 3.3-79

2. Automatic 122 3,'4 2 trains SR 3.3.6.2 NA Actuation SR 3.3.6.3 :

Logic and SR 3.3.6.5 Actuation . Relays

3. Containment Radiation

a. Gaseous IF .*3,*J; 1] SR 3.3.6.1 a [2 M;kgr;;rd: yyg g 3

_c} SR 3.3.6.4 fl>) (af - SR 3.3.6.7 3.3-79 , f Q-3.3 79 j

h. {43 0" 2.3.5.1 ; [2 x k;kgrourd:

    ";rti;;ht;                                                    :" 3.2.0.'                                      3.       79 C"  2.3.0.'                                     Q 3. -

c. Mir.; {43 0" 2.3.0.1 a [2 x k;kgreurd) 3.2.0." 3.

0" 3.3.07 Q. h" 3.3 79 d-Acee {43 5" 3.3.5.1 *-C ; k;kgr;;rd Redfet4en :" 3.3.0." 3. 23

" :.:.c.' Q.3.

4. Contairment. '

Refer to LCO 3.3.2. *ESFAS Instrumentation.* Function 3.a. for all Isolation- initiation functions and requirements. Phase A i i I CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-61 10B088

1 Containmentm Pur;c r4 Odou;t Isolation Instrumentation IT E 3.3.6

                                                                                                                             <-   ~

7 y Q 3.3 79

r. .

1 j t D NERE RR E R R'llM R h - - - - - - . _ _ _ . _ _ . . _ .

                                                             . mmm __ __ _m.
                                                                                                    . - a     an=,

33NB 0 3.3-79

   - - x = - #m                                            m mia                                                                                 3,3 79 Q 3.3 79 5

l

                                                                                                                                          .               i I

l l l l CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-61a 10BOMS

CHANGE NUMBER JUSTIFICATION CPSES plant specific Trip Setpoints from the current technical specifications have been inserted in the table. The function for automatic actuation logic and actuation relays was not listed in the j current technical specifications because of the simple, direct acting l design that is tested as parted of other ESFAS and control room HVAC l system testing. This function has beed added to the ITS to be ! consistent with the ISTS format, but new surveillances, beyond the current technical specification requirements, are not needed and have been deleted. ! 3.3-79 This change adds Applicability columns to ITS Tables 3.3.61 and 3.3.71 to reflect current TS with varying Functional Applicabilities. I This change is consistent with the format used for the RTS and ESFAS l instrumentation in the ITS and is a clearer method to present varying l App 11cabilities from the current TS. These changes are administrative format changes that insert the Applicabilties of the current TS into Tables 3. . nd 1 3 7-1. This chance is enne4t=+ with tr=ler TSTF- f thTEHtpatateYootriote[Cforj CORETAETERATIONSJndJ i o.3.3 79 l 1]IILming!t2XMlaMfi33JMMMMN.TERAM gplfj:abjitfGREEIRTiiR(3Rdig[danf307;ftic1gdjnR10DElS6 ~' [ E agd 3 [.goj!Qg@gLtgl. 3.3 80 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 81 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 82 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-83 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 84 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 85 The Note in Required Action 3.3.5 A.1 would be deleted as it is inconsistent with the current CPSES design and licensing basis.The CPSES design and current TS do not allow bypassing an inoperable channel. 3.3 86 Surveillance Requirement 3.3.5.2 is revised to reflect the current plant design and licensing basis. A Note is added to SR 3.3.5.2 indicating that setpoint verification is not applicable for the performance of the TAD 0T. This verification is performed during l Channel Calibrations (see SR 3.3.5.3). l 3.3 87 Not used. l 3.3 88 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). CPSES Differencesfrom NUREG-1431 -ITS 3.3 9 10B0A8

l ADDITIONALINFORMATION COVER SHEET l l ADDITIONAL INFORMATION NO: O 3.3-06 APPLICABILITY: CP i REQUEST: Surveillance Requirement 3.3.5.2 is revised to reflect the current CPSES plant ! design and licensing basis. A Note is added to SR 3.3.5.2 indicating that setpoint verification is ! not applicable for the performance of the TADOT. This verification is performed during channel calibrations (see SR 3.3.5.3). i Comment: Revise SR frequency to meet Writer's Guide j FLOG RESPONSE: The Frequency for SR 3.3.5.2 has been revised, as agreed upon at the

     " September meeting."                                                                                   l ATTACHED PAGES:

Enci5A 3.3-55 Enci5B B 3.3-160 1 l l

l l LOP DG Start Instrumentation 1 3.3.5 E ' . ~ ' J Jd. . -lll ::J :a;9l M - [ . f - ) .r .le@ M . JLTjjj _

                        , ; x . , 7. . .
                                  .                   m
                      * .-' ' .J .  %,*.

c . . " . j. m; 3 .j g M Iign R!samiBKMT.gtsite timeltes!kt Q.. . A . i'.J.d IM 3.3 131

U .'s :. .'. . . .

Q.3.3 131 8tEl E?MR ppggDg![q1typartet 6ihours

                                                                $Ouftelbreakets"tolthe gs p Ibdses GE. Required Action and                    Cf.1           Enter applicable                  Immediately                        WS.34313 associated Completion                                Condition (s) and Time not met.                                        Required Action (s) for                             .

the associated DG made inoperable by LOP DG' start instrumentation. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 l'crfor; C"."" EL C"ECK. ECM9lQ 12 hours M SR 3.3.5.2 j7 t.M.W.tQ u'i..in E : +.7 4 - 31 i;vs - 5 L7.'.EdEMkMDPif9Mt!T g m .a

                                                                                                    ..p.    .!..

Perform TAD 0T. 1 B-PS Q 3.3-86 N N l i CPSESMarkup ofNUREG-1431 - ITS5 $ 3.3-55 1020M8 l

LOP DG Start Instrumentation B 3.3.5 BASES SR 3.3.5.2 ER 3.3.5.2 is the performance of a TAD 0T. This test is

0 3.3 86 perioragess m a 4 S L. The test checks trip devices that provide actuation signals directly, bypassing the analog process control equipment. For thcsc tcsts, the rel;y Trip Sctpoints arc verified and adjusted as acccssary. The Frequency is based on the known reliability of the relays and controls and the multichannel redundancy available, and has been shown to be acceptable through operating experience. SB 3.3.5.3 SR 3.3.5.3 is the performance of a CHANNEL CALIBRATION. Be-sctp;ints es wcli s the respensc to a inss of voltag; and a dc; reded volt:g; tcst, sh:11 includ; a single point verificptica that the trip eccurs within the required ti;;;c dci y, s sh; r in "cfcrence 1. A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. o.3.3.s.1 The Frequency of }8; months is based on operating experience and consistency with the typical industry refueling cycle and is . justified by the assumption of an E181 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis. SPMM i sliLr.rs 4mEtytperfasstipicuttatigggEDMEtes]Lguetti!!e wsficattaT3senlmmuspaperAsRFADonthtERI8 l SIAHiEREB3ESTiBREIEERIRabtrEEliMcRRErMGMmEL1 Bit $ArdM#q# l 1CBhe7BhgLc811Bgl33lgts3g8]3LEgtpr1& cat 10n3h811 Duaudemisenst32tBrJ110ELGE3 hat 3mth:trarinsurewedfiemt legtrggpe_r3ftyggelligg , I ( l l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-160 192088 i

ADDITIONALINFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-94 APPLICABILITY: DC, CP, WC, CA REQUEST: ITS 3.3.4 is revised per current TS [3.3.3.2.1] with regard to [HSP] controls. l l Comment: This is a proposed generic change that is not approved by the staff. Revise , submittal LCO, Table functions, Actions Note 2, Condition A and Required Action A.1 to maintain ISTS format, which if necessary, can be accomplished with a separate table j entry for RSS controls. l FLOG RESPONSE: As discussed during meeting with the NRC staff on August 11 through August 14,1998, the FLOG has modified the ITS markups associated with JFD 3.3-94. WCGS is now adopting the changes associated with JFD 3.3-94. See also the response to Comment i Number O 3.3-24. I ATTACHED PAGES: EnctSA 3.3-50 Enci5B B 3.3-149 and B 3.3-151 l I I

Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System be 4 3,3,94 shall be OPERABLE. o.3,3 94 APPLICABILITY: MODES 1, 2, and 3. 1 ACTIONS

     ........................................N0TES                               --            ----- --- ----- ----------------

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function and.ltgguiried1tSPIcontFol.

CONDITION REQUIRED ACTION COMPLETION TIME

    - A.      One or more reauired                       A.1 Restor re uired Function                                      30 days                  3,3,94 Functio                                  - E - W i__BSPIC6htP615 to                                                                   a.3,3 94 noperaole.                        OPERABLE statu A                                                                   .

a summaardenpfesLEia . _ _

                . . . . . . . ~ y , y.,/..                                                                                                           h .: .

B. Required Action and B.1 Be in H0DE 3. 6 hours associated Completion Time not met. MQ B.2 Be in MODE 4. 12 hours l l l l l CPSESMarkup ofNUREG-1431 - ITS3.3 3.5-50 10B088 l l

l Remote Shutdown System B 3.3.4 BASES APPLICABILITY The Remote Shutdown System LC0 is applicable in MODES 1, 2. and 3. This is required so that the unit can be placed and maintained in MODE 3 for an extended period of time from a location other than the control room. l This LCO is not applicable in MODE 4, 5, or 6. In these MODES, the facility is already suberitical and in a condition of reduced . RCS energy. Under these conditions, considerable time is I available to restore necessary instrument control functions if ; control room instruments or controls become unavailable.

ACTIONS Note 1 is included which excludes the MODE change restriction of l LCO 3.0.4. This exception allows entry into an applicable MODE l while relying on the ACTIONS even though the ACTIONS inay eventually require a unit shutdown. This exception is acceptable due to the low probability of an event requiring the Remote Shutdown System and because the equipment can generally be'-

l repaired during operation without significant risk of spurious trip. Note 2 has been added to the ACTIONS to clarify the application l of Completion Time rules. Separate Condition entry is allowed for each Function listed on Table 3.3.41M2gquifed So@hpfdaghtefitTAHR99cIR@l. The Completion Time (s) of the inoperable channel (s)/ train (s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function. m Kame"8

                                                                                                                          ~
                                                                                                                 #1
                               . p g. c .c u 4. :..,, q y \ ; 2 4.y ) v                        :    ,g s a ,p.y al                                                                                                       l Condition A addresses the situation where one or more required Functions of the Remote Shutdown Syst                                                g,3,3,94 g _ _ m, .          ,u _     ,__,.m__   __..r..__.:__         m___.

in _---;- I Table 3.3.41t-- ek s i -12_f-Ji

                                .- ute . s            w. ; es the cer, trol er,d trer.sfer switches.                                   '

The Required Action is to restore the required etio erGtud gggittGMiPACUMtBl$ to OPERABLE status within 30 days. The j (continued) !' L CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-149 10B088

 .      _    _.       _.      . . ~ . _ _ . _ - . _ _ _ _ _                                                    .            .  . _ _ .        _ . _ _ .

Remote Shutdown System B 3.3.4 BASES , The Frequency of 31 days is based upon operating experience which demonstrates that channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels - during normal operational use of the displays associated with the LCO required channels. i SR 3.3.4.2 N SR 3.3.4.2 verifies each required Remote Shutdown Syst Q 0 3.3 94 poWerg control circuit and transfer switch performs the I intended function. Ihisverificationisperformedfromthe l

                                            %utdown@nel and locally, as appropriate. Operation of tne equipment from the remote shutdown panel is not necessary.

The Surveillance can be satisfied by performance of a continuity ] check. This will ensure that if the control room becomes j inaccessible. the unit can be placed and maintained in MODE 3 ! from the remote shutdown phreel and the local control stations. I The }8 month Frequency is based on the need to perform this l Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. (However, this Surveillance is not required to be performed only l during a unit outage.) Operating experience demonstrates 1 that remote shutdown control channels usually pass the 0 3.3.s.1 l Surveillancetestwhenperformedatthe18monthFrequency. SR 3.3.4.3 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. IlhtG H er m 3 1elat M B E E 9 M a t LT@tg TR-3.3 004 j liibetTifsiridiCIMMEMMEEEliBGEMEhtiMkistMM nanomaannnem m Mhe i Frequencyof38monthsisbaseduponoperatingexperience 0 3.3 G-1 l and consistency with the typical industry refueling cycle. l Y .,u r . .$ S" 3.3.4.4 is the p;rf; men;; Of ; TA00T recry 10 renths. This

t;;t ;hould J;rify th; 0lT"XILI"I Of the. r;;;ter trip br ;kcr; l 1

("Jh) ep;n :.ad ;l; ;d indi;;ti;n en th; r; et; ;hutdc.;. pencl, by ectu; ting the "Jh. The ."rcqu;ncy is b;3ed upon ep;r; ting (continued) \ CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-151 10B088 l

I l l ADDITIONAL INFORMATION COVER SHEET [ ADDITIONAL INFORMATION NO: O 3.3-96 APPLICABILITY: DC, CP, WC, CA REQUEST: [ Note 2 for ITS SR 3.3.1.2 is revised to replace the bracketed 12 hour time constraint with 24 hours. No such time limit is contained in the current TS, which has an SR 4.0.4 exception. The performance of ITS SR 3.3.1.2 should be provided sufficient time to perform the initial comparison and gain adjustment, equal to the SR frequency.] Note 2 for ITS SR 3.3.1.3 is revised to replace the bracketed 15% RTP power level constraint with 50% RTP. The specified power levelin ITS SR 3.3.1.3 should reflect the applicable safety analysis basis consistent with the [ Applicability and] Required Actions of ITS LCO 3.2.3 (AFD) and LCO 3.2.4 (QPTR). Comment Reject - Scope issue - because ITS Note 2 to SR 3.3.1.2 and Note 2 to l SR 3.3.1.3 proposes 24 hours for delay in performing the SR which are generic changes to STS that are not included in an approved TSTF. The justification is inadequate. Adequate justification would be the format is not usable, or the requirements represent unsafe practices or may result in an operational hardship. Note [DCPP] ITS markup missing "3.3-96" annotation. 1 i Reject 50% RTP in Note 2 to SR 3.3.1.3. FLOG RESPONSE: The justification for the proposed changes, originally provided in JFD 3.3-96, will be modified to include more detailed information conceming the application of the CTS ; 4.0.4 exception to these surveillances. I i The following has been added to JFD 3.3-96: These proposed changes address the current practices conceming the application of the CTS 4.0.4 exception to various STS surveillance requirements. j l For DCPP, the plant-specific revision to SR 3.3.1.2 necessary to incorporate CTS is described in JFD 3.3-47. For Callaway, CPSES, and WCGS,;the proposed change to STS SR 3.3.1.2, Note 2, is provided to incorporate the SR 4.0.4 exception provided in the equivalent CTS surveillance, contained in CTS Table 4.3-1, Note (2). The current practice conceming the application of the CTS 4.0.4 exception is to defer the first required calorimetric measurement and the associated normalization of attemate power indications until a scheduled testing plateau is attained during the post-refueling outage power ascension. Typical post-refueling outage power ascensions include a power increase to approximately 30% RTP; although, the current practice of some plants is to achieve a power plateau nearer to 50% RTP. Using typical power ascension rates of 3% RTP/ hour,5 to 12 hours are required to reach the first scheduled power plateau above 15% RTP. Based on plant experience, after a specified power plateau is attained, approximately 2 hours are required to stabilize the plant and perform the calorimetric measurement. Two additional hours are required to make any necessary adjustments to the Nuclear instrumentation System [and/or N-16] power indications. The proposed 24 hour time frame also provides a reasonable allowance during which the effects of equipment failures may be addressed. For example, if the plant computers are not available, some additional time is required to manually collect the data and perform the required calculations. The proposed 24-hour allowance after increasing THERMAL POWER above 15% RTP provides a reasonable

time to attain a scheduled power plateau, perform the required calorimetric measurement and make any required adjustments in a controlled, orderly manner. Plant procedures provide

guidance conceming the use of all available power indications [(e.g., turbine load, hot leg temperatures, loop AT)] during a power ascension. Any significant inconsistencies would be resolved through the performance of a calorimetric measurement. Based on the current, conservative operating practices and the fact that secondary plant calorimetric measurements are typically more accurate when preformed at higher power levels, it is not necessary to require a formal calorimetric comparison to be performed prior to exceeding 15% RTP. The note has sufficient limitations to ensure the plant is operated in a safe manner. Note 2 to STS SR 3.3.1.3 addresses the conditions required to perform the incore-excore comparisons of AFD. The STS includes an allowance of 24 hours (within brackets) after exceeding a specified power level for the first performance of this surveillance. The proposed change to the time allowance of STS SR 3.3.1.3, Note 2, would adopt the 24 hour allowance, but specify the power level to be 50% RTP. The change is predicated on the current practices conceming the application of the CTS 4.0.4 exception to the CTS (e.g., for CPSES, CTS Table 4.3-1, Note (3)). Current practice is to perform this surveillance at a power level below 50% RTP. Based on plant operating experience,24 hours is a reasonable time frame to limit i operation above 50% RTP while completing the procedural steps associated with the

surveillance in an orderly manner.

The deferral of the power level above which SR 3.3.1.3 is required to be satisfied is also consistent with current operating practices concerning the application of CTS 4.0.4. Due to such effects as shadowing from the relatively deep control rod insertion and, to a lesser extent, the dependency of the axially-dependent radial leakage on the power level, the relationsh,ip between the incore and excore indications of axial flux difference (AFD) at lower power levels is variable. Thus, it is prudent to defer the calibration of the excore AFD against the incore AFD until more stable conditions are attained (i.e, withdrawn control rods and a higher power level). The AFD is used as an input to the overtemperature reactor trip function and for assessing compliance with ITS LCO 3.2.3, " Axial Flux Difference." Due to the DNB benefits gained by administratively restricting the power level to 50% RTP, no limits on AFD are imposed below 50% RTP by LCO 3.2.3; thus, the proposed change is ccos6terd with the LCO 3.2.3 requirements below 50% RTP. Similarly, sufficient DNB margins are realized through operation i below 50% RTP that the intended function of the overtemperature reactor trip function is maintained, even though the excore AFD indication may not exactly match the incore AFD indication. [Further, current practice at many plants is to administratively reduce the Power Range Neutron Flux - High setpoint until this and other surveillances (e.g., peaking factors) have been completed anJ it has been demonstrated that the plant is ready for sustained operation at full power in accordance with the design and licensing basis.] In summary, the proposed changes are more restrictive than the CT% boi w consistent with the current operating practices conceming the applications of the CTS <t 0) exceptions to the equivalent CTS surveillances. The proposed changes allow powr ncent ons and associated testing to be conducted in a controlled and orderly manner, at v.Mt;om inat provide acceptable results and without introducing the potential for exended eperation at high power levels with instrumentation that has not been verified to be aco;otmle for subsequent use. ATTACHED PAGES: Enci5B B 3.3-51 and B 3.3-52 Enct 6A 11 and 11a

d CHANGE NUMBER JUSTIFICATION l

As revised, these surveillance requirements are acceptable in that they assure the surveillances are performed after the appropriate plant 4

conditions are attained and still provide sufficient time to perform the surveillances in a controlled manner. Eleik 64'atitTchirtent3tifictRits'1poncetWafthe 0 3.3 96 IsottsaEREftBbMEEMENRept10Eh6Hanet 8880enERs Egt~R;2Eigh!G8pgggKcAtBBggigigg'id' SIC 333Enajllessari3g Ini;orMr18RIEBOR!EtBapONJJ133ZMerJ4U4BrJEMSMMCGSI thCptgetited:MJiEDBEX@Ilott3ABRato. Erie 8Minc.grpotate t_helSRJ4ECgggpMon%^Ti.2in;theitqu1ValenN:csurVejllg pontainarNn3EEF#!1e"C5W7110te32t?phCcmn!nt3itectice3oncerning l thelapplasticof2hercJSMioEggception3satoIdete_r;the l titstiteguited l calorjee_trJcLangstementianothe associsted36temitationrof alternate ! poserEinnsatagg Ba1BCatadulettesting plateau tsattainstd_ ting 3_he poltittMm11mractes0Meerarscensionxrspicalmostreefoeunn3gstge:pgwer pscansfonslinclimmacig!!gggsperegeltagesprox5sately]OJEEEtlthoughj theTcurrent)3CLggf3dag:plents!1Ct6'raai=azgggrZplqgatf3 tearer; 3GOERnTaskWatipicatage!rascensionTreagatGREggglingtsto 12 ho0tsMX1tstNChDelEE0liierstel34MxdK35* RT, PRS $526MM5ftaggpBBEBLN atsniedampomanassRemarrteneesomintaktasumarcelagiand petDrEtheX41, RIMBIMBSSRegent35Fradm[ sip 1'aggr$3sEr.emited to.)ngJe IitemaggIBileGBBLt_s%th67KutleM7nsttWetetfon]yge,m tand/srhan6EmmenginmostseWWRhelpcoposedELMir23nemamentso 6:durfpH3hich3tHufffG2pt2@illlEnt fajgtg!gggggggggigg[ggilgSpxampiggtf3lly31antMwam

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l CHANGE i NUMBER JUSTIFICATION l

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, current TS Functional Unit [2.a and 7] surveillance requirement of Table i

1 CPSES Differencesfrom NUREG-1431 -ITS 3.3 11a 1020A8

RTS Instrumentation B 3.3.1 BASES channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant i deviations between the two instriment channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect i gross channel failure; thus, it is key to verifying that the ' instrumentation continues to operate properly between each ; CHANNEL CALIBRATION. Agreement criteria are determined by the unit staff based on a combination of the channel instrument uncertainties, including indication and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal , processing equipment has drifted outside its limit. The Frequency is based on operating experience that demonstrates channel failure 1's rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels. 1 . l SR 3.3.1.2 : SR 3.3.1.2 compares the calorimetric heat balance calculation to the NIS W very 24 hours. If the calorimetric exceeds the NISM channel atpt by > 2% RTP, the NIS ggggjiggggggggglef@s not declared inoperable, but a . d .; ., w st be adjusted MhUstkOlt6. If the NIS ggj]g channel outputi cannot be properly adjusted, the channel is declared inoperable. Two Notes modify SR 3.3.1.2. The first Note indicates that the NIS gr25; # .. s e T. { > < . ch;nnel atpt shall be adjusted i consistent with the calorimetric results if the absolute difference between the NIS chonnel l ee ma tha calorimetric is > 22 RTP . i ly f ctor l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-S1 10B088

RTS Instrumentation B 3.3.1 BASES power is a 15% RTP and that 12 MhourM is allowed for performing the first Surveillance after reaching 15% RTP. At lower power levels, calorimetric data are inaccurate. The Frequency of every 24 hours is adequate. It is based on unit l l operating experience, considering instrument reliability and ) operating history data for instrument drift. Together these factors demonstrate the change in the absolute difference between NISF R g and heat balance calculated powers rarely exceeds 21 in any 24 hour period. In addition, control room operators periodically monitor redundant indications and alarms to detect deviations in channel outputs. SR 3.3.1.3 ( SR 3.3.1.3 compares the incore system to the NIS channel output every 31 EFPD. If the absolute difference is a 3%, the NIS l channel is still OPERABLE, but must be readjusted. If the NIS channel cannot be properly readjusted, the channel is declared inoperable. This Surveillance is performed to verify ! the HerI+M4ql input to the overtemperature trT;N36 Function. Two Notes modify SR 3.3.1.3. Note 1 indicates that the excore l NIS channel shall be adjusted if the absolute difference i betwaan the incore and excore AFD is > 3 h '* l

                                                               .- m.   = m ; ,    .. /-xsT
                          @clardies ma6me 5urvei s iance is requirea on' y if reactor                CP-3.3-ED power is 2-154 lRg RTP. and that 24 hours is allowed for

! performing the first Surveillance after reaching 154 50] l RW. The Frequency of every 31 EFPD is adequate. It is based on unit operating experience, considering instrument reliability and l operating history data for instrument drift. Also, the slow changes in neutron flux during the fuel cycle can be detected during this interval. ( SR 3.3.1.4 l l ! SR 3.3.1.4 is the performance of a TADOT every 31 days on a STAGGERED TEST BASIS. This test shall verify OPERABILITY by actuation of the end devices. I l CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3 52 102088 l l

l l l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: O 3.3-97 APPLICABILITY: CP, WC, CA, DC REQUEST: The NOTE for SR 3.3.1.6 of ITS 3.3.1 has been revised to state "Not required to , be performed until 72 hours after achieving equilibrium conditions with THERMAL POWER l

t 75% RTP". This is consistent with the cunent TH Functional [ Units 2.a and 7] surveillance requirement of Table 4.3-1, as modified by Note (f,) and current operating experience of 72 hours for performing the SR.

l Comment: Reject - The JFD statement regarding equilibrium conditions: "This is consistent with the current TS Functiona' [ Units 2.a and 7] surveillance requirement of Table 4.3-1, as modified by Note (6)" This JFD does not appear to be consistent with CTS as the JFD states. The CTS note 6 only refers to incore-Excore calibration above 75% of RTP. The portion about " equilibrium"is added to the CTS Note (6) in Enclosure 2 as redline. Provide data to support the statement that operating experience shows 72 hours is required to perform the SR. FLOG RESPONSE: For Callaway, CPSES, and WCGS, the justification for the proposed changes, originally provided in JFD 3.3-97, will be modified to include more detailed inforrnation about the current practices conceming the application of the CTS 4.0.4 exception to this surveillance. For DCPP, plant-specificjustification is provided in JFD 3.3-06. For Callaway, CPSES, and WCGS, the following has been added to JFD 3.3-97: These proposed changes address the current practices conceming the application of the CTS 4.0.4 exception to STS SR 3.3.1.6. The proposed changes to the STS SR 3.3.1.6 Note is provided to incorporate the SR 4.0.4 exception provided in the equivalent CTS surveillance (e.g., see CPSES CTS Table 4.3-1, Note l (6)). For CPSES and WCGS, the current practice conceming the application of the CTS 4.0.4 exception is to defer the multi-point incore-excore calibration until a scheduled testing plateau l above 75% is attained during the post-outage power ascension. Based on plant experience, it is necessary to perform this calibration at power levels at or above 75% RTP. During a post-refueling power ascension, it is usually necessary to control the axial flux difference at lower power levels through control rod insertion. For example, at CPSES, it was determined that a multi-point calibration performed well below 75% RTP resulted in excessive incore-excore axial flux difference deviations at full power. The deviations were attributed to rod shadowing effects on the base f!ux map and, to a lesser degree, the dependency of the axially-dependent radial leakage on the power level. To collect the data necessary to satisfy this surveillance requirement, it is first necessary to obtain equilibrium conditions at the appropriate testing plateau. A full-core " base" flux map is ! obtained. The control rods are then inserted into the core to initiate a swing in the axial flux difference (AFD). Several partial flux maps are then collected at various values of AFD. Based on plant operating experience, failures in the flux mapping system can result in extended data i ! collection times. The plant is then retumed to a stable condition. The test data is then analyzed and reduced, and the appropriate calibration data for the excore data is calculated. l

The excore detectors are then adjusted, as necessary. Based on plant experience, after equilibrium conditions are achieved at the specified power plateau, approximately 24 hours are required to perform the base flux map, initiate the required AFD swings, and collect the required data. The data is typically analyzed and the appropriate excore calibrations are completed within the following 24 hours. Based on plant operating experience, an additional time allowance of 24 hours is provided during which the effects of equipment failures may be remedied and any required re-testing may be performed. For Callaway, a similar sequence is used during the post-outage power ascension; however, a single-point incore-excore methodology is utilized, rather than a multi-point mett,odology. Since an AFD swing and partial flux maps are not required, the time for performing the flux map and collecting the required data is less than the 24 hours discussed above (typically 4 to 6 hours duration). Similar to CPSES and WCGS, the subsequent 48 hours allow for the performance of excore calibrations and provide an allowance during which the effects of equipment failures may be remedied and any required re-testing may be performed. [Further, current practice at many plants is to administratively reduce the Power Range Neutron Flux - High setpoint until this and other surveillances (e.g., peaking factors) have been completed and it has been demonstrated that the plant is ready for sustained operation at full power in accordance with the design and licensing basis.] In summary, the proposed changes to STS SR 3.3.1.6 are more restrictive than the CTS, but are consistent with the current operating practices concerning the applications of the CTS 4.0.4 exceptions to the equivalent CTS surveillance. The proposed changes allow power asceilsions and associated testing to be conducted in a controlled and orderly manner, at conditions that provide acceptaDie results and without introducing the potential for extended operation at high power levels with instrumentation thct has not been verified to be acceptable for subsequent - use. ATTACHED PAGES: Enci6A 11b and 11c

CHANGE NUMBER JUSTIFICATION 4.3-1, as modifibd by Note (6) and current operating experience of I 72 hours for performing the SR.

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                               $pecitt m n EL4 M mnnusmeramenmurerenummmmmmmmmmawnesneswnnusanamnamnens                                                               ;

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CPSES Differencesfrom NUREG-1431 -ITS 3.3 lib 102088

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l associateditestinGEM3MBERM!Leonm]1eEMRet1Esannerzat con _djtionslthatlprW1;de']L:ceptableesults3!!dM.t._hou_tZintgucingithe Potential 11orfexteglediosta11eQtihgpokerJetelsligithJnstrumentation that*has~not been3erjQeditc[bela'ecentable?for3ubseQdentZusej 3.3 98 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-99 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-100 Not used. l l 3.3-101 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-102 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-103 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-104 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 105 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B), 3.3-106 ISTS 3.3.1 Required Actions B.2.2 and U.2.2 are not used, consistent with I the current TS requirements of LC0 3.3.1 Action Statements [1, 8, 9. and i 11] and the Applicability for ITS Table 3.3.1-1 Functions 1 and 20. The ; current TS provides for these Functions to be restored to OPERABLE status l with 48 hours or the plant must be in HOT STANDBY within the next 6 hours I when the plant is initially in MODES 1 or 2. Once HOT STANDBY has been l I reached, the shutdown mode applicabilities, i.e., MODES 3, 4, and 5. ; l prevail. When in these MODES, another 48 hour A0T is allowed by the j current TS or rod withdrawal must be precluded in the next one ; l hour. Therefore, ISTS Required Actions B.2.2 and U.2.2 for TR 3.3 006 l ) Functions 1 and 20 in Table 3.3.1-1 are not necessary since the performance of Required Action B.2.1 and U.2.1 takes the plant to MODE 3, exits the Applicability, and requires entry into Condition C. This change is consistent with ITS 1.3 and 3.0.4 BR!ItrMeler11Mm35. CPSESDifferencesfrom NUREG-1431 -ITS3.3 11c 10B088

ADDITION ~AL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-107 APPLICABILITY: DC, CP, WC, CA REQUEST: Based upon operating experience to change thermal power in a controlled , fashion without challenging the plant and consistent with the current TS which does not have a 1 Completion Time for restoring one channel to Operable status; but does prevent going above P-10 until it is restored, the Cnmpletion Time for ITS 3.3.1 Required Actions F.1 and F.2 should be increased to 24 hours. 1 Comment: The CTS has no requirement on the time to restore inoperable intermediate range neutron flux interlock. ITS markup establishes a 24 hour time limit. Time limit is significantly longer than generic ITS limit of 2 hours. However, in the transition to the ITS markup, the CTS action has changed. Expliciijustification for a 24 hour time limit is not provided. Recommend adopting ITS generic limit of 2 hours or providing explanation of hardship from not complying with ITS generic limit. In addition, the JFD statement that CTS does not " prevent going above P-10" is more correctly stated that power is not allowed to exceed the P-10 setpoint. {TSTF-246} FLOG RESPONSE: The FLOG continues to pursue the changes proposed in traveler TSTF-246. When operating between the P-6 and P-10 permissives, the intermediate range nuclear. , instrumentation channels provide core protection for reactivity accidents. If one intermediate range channel becomes inoperable, Condition F is entered. If Required Action F.1 were followed and THERMAL POWER reduced below P-6, the main turbine and generator must be removed from service and feedwater supply must be transferred from the main feedwater pump to the motor-driven startup feedwater pump. In addition, since the plant is not maintained at P-6, the RCS would be borated to MODE 3 conditions, control rods inserted, shutdown margin verified periodically, and all MODE 3 change requirements must be met. If Required Action F.2 were followed and THERMAL POWER increased above P-10, the following major plant evolutions are performed: Start a main feedwater pumps while controlling SG water levels and retire motor-driven startup feedwater pump; Make required RCS boron concentration changes; Align auxiliary systems and warm secondary side (including main turbine chest and shell); j Place feedwater pre-heating in service; l l Roll main turbine and ensure all Turbine Trip Function surveillances are current-; and l Synchronize the main generator. Depending on plant status and power level at the time of Condition F entry, neither ITS 3.3.1

Required Action F.1 nor F.2 maybe able to be performed in a controlled manner within 2 hours. Obviously, F.1 can be performed more quickly than F.2. However, given the desire to perform these low power. evolutions in a controlled manner and the "OR" logic connector between F.1 and F.2, the Completion Time of 24 hours from traveler TSTF-246 was adopted (the Traveler Status Sheet had identified this as a proposed traveler under WOG Mini-Group Action item

      #145). DOC 1-07-LS-3 and NSHC LS-3 provide discussions establishing the lack of any adverse safety impact associated with this change. This change has been previously approved for Vogtle.

ATTACHED PAGES: Enci5A Traveler Status Sheet Enci6A 12

'By

+u g e

               .    .              _     . _ _ _ _ -    _ _ _ _ . ~ _ _ _ _ . . _ _ _                     .. _ ._ _. _ _                    ..

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 TRAVFLER # STATUS DIFFERENCE # COMMENTS TSTF-19. Rev. 1 Net]ncorporated NA "et "RC epproved as of cut off d;tc. == YN NM 1 ru.< w . TSTT 35, ncv. 2 11werperated 3-3-34 . L TSTF 37. Rev. 1 Not Incorporated NA ITS 5.6.8 still addresses PAM reports. Sections after ITS 5.6.7 were not renumbered. TSTF 51 Not Incorporated NA Requires plant specific reanalysis to establish decay time dependence for fuel handling accident. TSTT 01 Not In:ciparated NA [ ] Alle.;;bic '!alues TR 3 3 005 5 i for 1033 cf voltage and ! degrcded voltasc .;ill rc;;in in th; TS. TSTF 111, Rev. 1 Incorpr ed NA TSTF 1353ReyG13 Part+c' 3.3 41 Travcicr is tsc broad ~ l TR-3.1-006 5 Incorpor ted 31333 scop; in naturc; 3iE90] should h vc k ca 32112 scvcr:1 separate travcicrs. 3.3 93, Portion:; cf tk travcicr that 3.3 95, significantly clarify 32 100 cpcr;bility requirc; cats hvc 3.3-122, k ca incorporated. 3.T*Ija TSTF-161, [ tee Incorporated 3.3 79 AfstoVili(IbYitheGNRC 03. -79 l TSTF-168 Incorporated 3.3-43 ggif6Wd~tFAllelNRQ 03. 43 l TSTF 169 Incorporated 3.3 42 gipt'oepilHT2heINRCY TR-3.1 003 l

  \                                                                                                                                             \

WOC 105 m g 2!2 Incorporated 3.3 49 l o.3. . 49 l Incorporated 3.3 107 WOC ".ini Croup Actica l 0 3.: 107 l Itc;;; #14S. traveler i.

CHANGE NlASER JUSTIFICATION 3.3-107 Based upon operating experience to change Thermal Power in a controlled fashion without challenging the plant and consistent with the current TS which does not have a Completion Time for restoring one channel to Operable status; but does prevent going above P-10 until it is restored, the Completion Time for ITS 3.3.1 Required Actions F.1 and F.2 should be increased to 24 hours. Condition F of ITS 3.3.1 is for one Intermediate Range Neutron Flux channel inoperable. Reactor protection would be provided by the Operable Intermediate Range Neutron Flux channel and Operable Power Range neutron Flux channels. Indication would be available from the Operable Intermediate Range Neutron Flux channel [from Operable NIS detectors] and from Operabla Pruer Ranae Neutron Flux channels with power aooroaching P-10.16; "cstinghouse 0 ncis Oroup is Csidcring a scacric ch;ngc on this issuc but delit; rations o.3.3107 ]wcrc ql i

                    --t capicted et the ti;c of our sub;ittal. SeelSTFj246]

3.3-108 Not used. 3.3-109 Not used. 3.3-110 Not used. 3.3 111 This change adds a note to ITS SR 3.3.1.7 for source range instrumentation to verify interlocks P 6 and P-10 are in their required state for existing unit conditions. This is consistent with the current TS and is an enhancement which is easily performed and provides additional assurance that the interlocks are functioning correctly. 3.3-112 Not used. 3.3 113 Not used. 3.3 114 Not used. 3.3-115 Not used. 3.3 116 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). l 3.3 117 Not ;pplicabic to C:'SES. Occ Conversica C a p; risen Tobic (Encissure SS'. DisEcha!)gmDJTSERM 0-3.3 117 WIttentss2rabH3D2138gEplstmeWat3B2EElDMEtesMM1gg ; l 9!@td m etaf2s519] l 3.3 118 This change is provided for consistency with ITS 3.7.10 Condition [G). l 3.3-119 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 120 ITS 3.3.1 Cendition 0 is revised to rc'icct ITS SR 3.2.4.2 and CN 3.2 IS in the 3/4.2 pockesc. Ndt3lTed] o.3,3 120 i 12 10BOM8 l CPSES Differencesfrom NUREG-1431 -ITS 3.3

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-117 APPLICABILITY: DC, CP, WC, CA I

l REQUEST: This charige to ITS 3.3.1 Condition R reflects current TS Table [3.3-1, ACTION i Statement 12] which was based on NRC Generic Letter 85-09. Comment: Reject-Beyond Scope -This generic change requires a staff approved l TSTF before acceptance in ITS. l 1 [WC)- Based on a comparison of the record copy of CTS T3.3-1 Action 12 the electronic markup appears to be missing CTS requirements. Therefore, the conclusion is that Condition R does not reflect CTS T3.3-1, ACTION 12, because there are , differences between CTS and STS that are not evaluated. ) l [DC, WC, CW) CTS requires 2 channels of RTBs to be operable. ITS requires 2 trains of RTBs to be operable. STS action R contains two Notes that address both channel and train inoperabilities. The ITS proposes to change Condition R to require actions based on RTBs which allows RTB bypass for up to 48 hours versus the 2 hours allowed , in Note 2 to Condition R. Provide additionaljustification. FLOG RESPONSE: Note 2 of ITS 3.3.1 Condition R is taken directly from the current TS (e.g., ACTION 12 for Functional Unit 19 in Table 3.3-1 for Callaway), allowing the RTB to bb bypassed for the time required to restore the inoperable trip attachment. Two hours, as included in the STS, is insufficient to perform the full range of troubleshooting, maintenance, and retest activities on an inoperable undervoltage trip attachment (UVTA) or shunt trip , attachment (STA) that may be involved. The time required will obviously depend on the nature of the inoperability, but the discussion below assumes the trip attachments must be replaced. 1 1 UVTA replacement may require the following actions: l Temporary connection of the new trip attachment (after QC parts verification); 1 Checks to ensure proper dimensional interfacing of the UVTA with the breaker trip bar l (must verify " pre-travel" gap between the roll pin and trip arm as well as the trip margin dimension); Permanent connection of the UVTA to the breaker secondary contacts; I Cycling the breaker at least 5 times to verify UVTA operation; Post-maintenance testing by the maintenance department to verify breaker response time (OC inspection point), dropout and pickup voltages, and UVTA trip force vs. breaker load; TS surveillances by the operations department involving a TADOT that includes an independent verification of UVTA and STA trips.

STA replacement may require the following actions: Temporary connection of the new trip attachment (after QC parts verification); Checks to ensure proper dimensionalinterfacing of the STA with the breaker (must verify " pre-travel" and total travel); Permanent connection of the STA; Cycling the breaker at least 5 times each at the maximum, nominal, and minimum STA voltages to verify STA operation; Post-maintenance testing by the maintenance department to verify breaker response time (QC inspection point) and verify the breaker trips at the minimum STA voltage; TS surveillances by the operations department involving a TADOT that includes an independent verification of UVTA and STA trips. The FLOG will retain the flexibility afforded by the current TS in this regard. As ITS 3.3.1 Condition R Note 2 reads, the RTB will be bypassed only for as long as it takes to restore the inoperable trip attachment.

 . As discussed in response to Comment Number 3.3-03, Condition R and its Notes will use the   ~
  *RTB train" wording.

For Wolf Creek, CTS Table 3.3.1, Action 12, a line of text was inadvertently deleted during the development of the conversion application. With the addition of the deleted test and reflecting the application of DOC 1-14-A, ITS Condition R does reflect CTS Table 3.3-1, Action 12. ATTACHED PAGES: l Enci5A 3.3-9 Enci5B B 3.3-48 and B 3.3-50 l Enci 6A 12 i Encl 6B 18 l

RTS Instrumentation 3.3.1 ; l ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME Q. One train inoperable. - --- -- - NOTE--- --- -- -- One train may be bypassed for up -y. . 32: to I hours for surveillance testing provided the other train 1 is OPERABLE. !

                                  ................................                                                                  1 0.1 Restore train to OPERABLE                        6 hours status.

E l Q.2 Be in H0DE 3. 12 hours I R. One RTB train -- - - --- NOTES -- -- - - -- - l inoperable. j; One train may be bypassed for up to 2 hours for . surveillancetesting3r - m3.3-4391 gigtgWicj, provided the other train is OPERABLE. , l

2. On; ",T" ;y b; byp:33;d for j

up to 2 hours for

                                            =;inten;n;;. en unirscit;;;                                                             i er ; hunt trip ;;;honis;;,                                                              '

previ i d th; other tr;in is aama."LE. t ! Z.J GnsmB2mim 2 N :or0A BaalEE3mRNWrit@~fol' \ 3.3 117 Q-3.3 117 unmensepummmtiom 3 . ,.. . .: 4. w , , u

( .. _............................ l i R.1 Restore train to OPERABLE 1 hour i status. ; i E l

i . R.2 Be in H00E 3. 7 hours 1 (continued) ' i CPSESMarkup ofNUREG-1431- ITS3.3 3.3-9 10B0M8 1

RTS Instrumentation B 3.3.1 BASES - l be placed in MODE 3 within the next 6 hours. The Completion Time of 6 hours (Required Action Q.1) is reasonable considering that in i this Condition, the remaining OPERABLE train is adequate to l perform the safety function and given the low probability of an event during this interval. The Completion Time of 6 hours (Required Action Q.2) is reasonable, based on operating experience, to reach MODE 3 from full power in an orderly manner l and without challenging unit systems. l The Required Actions have been modified by a Note that allows bypassingonetrainuptojhoursforsurveillancetesting, provided the other train is OPERABLE. i R.1 and R 2 Condition R applies to the RTBs in MODES 1 and 2. These actions address the train orientation of the RTS for the RTBs. With one train inoperable. I hour is allowed to restore the train to ! OPERABLE status or the unit must be placed in MODE 3 within the next 6 hours. The Completion Time of 6 hours is reasonable, based on operating experience, to reach MODE 3 from full power ih-an orderly manner and without challenging unit systems. The 1 hour and 6 hour Completion Times are equal to the time allowed by LC0 3.0.3 for shutdown actions in the event of a complete loss of RTS Function. Placing the unit in MODE 3 &#M,t sity TR-3.3 006 Co 6nd]is1i,nger8bleZrcr.exs th; icquir;. cat for thi; p;rticuler functi;n. The Required Actions have been modified b ~ tw $ ot @ ~

s. N;t; iM10ws one channel to bypassed for 3 a.3.3 117 g upto2hoursforsurveillancetesting3 ~)

provided the other t hannal is OPERABLEf; Ri a sa w a + ~. . 1 7 A !.w w v ca % W U rovided the o s :

                                            .; b; byp;ssed for up to 2 heur; for = int === n undcrvelter
                                           .. ..-        ~ . _ . . . . . . . , . . . - . . - .    . . , , , . ., . m. _ . IM

{ hour ti;;;; li;;;it is justified in "cf;rena 7 ? S.1 and S.2 ! Condition S applies to the P 6 and P 10 interlocks. Withonepg gyngdittg channelig inoperable] for en; cut-Of tw; er l tw; ;ut of-f;ur ;;inciden;; logic, the associated interlock must be verified to be in its required state for the existing unit condition 9EDb.5BEttBEREEnf3RRgtB31962nhuhClat013tlDjoW continued l CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-48 10B088

l RTS Instrumentation l B 3.3.1 , l BASES . 1 i l to perf- maintenance to one of the diverse feature

u. ~_ . m. . a. ._m._.~_

                                                          ..         . ...n......,-....______,
                                                                       .__           __a_
                                                                                           . . . . ~ 6 of the divers; featurcs is 2 hours for the reasons st:ted tmdciondition n.

The Completion Time of 48 hours for Required Action U.1 is reasonable considering that in this Condition there is one remaining diverse feature for the affected RTB, and one OPERABLE RTB capable of performing the safety function and given the low probability of an event occurring during this interval. Yzi

                          ith two I,TS trains inopcrobic. ac outc;;;; tic cape.bility is availabic to shut down the reactor and i=cdiate plant shutdown in accordance with LCO 3.0.3 is rcquired.

SURVEILLANCE The SRs for each RTS Function are identified by the SRs N REQUIREMENTS column of Table 3.3.1-1 for that FunctiontandMMMQQ. A Note has been added to the SR Table stating that l 0-3.3 55 Table 3.3.1-1] determines which SRs 5tifCRt)11tEdRMRdEMil yerficatfoA apply to which RTS Functions. ly % t IINEf"ri4f.dtt]jgTyr,1f, f l E336E j Note that each channel of process protection supplies both trains of the RTS. When testing Channel I, Train A and Train B must be examined. Similarly. Train A and Train B 1 must be examined when testing Channel II, Channel III, and I Channel IV (if applicable). The CHANNEL CALIBRATION and COTS are performed in a manner that is consistent with the f assumptions used in analytically calculating the required channel accuracies. Is vicucr's Note. C-ertain ircquencics cre based on approval , topical icports. In ordcr for a liccascc to usc thcsc tir.cs, the l licenscc ;;;ust justify the frequcacics as required by the staff j

SEPs for thc topical report. !

l i l i SR 3.3.1.1 t l Performance of the CHANNEL CHECK once every 12 hours ensures that l gross failure of instrumentation has not occurred. A CHANNEL , CHECK is normally a comparison of the parameter indicated on one CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-50 10B038 _u

  . .-             -. . _ - ~ _ - - - _ . -                  - - - . .- . - - . . _ . - - .           - _ - _       . . = . _ . - . _

l CHANGE I NUleER JUSTIFICATION ! 3.3 107 Based upon operating experience to change Thermal Power in a controlled i fashion without challenging the plant and consistent with the current TS ! which does not have a Completion Time for restoring one channel to i j Operable status; but does prevent going above P-10 until it is restored. the Completion Time for ITS 3.3.1 Required Actions F.1 and F.2 should be

                                  ' increased to 24 hours. Condition F of ITS 3.3.1 is for one Intermediate                             l l                                   Range Neutron Flux channel inoperable. Reactor protection would be                                   l provided by the Operable Intermediate Range Neutron Flux channel and Operable Power Range neutron Flux channels. Indication would be available L                                    from the Operable Intermediate Range Neutron Flux channel (from Operable NIS detectors) and from Operable Power Range Neutron Flux channels                                  !

with power approaching P 10. h ";stinghou;; 0 ncr; Creup is '

1 1 considering a gn;ri; ch;ng; en this i;;uc. but d;11bcretion; are o.3.3 107 l not c;;pleted et the ti;; cf ;;r :ab;ittel. SeelpmzE 3.3 108 Not used. 1 3.3 109 Not used. i 3.3 110 Not used. l 3.3 111 This change adds a note to ITS SR 3.3.1.7 for source range instrumentation i to verify interlocks P 6 and P-10 are in their required state for existing ' i unit conditions. This is consistent with the current TS and is an enhancement which is easily performed and provides additional assurance that the interlocks are functioning correctly. 3.3 112 Not used. 3.3 113 Not used. 3.3 114 Not used. , a 3.3 115 Not used. , 1 3.3 116 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). l 3.3 117 et ;pplic;bl; t; OPSES. S;; 0;n';;rsien C a p; risen T;ble (Encle;;raSS). M M M C0ff4mMEimStItWinntB5HRflCMilWSB4tlK G GRil1& M & Mj 3.3 118 This change h3 provided for consistency with ITS 3.7.10 Condition [G). 3.3 119 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 120- ITS 3.3.10;ndition 0 is revi;;d to reflect ITS S" 3.2.4.2 and 0% 3.2 15 in th 3/4.2 p;;kogc. R8 3 d138d 0 3.3-120 12 IW3M8 CPSES Differencesfrom NUREG-1431 -ITS 3.3

L Page 18 cf 22 CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 SECTION 3.3' APPLICABILITY TECH SPEC CHANGE DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION N/A N/A N/A N/A 3.3-115 Not used. Yes No No No 3.3-116 ACTION J of ITS 3.3.2 is not used since DCPP does not rely on motor-driven AFW pump start with loss of both main FW N8 ' r,c c 3.3-117 This change to ITS 3.3.1 Condition R reflects current TS Yes E Yes r,ct M c;., , c .; A Yes s #es Y l0-3.3-11 ' l Table [3.3-1, ACTION Statemen } which was based on NRC Generic Letter 85 09. Yes Yes Yes Yes 3.3-11B This change is for consistency with ITS 3.7.10 . Condition [G]. No No No Yes 3.3-119 This change reflects Callaway-specific BDMS analysis restrictions associated with RCS mixing volume and dilution flow rate. These are administratively controlled under the current TS, as approved in OL Amendment No. 94 dated March 7, 1995. However, with the conversion to ITS 3.3.9. these analysis assumptions should be included in the body of the TS. N l 0-3.3-12l

                   -b-.kb.. Ib,!,,'I.I,~..,..e  ~
                                                                                                                 ,)) N!b!

n . n 5$ l No No Yes 3.3 121 For Callaway ITS 3.3.9 is revised to reflect that only one No BDMS train is required OPERABLE in MODE 5 and that the suspension of positive reactivity additions and accelerated SDM verifications are required only if no source range neutron flux indicator is OPERABLE. Yes Yes Yes Yes 3.3-122 ITS 3.3.1 Applicability Note (b) for Functions 1. 5, 19-21 TR-3.3 O'l6 l and Conditions C and K are revised to replace Actions requiring the RTBs to be opened with actions that ensure subcriticality is maintained (i.e., by fully $nitiating actjenitojinsertimg all rods and ensuring the Rod Control System is incapable of rod withdrawal) yet do not initiate ' a feedwater isolation (P-4 and low T, ) in MODE 3, consistent with traveler TSTF-135. CPSES Conversion Comparison Table -ITS 3.3 102088 ' 1

4 ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-120 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.3.1 Condition D is revised to ieflect ITS SR 3.2.4.2 and CN 3.2-15 in the 3/4.2 package. Comment: Reject - The ITS proposes generic changes to the STS that are in not TSTF-109. Revise the ITS to adopt the STS. Based on 8/14/98 meeting staff is considering a conforming LCO 3.3.1 changes for consistency with TSTF-109. FLOG RESPONSE: JFD 3.3-120 is withdrawn. The Note above ITS 3.3.1 Required Action D.2.2 has been revised to reflect the STS, NUREG-1431. Bases changes have been made to clarify that the performance of ITS SR 3.2.4.2 per Required Action D.2.2 is subject to the SR 3.2.4.2 Note. s ATTACHED PAGES: " Enci2 3/4 3-6 Enci 3A 7 and 13 Enci38 4 and 9 Enci5A 3.3-3 Enci 5B B 3.3-39 and B 3.3-40 Enci6A 12 Enci 6B 18

TABLE 3.3-1 (Continued) ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Himatma g"":- gggited Channels OPE"XLE ccquir;nrt. restore the inoperable channel to OPERABLE status within 48 hours or be in HOT STANDBY within the next 6 hours. i ACTION 2 - With the number of OPERABLE channels one less than the Tet-el Nu;bcr ;f M Channels. STARTlJP and/or POWER OPERATION m*:

                                                                                              ^        ~- -

may proceed provided the following conditions are satisfied. , 1

a. .The inoperable channel is placed in the tripped condition within 6 hours,

b. The "ini;;; Channel: 0"E"#LE requir;xat i; ;r.ct; 91443-AM how icr, lloteDthe inoperable channel or another #1'17'A M channel may be bypassed for up to 4 hours for setpoJtit3dysteegt~yrj surveillance testing per Spaification 4.3.1.1, and

c. Either. THERMAL POWER is restricted to less than or equal to 75% of RATED T1lERMAL POWER :nd the MW

                                   ";wcr ";ng- Ncution Flux Trip Sctp; int i; reduad to ic;; th;n er cqu;l to 05% of "#EO               1-9.A T!!E""X "%'E" within 4 Ig hours: or 1 tith]q            '

0 3.3-120 pogGraggejBleDitMEDEjtiputito3M;0UADRANT POWER TILT RATIO isliggpetab]e ZthtE is monitored at least once per 12 hour 1 66 LS Spaification 4.C.4.1. 0 3.3.3 De!!! OtherwisersbelstrCHOTISTANDBY;ttithg12:hoors7 LET1002112 Wigthe3lgdteyMJ!PEitMEEElkiMtlGDOlesOth!Gthg Re#81.tedlEhMBWN.29fitRER$TEIt & M oceed st@dgR p_rwids!MEMieltlGR35BGBigBQLrQB1811*ff E HemanmMatmetaElumineOln%hestMed M , bl / i O '.e 4 ;M W TBgBRLthpMM suamuna Mo wL

                            . m 3. :. m;. . x . ; g_; a
                                                                                           ^

CJ 6MitMirthCDdRtFhatits? :

                                                                                                 'y         i ACTION 3 -       With the number of channels OPERABLE one less than the MWous                              I BggQt@jChannels 0"E"XLC requircxat end with the SC""X PC C 1rici;
                   ;.       Sci;w the " 5 (Intc.xdi;tc ";ngc Neutron flux                      WM Interlec!O S:tpoint. rc:itorc the inspcr;bic chonnci to OPE"XLE :t;tu; prior to inic;;ing T.'E""X "2E" ob;vc
                            -.e it_ n m yv ......

c_i__,_ t

                                              - ., ~ - _   =-a---             -%                            ;

_ _ _ _ ~ __=n-.-c_-

  "" ~ - W.W-O               W--uw----;,._------
                                  '5O$C-_..N~?A                   S?   =?
                                                                                -  *m         }.%.A          '
              -.  ..m_

Q 3.3 120 w v. u-CPiE9 Markup o a 1 ".! M *-6 1020/98

l l l CHANGE NUMBER EE DES'CRIPTION If the above actions are not c lated. the plant must 0 3.3e be in MODE 3 within 12 hours. (Sc 31= CN 1 5::3 i 1-19 LS 8 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38). 1 20 A Not applicable to CPSES. See Conversion Comparison Table l (Enclosure 3B). 1 21 A The monthly and quarterly channel calibrations associated with Notes (3), (4), and (6) of current TS Table 4.3.1 have been moved from the Power Range Neutron Flux- High l Setpoint Function to the Overtemperature [N 16] Function. This change clarifies the relationship of these l surveillances to the f3 (aI) penalty portion of the Overtemperature [N-16] Function. The primary purpose of these surveillances is to verify correct f (aI) input to 1 l Overtemperature [N 16]. Although these surveillances affect all power range instrument channels, and appropriate action must be taken for any affected power range neutron flux channels, this change groups the1 surveillances with the most appropriate reactor trip - function for operability concerns. [] The applicable portions of current TS Table 4.3-1 Notes (3) and (6) are incorporated directly into ITS SR 3.3.1.3 and SR 3.3.1.6, as discussed in CN 1 25 A. Note (4) has been deleted from the daily, monthly, and quarterly surveillances associated with Notes (2), (3), l and (6) of current TS Table 4.31 since these l surveillances are not CHANNEL CALIBRATIONS: rather they are comparisons and adjustments as needed. These changes are consistent with NUREG 1431 Rev.1. 1-22 M Quarterly COTS have been added to current TS Table 4.31 for the Power Range Neutron Flux Low and Intermediate l Range Neutron Flux trip functions in the event extended operation within their Applicability (i.e., MODE 1 below P 10 and MODE 2) takes place. The current TS only require a COT prict to startup for these functions. New Note [(17)] has been added to require that the new ! quarterly COT be performed within 12 hours after reducing power below P-10 for the power range and intermediate range instrumentation (P-10 is the dividing point marking the Applicability for these trip functions), if not performed within the previous 92 days. [In addition, ! Note (9) has been revised] such that the P 6 and P-10 CPSES Description of Changes to CTS 3N.3 7 102088

CHANGE NUMBER EBC DESCRIPTION l nore appropriately controlled outside of the TS while the l underlying requirement to verify proper permissive l operation is unchanged. ! N l 1 53 A Curicat TS Tabic 3.3 1 AC'!0N,vcStet acnt [2.c] is __.. __ q t. ___,___..uu en , ,,, __

                                        ' mCE

d. ~ m/ [...m M,",l" C.,'7%'d

                                                                  -m
                                                                      'I... M..I L.,',/.-.e
                                                                                             ;" C  ,_I'. - .            0 3.3 120 M

1 54 LS 37 Not applicable to CPSES. See Conversion Comparison Table ! (Enclosure 38). 1-55 LS 39 [ Applicability Note [a] and] ACTION Statements [5 and 9] I for Functional Units [1, 6.a.2),19, and 20] of current TS Table 3.3-1 are modified to provide an alternative to 1 opening the reactor trip breakers (RTBs) while still l assuring that the funcuon and intent of opening the RTBs is met. As currently worded, these ACTION Statements result in a feedwater isolation, signal (FWIS) when in l H0DE 3 with a T., less than [564*F.] A more generic action, @,1ch @lresithat: action ~beLtaMto TR-3.3-006 l assures the rods are fully inserted and cannot be ! . - , withdrawn, replaces the specific method of precluding rod ~

withdrawal. The revised Applicability and ACTION -

! Statements still assure rod withdrawal is precluded. This change does not involve any safety impact and is

consistent with traveler TSTF 135.

I 1 56 A Not applicable to CPSES. See Conversion Comparison Table 1 l (Enclosure 3B). l l 1-57 LG Current TS Table 3.31 Functional Units [12.a and 12.b] are combined per traveler TSTF-169. The Required Channels, ACTION Statement, and Surveillance Requirements are the same for both Functional Units. The only difference between the two is the Applicability which could lead to entry into ACTION Statement 6 for Functional Unit (12.a], followed by a power reduction below P 8, exiting the Applicability and required actions for that j Functional Unit, and subsequent re entry into ACTION Statement 6 for Functional Unit [12.b]. This would ; l involve an improper cumulative A0T of 12 hours before j l tripping an inoperable channel, beyond that evaluated in i WCAP 10271 and its Supplements. The relationships between these Functional Units and permissives P 7 and P 8 are moved to the ITS 3.3.1 Bases. i 1-58 A In the SRs for RTS and ESFAS response time testing, the the active verb is changed from " demonstrated" to

                                         " verified." This change would allow Reactor Trip System CPSES Description of Changes to CTS 3N.3              13                                                      10B088 l                                                                                           -                                        -

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 4 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY CANYON PEAK 1-13 [] ACTION Statement [8] is [] revised to require restoration of an inoperable Yes Yes Yes Yes LS-6 RTB within 1 hour or the plant must be in HOT STANDBY within the next 6 hours. This is less restrictive since an additional hour is provided for the transition to HDDE 3. 1-14 In the ISTS Table 3.3.1-1. Function 20. the Reactor Trip Breaker (RTB) Yes Yes Yes Yes A Undervoltage and Shunt Trip Hechanisms are separate from the RTB Functional Unit. The current TS have been revised to reflect these requirements. New [ footnote [(j) in Table 3.3-1 and (f) in Table 4.5-1 have] been added to the RTB Functional Unit to note that the same OPERABILITY requirements end ACTIONS apply to a bypass breaker if it is racked in and closed for bypassing an RTB. The bypass breakers were already handled in this fashion. ACTION Statement [11] in current TS Table 3.3-1 has been revised accordingly. 1-15 The Applicability for the Reactor Trip on Turbine Trip function is modified by No - see CN No - already Yes Yes A new footnote [(c)] such that this function is only required to be OPERABLE above 1-48 LS-4. in current TS. the P 9 interlock setpoint (50% RTP). This is acceptable since the trip function is blocked below P-9. [New] ACTION Statement [39] is applied to the Low Fluid Oil Pressure and Turbine Stop Valve Closure trip functions. 1-16 The requirement to verify the setpoint during quarterly TAD 0T for RCP Yes Yes Yes Yes LS-40 Underfrequency [ ] is deleted. 1-17 The bypass allowance can be used for surveillance testing or setpoint Yes Yes Yes Yes A adjustment. Setpoint adjustment can be performed at power and may be required by other Technical Specifications. 1-18 The current TS requirement to reduce the Power Range Neutron F ux Trip setpoints Yes Yes Yes Yes -12,., LS-7 in the event a power range flux channel is inoperable is deleted. The time to reduce power below 75% RTP is increased from 4 hours to 12 hours and, if a s / are nnt completgd as required', the unit must be in H0DE 3 in 12 hours. N

         @c CN 153 O {_                _                                         f CPSES Conversion Congwrison Table - CTS 3M.3                                                                                                                                          10B088

CONVERSION COMPARTSON TABLE - CURRENT TS 3/4.3 Page 9 of 22 TECH SPEC CHANGE APPLICABILITY DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER DESCRIPTION CANYON PEAK For DCPP. a new note (f) is added and applied to the Functional Unit 6.c. The Yes No No No 1-47 A note is for clarification only as the current TS Table 3.3-1 indicates that only 1 channel is required to be OPERABLE and that there is no trip function under these conditions. For DCPP. CTS ACTION 7 is revised to allow a reduction in power below P-9 in Yes No No No 1-48 LS-4 lieu of tripping the inoperable channel. The action is also revised to allow

bypassing a tripped channel for four hours for surveillance tasting other channels. Note (.1) is added to Table 3.3-1. Applicable Itn for Functional Unit 17.a and b that states that the requirements are only applicable above P-9.

for DCPP, CTS ACTION 9 is deleted and revised ACTION 6 is used which allows a Yes No No No 1 49 LS-18 power reduction below P-7 in lieu of tripping the inoperable channel. Note (g) is added that specifies that Functional Unit 19 of the CTS does not have to be applied until the power level associated with P-7 is reached. ACTION 6 also allows the tripped channel to be bypassed for up to 4 hours to perform surveillance testing on other channels. ; 1 50 ACTION [12] of the CTS duplicates CTS ACTION [2.1, as revised] and is deleted. Yes Yes No - not in No - not in A current TS. current 15. This change moves the description of the P-7 inputs. i.e.. P-10 and P-13. to the Yes Yes Yes Yes 1 51 LG Bases since they are duplicated by Functional Units [18.e and 18.f] and lists"1 ' per train

under the Required Channels column. [ ]

1-52 This change moves the specifics on how to verify permissis* functions of Yes Yes Yes Yes LG ACTIONS [7] prJdkTabM49digstanpland [18] to the Bases. ( _ 1-53 ,,,- [tgjgtsstediCucccc.t 5 T; tic 3.01/.CT!0" St;t ~.. [0.c] i; rcvi;cd t; bc Ves M Ves M Ves M Ve A ce. i;tcat with IE 5 3.2.4.2. ;; di;cu ,,cd i- C" t Oi LS-12 in thc 3/4.2 . s y 0-3.3-120 _g;.q , Y _ f CPSES Conversion Comparison Table - CTS 3M.3 &&& t - - - - _ _ _ _ _ _ _ __ _ ___-_ _ . _- _ _ _ _ _ ___________ _ _ ___

                                                                       .               RTS Instrumentation                        ,

3.3.1 j i

0. One Power Range Neutron ------------

NOTE---- -- ------ Flux-High channel The inoperable channel g inoperable. O ,.n <Y . ay be bypassed , for up to 4 hours for I surveillance testing and setpoint adjustment of other i channels. D.1.1 Place channel in trip. 6 hours eBD D.1.2 Reduce TliERMAL POWER to 12 hours s F5% RTP. E D.2.1 Place channel in trip. 6 hours AND

                                  .............-N0TE                                                    ~

Onlyt required to be ! performe g gj = r n ;.i;; q . dr~t%r;f'Zhnthepn;the, _s-s.4ee

                                                                                                                         ,       l i

Power Range Neutron Flux QJ 0 3.3 120 S inpytp o QPTR is inoperab w e , ;cl.f.".1",Jis4 yp.,,, ~.1 _ Once per 12 hours 0.2.2 Perform SR 3.2.4.2. M 12 hours D.3 Be in MODE 3 l (continued) l l I l l l I' i CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-3 1030M8 h

RTS Instrumentation B 3.3.1 i BASES . l l g .3;=tp.A g.;w... ., . .m y z.n ; .3. ; y . l IAEW S.1 b . r .:'.r. : n a- H' - ; : cum. - 1 M3,nk s ; 4 ; e ..) . J. ' d .

                                                                 .?-  -h i ,&y &M M

D.1.1. D.1.2. D.2.1. D.2.2. and D.3 Condition D applies to the Power Range Neutron Flux-High Function. The NIS power range detectors provide input to the CRD System cr.d the SC L'cter Lcycl Cor, trol Systa;;; and, therefore, CP 3.3 009 have a two out of-four trip logic. A known inoperable channel must be placed in the tripped condition. This results in a partial trip condition requiring only one out of-three logic for actuation. The 6 hours allowed to place the inoperable channel in the tripped condition is justified in WCAP 10271 P-A (Ref. 7 5). In addition to placing the inoperable channel in the tripped condition, THERMAL POWER sust be reduced to s 75% RTP within 12 hours. Reducing the power level prevents operation of the core with radial power distributions beyond the design limits at a power level where DNB conditions may exist. With one of the NIS power range detectors inoperable,1/4 of the radial power distribution monitoring capability is lost. As an alternative to the above actions, the inoperable channel can be placed in the tripped condition within 6 hours and the QPTR monitored y 12 hours as per SR 3.2.4.2. 0 3.3-120 QPTR verification 6,.? 7- n, -wg Calculating QPTR every 12 hours compensaces ivr me iusc monitoring capability due to the inoperable NIS power range channel and allows continued unit operation at power levels > 75% RTP. The 6 hour Completion Time and the 12 hour Frequency are consistent with LC0 3.2.4 " QUADRANT POWER TILT RATIO (QPTR)." As an alternative to the abe*19 Actions, the plant must be placed in a MODE where this Function is no longer required OPERABLE. Twelve hours are allowed to place the plant in MODE 3. This is a reasonable time, based on operating experience, to reach MODE 3 from full power in an orderly manner and without challenging (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3 39 10B088 l u

                                          ._m                 _.           _ _ .

I l l RTS Instrumentation B 3.3.1 BASES . 1 plant systems. If Required Actions cannot be completed within their allowed Completion Times. LCO 3.0.3 must be entered. l The Required Actions have been modified by a Note that allows ! placing the inoperable channel Egigtglggggume] in the bypass condition for up to 4 hours while performing routine surveillance testing of othcr chcr.aci;. The Note also allows placing the inoperable channel in the bypass condition to allow setpoint l adjustments of other channels when required to reduce the setpoint in accordance with other Technical Specifications. The , l 4 hour time limit is justified in Reference 715] ! 1 Required Action n 2.2 has been modified by a Note whkh-en4y I rcquire M requiresistetet #wdhSR 3.2.4.2 M t Jcquir % 0 3.3 120 performeo if @.c u~uw ;RI 12.;.c,;r; ; =r 17.;.=Jrp; I ene, ower Range Neutron Flux input to QPTR becomes inoperable

                                     .mm. m _ , .,.y . Failure of a component in the Power Range ntub un fiux Cnannel which renders the Hiph Flux Trip Function inoperable may not affect the capability to monitor OPTR. As such, determining QPTR using th+s t_he movable incore                          ,

detectors once per 12 hours may not be necessary. u l E.1 and E.2 Condition E applies to the following reactor trip Functions: l

                           .        Power Range Neutron Flux-Low,                                                  i
                           .        Overtemperature AT 3 -36]
                           .        Overpower cENjJg
                           .        Power Range Neutron Flux-High Positive Rate; j
                           ;        Powcr Reagc !!cutrea flux "igh lJcgctive R;tc; I                           .        Pressurizer Pressure-High:Hncj
                            .       SG Water Level-Lew Low.-end (continued)

CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-40 1020/98 I . _

l CHANGE i NUleER JUSTIFICATION ! 3.3-107 Based upon operating experience to change Thermal Power in a controlled fashion without challenging the plant and consistent with the current TS which does not have a Completion Time for restoring one channel to Operable status; but does prevent going above P 10 until it is restored, the Completion Time for ITS 3.3.1 Required Actions F.1 and F.2 should be increased to 24 hours. Condition F of ITS 3.3.1 is for one Intermediate Range Neutron Flux channel inoperable. Reactor protection would be provided by the Operable Intermediate Range Neutron Flux channel and l Operable Power Range neutron Flux channels. Indication would be available l from the Operable Intermediate Range Neutron Flux channel [from Operable NIS detectors] and from Operable Power Range Neutron Flux channels l with power approaching P 10. The "c;tinghou:c Owners Creup is cen;idcring ; scacric ch;ngc en this is;;c. ht dclikr; tion; wcrc o.3.3 107 not capleted et the tiac of our :uhittel. SeelTSTF12462 3.3-108 Not used. 3.3-109 Not used. i 3.3 110 Not used. 3.3 111 This change adds a note to ITS SR 3.3.1.7 for source range instrumentation

to verify interlocks P 6 and P 10 are in their required state for existing unit conditions. This is consistent with the current TS and is an enhancement which is easily performed and provides additional assurance that the interlocks are functioning correctly. 3.3 112 Not used. 3.3 113 Not used. 3.3 114 Not used. i 3.3 115 Not used. 3.3-116 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 117 X;t opplicebic to CPSES. Occ 0;nscrsion Cap;rison T;bic (Encle;urc 03). B143halWGGEK43LCeditiogmeflets o.3.3 117 BNfrefit35~Jalgf23E39CIl0lGitag! aft $111]lMiichTett?jgtMW f@ 9e@r1GetteG5ltB 3.3 118 This change is provided for consistency with ITS 3.7.10 Condition [G]. 3.3 119 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). '.l 3.3 120 IS 3.3.1 Conditien 0 is revised t; rcficct ITS SP,3.2.4.2 :nd i CN 3.2 15 in the 3/4.2 package. igg!fs&d] 0 3.3 120 12 10B088 CPSESDsferencesfrom NUREG-1431 -ITS3.3

                                                                                                            -s t

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3 Page 18 cf 22 TECH SPEC CHANGE -APPLICABILITY DIABLO CANYON. COMANCHE PEAK WOLF CREEK CALLAWAY NUPBER DESCRIPTION N/A N/A N/A N/A 3.3-115 Not used. ACTION J of ITS 3.3.2 is not used since DCPP does not rely Yes No No No 3.3-116 on motor-driven AFW pump start with loss of both main FW pumps. Tht: change to ITS 3.3.1 Condition R reflects current TS Yes N; r.ct il cu.cc..t Yes Yes EMEMMIMEW 3.3 117 E Yes E 0-3.3-11 ' E Table [3.3-1. ACTION Statement 112] which was based on NRC Generic Letter 85-09. Yes Yes Yes Yes 3.3-118 This change is for consistency with ITS 3.7.10 . Condition [Gl. No No No Yes 3.3-119 This change reflects Callaway-specific BDMS analysis restrictions associated with RCS mixing volume and dilution , flos rate. These are administratively controlled under the current TS. as approved in OL Amendment No. 94 dated March 7. 1995. However, with the conversion to ITS 3.3.9. these analysis assumptions should be included in the body - of thye __ 3.3-120 d2.3.1 Carditic;; O i; cc.-i cd t; r;fk;t ITS S" 3.2.4.2 Ves_N/A Ves;'N/A VesN/A ' ord CN 3.2-10 17 th; 3/4.0 p;d ;;;. ll;t&used ( V For Callaway. ITS 3.3.9 is revised to reflect that only one No No No Yes 3.3-121 BOMS train is required OPERABLE in MODE 5 and that the suspension of positive reactivity additions and accelerated SDM verifications are required only if no source range neutron flux indicator is OPERABLE. Yes Yes Yes Yes 3.3-122 ITS 3.3.1 Applicability Note (b) for Functions 1. 5. 19-21 l %3.3 0-6 ll and Conditions C and K are revised tu replace Actions requiring the RTBs to be opened with actions that ensure subcriticality is maintained (i.e.. by fully 1r)1tiating ac1;1oni t oginsertieg all rods and ensuring the Rod Control System is incapable of rod withdrawal) yet do not initiate ' a feedwater isolation (P

and low T ) in MODE 3 consistent with traveler TSTF-135.

CPSES Conversion Comparison Table -ITS3.3 10B088

                                                      ._                 _____m _ _ _     _ _ _ _ _ _ -

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-54 APPLICABILITY: DC, CA, CP, WC REQUEST: Function 18.b (P-7) of ITS Table 3.3.1-1 is clarified. COTS and Channel Calibrations apply to the P-10 and P-13 inputs, not to the P-7 logic function. Comment: Reject - Deleting all SRs results in no TS requirements for establishing interlock operability. Revise the ITS to adopt the STS. Scopeissue FLOG RESPONSE: SR 3.3.1.5 has been assigned to ITS Table 3.3.1-1 Function 18.b (this was already discussed in the SR 3.3.1.5 Bases), as previously approved for Vogtle. JFD 3.3-54 has been revised for clarification. Except for DCPP, there are no current TS Enclosure 2,3A/3B, or 4 changes required since there is no surveillance listing for P-7 in CTS Table 4.3-1. WCNOC will now adopt JFD 3.3-54. For DCPP, the P-7 permissive is a derivative of permissives P-10 and P-13 and the CTS requires that the P-7 as well as P-10 and P-13 be surveillance tested via a COT and a CHANNEL CAllBRATION. There are no field sensors associated with P-7, there are only sensors associated with P-10 and P-13. There is also no place outside the SSPS to inject a simulated signal into P-7. There are no adjustable devices directly associated with P-7 and therefore no required range or accuracy values except via the P-10 and P-13 functions. There are no outputs from P-7 other than to the main annunciator permissive window and a digital output to the P-250. There are no interlock or trip functions outside the SSPS. Therefore the definition of a CHANNEL CALIBRATION and COT do not apply to P-7. The P-7 function does lend itself to testing that would meet the requirements of the definition of an ACTUATION LOGIC TEST. As noted in the Bases for SR 3.3.1.5," Perform ACTUATION LOGIC TEST", the P-7 logic is included in the SSPS testing that is conducted monthly on a STAGGARED TEST BASIS. This testing, however, does not verify the function of the main annunciator alarm that can only be tested during a refueling outage. Therefore, DCPP will apply SR 3.3.1.17 to the P-7 function in lieu of the CTS and STS required CHANNEL CAllBRATION and COT, which as explained above are inappropriate. j Refer to the Q 1-51 response for changes to the CTS. l ATTACHED PAGES: EnctSA 3.3-21 Enci 6A 6 Enci 68 9 i i

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 9) Reactor Trip System Instrumentation i APPLICA8LE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE fete FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUEst gggpogy;w - -

17. Safety .

1,2 2 trains Q SR 3.3.1.14 NA M Injection (SI) ' Input from Engineered Safety . Feature Actuation

        . System (ESFAS)

18. Reactor Trip j System Interlocks

a. Intermediate 2* 2 S SR 3.3.1.11 SR 3.3.1.13 2 Miff asp t-9E-+6 any pgg Range Neutron Flux, P-6

b. Low Power 1 1 per T KM NA 3.3 54 Reactor Trips train %335 m !

Block, P-7 -.....;- Q 3.3 54 i

                                                                                                  = !.3.1.1:

s

c. Power Range 1 45{ T 50:2 -

Neutron Flux, SR 3.3.1.11 M RTP ; '.C l:77 y,m ., k ".. P-8 SR 3.3.1.13

d. Power Range 1 45i T 52:2 s-50N-RfP iH).44 Neutron Flux, SR 3.3.1.11 35E35RTP Q 3.3 44 P9 SR 3.3.1.13

e. Power Range 1,2 45i S 7:e ; = :::r Neutron Flux, SR 3.3.1.11 M RTP P-10 SR 3.3.1.13 and +2:2 M RTP g l I

f. Turbine

                % amm 1                 2             T
                                                                                                  = :.:.:.:

49:2 mass s-tem

rim,e M '

M SR 3.3.1.10 turbine power ~ ' ~ ~ ' - Pressure, P-13 SR 3.3.1.13 power , 1

19. Reactor Trip 1,2 2 trains R SR 3.3.1.4 NA M l BreakersM(k) m g()

3*,4*,5* 2 trains C SR 3.3.1.4 NA TR 3.3 006 ! l (continued) (c) ::. . . . . . ' . L ; . . U. . : . .,,.e f . ' . ,,;- .;.; ; . -, - .; . . .; , id ; L;; 'J.; _ , . ; . . , . ;,~ ; . .; mw

.3, i.. 4.; .,,' ...,: ;,, J., .: . . e t 3- ,:-

                                                                                       ..     ' -    m.       '
                                                                                                                       - - - - .       .. W                      4-m:                           J. . q. . ,y,;y (b) With Afte-etoestend Rod Control System capable of rod withdrawal                                                                 V M

(s) Below the P-6 (Intermediate Range Neutron Flux) interlocks. (k) Including any reactor trip trypass breakers that are racked in and closed for bypassing an RTB. 3.3 122 1R 3.3 006 CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3 21 10B088

CHANGE NUPSER JUSTIFICATION 3.3 53 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3-54 function. change is an administrat ve shios between these interlocks i MtMee m k m totMet*Jp* 3.3 55 This change revises ITS SR 3.3.1.16 and SR 3.3.2.10 to verify veqtured" response times Pe'WithifGimitEgesifiedln,Q hel G E ], accommodating j those channels that have no response time requirements per the current l licensing basis. [As such, line item references to these SRs in Tables 3.3.1 1 and 3.3.2 1 can be deleted. The current TS do not identify which functions have a required response time.] The response time limits and the identification of those functions that have required response times are currently listed in a licensee controlled document: not in the current TS. This change makes the ITS consistent with this aspect of the current TS. [A similar 0 3.3 55 revision to the ITS 3.3.6 SR Note has]also been made regarding SR-3.3.6.8.] 3.3-56 This change revises ITS 3.3.2 Condition J to reflect current TS Table [3.3 2], Action Statement [23a which has been revised and renumbered as 23f in the CTS markup] for Functional Unit [6.e]. [The required action is to place the channel in trip within 6 hours rather than to restore operability within 48 hours.] CP 3.3 005 3.3-5'l "M ida 3822 di 3.3 58 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). < 3.3 59 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 60 Consistent with the plant design and current licensing basis, Surveillance Requirement [ 3.3.2.3 is] not used by any function listed in Table 3.3.2 1. Therefore, as an administrative change, SR 3.3.2.3 is changed to "Not used." 3.3-61 ThischangerevisestheITSSR3.3.2.11Frequencytoi18] months per current TS Table 4.3 2 Functional Unit [10.b], which is the oc n 001 l ESFAS P 4 permissive. The 18 month frequency for the surveillance I CPSES Differencesfrom NUREG-1431 -ITS 3.3 6 1020M8

CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3 Page 9 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3 49 ITS SR 3.3.1.8 is revised to extend the conditional COT Yes Yes Yes < Yes frequency for power and intermediate range channels from ! 4 hours after reducing power below P-10 to 12 hours, based on operating experience regarding the time needed to perform the COTS. It stands to reason that if 4 hours are allowed for 2 Source Range COTS 12 hours should be allowed i for 6 Intermediate Range and Power Range COTS. i 3.3-50 ITS SR 3.3.1.12 is deleted per the current TS. Where cited No - see CN Yes Yes Yes in Table 3.3.2-1. a change to SR 3.3.1.10 has been made. 3.3-101. 3.3-51 ITS ACTION B.2 of LCO 3.3.7 is deleted, since DCPP cannot Yes No No No operate CRVS with both pressurization systems running at the same time. 3.3-52 Added Note [(1)] to ITS Table 3.3.1 1 per the current TS as No - adopted ISTS Yes Yes Yes an operator aid to note the dual RTS/ESFAS functions of SG format. Water Level Low Low. 3.3-53 The REQUIRED CHANNELS description for Functions 2.a and Yes No No No 3.b.(1), of ITS Table 3.3.2-1, are revised per DCPP CTS to note that only two switches (one per train) exist and that both must be coincident for manual initiation. 3.3-54 Function 1R_h (P-7) of ITS Table 3.3.1-1 is clarift o Yes Yes c .dc;.tcd !5 Yes B 3'3 5 MISR13 31115tand'deleggi3Rij;5M113ngigg}## Ts fermet-Igg , anc Channel Calibrah awb tr " " N am r-u inputs. ._ w r not to the P-7 logic function. 3.3-55 Revise ITS SR 3.3.1.16 and SR 3.3.2.10 to verify ccy;cid- "; 5"; will bc Yes Yes Z: Will bc Yes response times 6 6 @ ug. rctcincd i- !TS rctci .cd '- !E l 3.3 6 l accommodating those channels that have no response time Titics for rc vircd Tibic; for re vircd , requirements per the current licensing basis. [As such. Functicn;.yes reetic ;. line-ites references to these SRs in Tables 3.3.1-1 and 3.3.2-1 can be deleted. A similar revision to the ITS s' 3.3.6 SR Note has also been made regarding SR 3.3.6.8.] CPSES Conversion Comparison Tabic -ITS3.3 10B088 e .-

6 ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-55 APPLICABILITY: DC, CP, WC, CA l REQUEST: Revise ITS SR 3.3.1.16 and SR 3.3.2.10 to verify " required" response times, acccivin,0 dating those channels that have no response time requirements per the current licensing basis. [As such, line-item references to these SRs in Tables 3.3.1-1 and 3.3.2-1 can be deleted. 7

A similar revision to the ITS 3.3.6 SR Note has also been made regarding SR 3.3.6.8.] Comment: Reject - The ITS proposes generic changes to the STS by deleting l SR 3.3.1.16 for applicable functions in T3.3.1-1 and modifying SR 3.3.1.16 that are not included in an approved TSTF. : Adoption of WCAP-13632 for eliminating selected sensor response time testing requires ; staff review independent of the Conversion TS review. TSB management sees no benefit to making this change because the proposed STS format introduces ambiguity in identifying TS required testing. Additionally, this change is generic and the staff has not received a TSTF request to review these changes. Bill notes that the i l staff is yPJy sensitive about changes to response time testing requirements and although ) the staff approved moving response time lists to owner-controlled documents, elimination ! of TS required RT testing requires a TS amendment in either the old STS fcnnat or in iSTS. FLOG RESPONSE: Based on meetings with the NRC held between September 15 and

;                September 18,1998, Diablo Canyon will also be taking this change. The Note preceding the l                 Surveillance Requirements in ITS 3.3.1 and 3.3.2 has been modified and the wording in ITS SR                        :

j_ - 3.3.1.16 and SR 3.3.2.10 has been revised to cite the licensee controlled document where the i response time limits are contained. In addition, surveillances originally modified under JFD 3.3-31 will be revised to be consistent with the changes to ITS SR 3.3.2.10 since the affected surveillances measure ESF RESPONSE TIMES. For WCGS, JFD 3.3-55 is now being adopted in its entirety, which also results in their adopting JFD 3.3-31. , L ATTACHED PAGES: Enci2 3/4 3-1 and 3/4 3-17 Enci 3A- 1a l Enci5A 3.3-11,3.3-15,3.3-32,3.3-33,3.3-56 and 3.3-60 Enci5B B 3.3-50, B 3.3-116, B 3.3-121 ani 7 3 3-169 Enci 6A 6 !' Enci6B 9 i 1

, 3/4.3 INSTRUMENTATION ! 1 63 A f ( Q 1 A GEN 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION l i 3.3.1 As a minimum.'the Reactor Trip System instrumentation channels and ! L interlocks of Table 3.31 shall be OPERABLE. I l-

l APPLICABILITY: As shown in Table 3.3 1. l l ACTION:385 l As shown in Table 3.3-1. 1 i SURVEILLANCE REQUIREMENTS l 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of p the Reactor Trip System Instrumentation Surveillance Requirements specified in

Table 4.31.

4.3.1.2 The ACTOR TRIP SYSTEM RESPONSE TIME of each1 Reactor E E trip function = mii ve demonstrated ggggd to be within its limit at y:.g least once per 18 months -

                                                                  -       =
                                                                               -- -- wuASLE**. E;;h t;;t ; hell                          ""

include et icest ea; trein such t;;t both treins ;re tested et icest en;; per 30 anth; end era chr.nnel p;r fur.cti;n such th;t ;11 ;Fr.ar413 er; tested - et 1;;;t en;; ;;;ry N ti.c; 10. enths Jar; N is th; t;t;l nu b;r ;f l redund;nt cher.ncl: in ; ;p;;ifi; .";;;ter trip functi;n s ster, in th; "T;tel N;. of CP.;nrals" ;;1;;; cf T;ble 3.31. T 7 of i t i i

.-(

l M [ l

                                         ,y _ _ . . : ;     _e yLy. _ ,;.._. p :, ,

M I i l i l 4 1 .I i p CPSESMarkup ofCTS 3N.3 3M 3-1 10B088

INSTRUMENTATION SURVEILLANCE REOUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3 2.

                                                                                                                                                                                          - 0 3.3 55 NGINEERED SAFETY FEATURES RESPONSE TIME of each 4.3.2.2 ESFAS function       ThM;;       mmoe demonstrated MttBIN to be within the limit at least once per 18 months J     1. .J.        A    1.-_A         ---           &_-J.          ...L       AL A           L_AL       &_       J _ -_. A                  _A      J   _A     1    ..A     __ .

Iurw5wu% ub asudb VI N t. s u s I a duvs i bq ru b vv b51 bi U i3tw us L b5dkwu ob asudb vi sww j _ _ ._ S c __ AL. -_J ___ _L.___1 ___ s..__AJ. ...L AL.A .11 _L___1. -_. i ywi wv suvs s bs ud us N vs N vs sus u rw a ywa u us sw w s vi a auwa e bs su b uas ws um si rw s a un s A .A.J A 1_-_& ____ .-_ M AJ--_ to ___AL. . .L___ M J. AL. L . A .1 ..._L__ .s b5JbEu ub awwwb wu Nw y%s vi b s uuss a A aurm ublad wi rw s L ri aw bsub hvbui s aussivw s vs

   ._  J. . J        & . L - - _1 _ J_                      -    .___JsJ.           f*e t" A P       s.._.&J-_               --      _L._             J. AL_

T _ L .1 M. .

s wuus suus a b ws sus si rw 3 J usa u wywwie sw s.su og a us sw b i vi i ud as avws a aas bN svbui viv . vi r=L-__ 1_a .1.__ . T L1. e s o vi sus as N s e wv i usses a oa auvsL w.w h. I l

   ,i.          TuJ. ..._... m .___ .                                 _t      J_A__...,             J_     .___Ja                   ..       ,J     ___       L.     ,_

g is s J Jus v u a a s us Nw bbwb a sibus su s sw wn bwu Nsu by s.'T uvvi s ba ia s vi g g ,,. M 6 L J_ .ss..A LL_ _- -1LJm_ .s &L. _____J Um

                                                                                          . . A J 1, fv,.

t_ J. s. L s. , b . . .u- J. s_. as, es,sub mbs

b. N hv rsubsms vs b. m .wwm N

! . s. . 1 4 ...A.. c__ s t_ J s a s._ st. s 11 .J _ s..__AJ.__ __J

L s uw a isry vubuyw a vi vu s a b s. , a va bs N u oaa vw Iu33 s us N b a vi sa ussu

( asJ.sa. 1_. l J, s_i s b a u b s m s . _J...N.. e . s.s . . t_2 _AJ _ r rr*ee s nL.__ =A* T 1.64._ A.mJ1J... r_.l..& wuuwby as syLw b Ivie gswww/, s I ru dw n & du I u b e vs ae nuA u e a us J 3 wwwwu bus ard " cr;c . y Ciescl Ocr,cratcr Opcraticr. cr Cor.tair...c ,t l'r ssure-- l 1 n_....._J_ _ n___.._. .... __J e. ._ . J__ n___.._.

                                 -nJ _L.

sw s A, sasoeus ambs a a weem w s.vw , u. N obs s. . N s a wa,ui f l

__ e .

t e vm _ t uis_.N s .i e___..n,..__ s bu wr, u, u y m, vvi . bu J. s_N . . bA ..w n___.... .w i n. . .,L. s 1.

                                                                                                                                                                                 ._J u, N TL___              s.._.AJ          __ . .J A L ______..                       s4___           ..LJ.L           -_. J_asa              s_J     L.. e..

s a tvww I us rw b i vu sJ w a kII s wsyvs ads b a svN J WI5 a ws a us L e s s a b a u bwu vg hvad

                                  . n.._                  re nLir        -_J      J a rtir e.s._.-_J.                       e.._A._           e L J _ _. . 1 & - _. s vs a vvvws                   g v . .rrs i unsu wv v wusLyuusuw wy a wwsn vs Nwn v v I buys / .

l 8 ! Mileq01cadMJg3gggggcGfg.3!Le@Lrb.1MRef?AFK~plupiDrit1U24 42-40iAid hourJIa.BPIRRgg$0!'gMEgt3Lterthanl5322Mg] l l i I I

                                                                                                                                                                                                                  .i J

f, s CPSESMarkup ofCTS3N.3 3M 3-17 10/30/98

l l CHANGE ! HUMBER !CitiC DESCRIPTION 1 i definition of STAGGERED TEST BASIS. However, several trip functions do not require response time testing, as indicated by N.A. in the tables of response time limits ! [previously relocated to a licensee controlled document. l l A note, which is currently located in the CPSES TRM, is ! added to denote that response time testing of the neutron and N-16 detectors R not required]. The improved TS specify thatClauiredjesponse 6ime i. be performed on a STAGGERED TEST BASIS and do not impose a requirements as to which train should be tested. l 0 3.3 55 Thereforgt.c wor: required" is added to ttp , C ircra TS er,dp oe requirement to ensure cnat each . l train is tested every [36] months is moved to the DC ALL 001 l Bases for ITS SR 3.3.1.16 and SR 3.3.2.10. 1 03 LS 1 Not applicable.to CPSES. See Conversion Comparison Table (Enclosure 38). 1 i i CPSES Description of Changes to CTS 3N.3 la 10B0/98 l

l RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS ........................................N0TE-- -- -- -- -- .-....------ -.......... Re .3.1 l'to determine which SRs for each RTS Function - 3.3 55 ) 0 3.3 55 l l i ................................................................................ j SURVEILLANCE FREQUENCY l SR 3.3.1.1 Perform CHANNEL CHECK. 12 h'urs l 1

SR 3.3.1.2 . - -

                                   - - - - NOTES . - - - . - - - - - . -                                           ,

1. Adjust NIS gjE167PcWeri!!onitor; channel res.3 334 )

if absolute difference is > 2%. I

2. Not required to be performed until 40 23 ~

                                                                                                         $823dNE hours after THERMAL POWER is a 15% RTP.

Compare results of calorimetric heat balance 24 hours l calculation to Nuclear Instrumentation System lN3$3Ed I (NIS) 864toJgfgchannel output. I SR 3.3.1.3 - - - ----- NOTES-- -- -- - -

1. Adjust NIS channel if absolute difference is a 3%.

2. Not required to be performed until -q-39 hours after THERMAL POWER is 2 454 5% RTP.

E Compare results of the incore detector 31 effective measurements to NIS AFD. full power days (EFPD) (continued) CPSESMarkup ofNUREG.1431 - ITS 3.3 3.3 11 10/3088

l l I I RTS Instrumentation 3.3.1 i SURVEILLANCE FREQUENCY SR 3.3.1.12 RIE M 0Al m, syv s s. ,....s

                 ,u,_        e.._.._,,,____           _m.,,      ,__,.2.     ..__,, ..,__ _,

tasas wun ww s e a un sww es su s a esswuwws wws ,u u wu b u vs s vs n___.__ e__,__. e . . __ ___,_.____ . - - - _ _ _ . . _ _ s sw ww bys u vv .uish WJ d bways t ud 3 d bui uww bumywnubutw L.__4.__

                 - .w.w              L,.-___e .

v y s. i, m . __.,.w_. 1.v_v__ .u in __ n

                 ,w,_ _ s. ._. _. _  e.n a uues ~e a~.t vnn w.....w               m .amy?rm,. .                                        m   ..~,.AL..

b. .

SR 3.3.1.13 Perform COT. 18 months SR 3.3.1.14 ---- - -- - -- NOTE------ ----- - --- - Verification of setpoint is not required. ) Perform TAD 0T. 13 months . , tensted SR 3.3.1.15 -

                                          -- - -- NOTE - - -                       - - -- -- -                 - - -NOTE             ---

Verification of setpoint is not required. Only required

                   ...............................................                                            when not performed within previous 31 days Perform TADOT.                                                                              Prior to reactor startup SR 3.3.1.16       --          - -

NOTE - -- -- - - - --- Ti H NeutronM detectors are excluded from response time testing. E Verify 62STS RESPONSE TIMESM 4s lamonthson a STAGGERED 3.3 55 within limits g1Qg3nttheer- Q BASISj 0 3.3 55 l l i l CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-15 10B088

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS

        ........................................N0TE                  -------------                     -- -

Refer to Table 3.3.2-1 to determine which SRs )

      -------------------g---                                                    eh ESFAS unction                 ..-             3.3 55 Q 3.3 55 l l     _,-                                                              s            -
        ...... .   .    ....         J...................................._                           .............

l l SURVEILLANCE FREQUENCY l i l SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours l SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 31 days on a ) STAGGERED TEST l BASIS l SR 3.3.2.3 "0TE The ;;ntinuity dc d =cy bc = luded. A

                                                                                                                                   ' 8 8E
                                                                                                                         ~

31 d y:; on a , l'crform AC"JATION LOCIC TEST. STAGGEREB-TEST BASM NKVRdj SR 3.3.2.4 Perform MASTER RELAY TEST. 31 days on a l STAGGERED TEST BASIS SR 3.3.2.5 Perform COT. 92 days SR 3.3.2.6 Perform SLAVE RELAY TEST. E days j~ 3*3'S SR 3.3.2.7 -- - -

                                                  ---- NOTEE -            - ---          ---

CP-3.3 005 EVerification of relay setpoints not required. 2 v.ActuatidtE6f5f1H8HdefiqEi. liggiic10dtd W ays s

                              ...............................................                                                        o.2 17

! Perform TADOT. l CPSESMarkup ofNUREG.1431 - ITS3.3 3.3-32 10B088

ESFAS Instrumentation 3.3.2 SURVEILLANCE RE0VIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.2.8 ---- ------------ - NOTE -- --- ------- ----- Verification of setpoint not required for I l manual initiation functions.

                  ...............................................                                                             l l

1 Perform TAD 0T. ]gmonths pgcog

,  SR 3.3.2.9        -- -- - -           --
                                                 - NOTE--- ------ -- - ------

This Surveillance shall include verification i that the time constants are adjusted to the prescribed values. Perform CHANNEL CALIBRATION. 18jmonths h@BN SR 3.3.2.10 -- ------ - --- - NOTE--- -- ------ ---- Not required to be performed for the turbine NFB W i driven AFW pump until 2_4 hours after SG pressure is 21000 g psig. EB9SW ,

                   ...............................................                                                          I kiJ48t @     !

VerifysMIAS ERRESPONSE TIMES are IQmonthson !

                                                        ==-1                            a STAGGERED            3.3 55       ,

within limitQr== TEST BASIS Q 3.3 55 !

SR 3.3.2.11 . .

                                   - - -- - NOTE--                   --    ------

Verification of setpoint not required. Perform TADOT. ]pMBlih5

n. - - ---

                                                                                        - n,                    hiMBs519 reactor trip brcckcr cycle p gl2]}g                 Perform CHANNEL CALIBRATION.                               9 months              R313:12f31 4
                                                                                                                          }

CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-33 10B088

             .-          . . ._ . _ . ..                      . --- - -.                                 ~ - .-.           -- . -- - - . .

l LOP DG Start Instrumentation 3.3.5 SR 3.3.5.3 Perform CHANNEL CALIBRATION with x tp; int E months ~: All;w:bic ";1 x - as follows: . . I

a. BR(etEREffsite sources undervoltage l L;ss of ';;1t;ge Allowable Value h MEidlEERM , , , .____;

2912 " with : tin 21:y of 3.3,132 o, {nv.wa A 6 a asww.su. 0 3.3 132 e... .c...,s...,.2. e.x..a s . m,e u

4. m.s i s y uvda vs vv i wup as a y vs byw s s a w _ , _ . _

LL - L2-. J1... .2 rn an . e n -- - J 'I * -- usa u kams wwsuy vs Lv.wJ A L J wwwwi su . p __,,..__,,.._..m., . .

AMcWabMaAtitiel!!*!iGRIBILM1490013, g$gi 6.9 kv Class 1E bus undervoltage 13 5.' j Allowable Value t 1935 V e,and. 5 3450 V

                      . .a s u .         .2-. J.,...      - en              e , ..-- J vs e b e i u       6 s uurw whauy vs          Lv.wg A L        J swwwi vu .

3 dbjg 6.9 kv Class 1E bus degraded voltage Allowable Valde 15933 V '" J.1. . . . rn ei i r 1 . -- J ,, _ ussuy vs Lv.vJ A L g ww wws iu . .. , j ,1 . . , - 3 yd3 480 V Class 1E bus low grid undervoltage 20 " i Allowable Value t 443 V with a tin delay N E '?

cf [^."] 1 [ ] second. _L.; . . ' .it -

l Iqig 480 V degraded voltage Allowable Value . , , .

                                                                                                                                                " "y ,

j 2 435 Y with a ti c deley Of - rn e1 i P 9 --- J Lv.wg A L J abwwi su . 1 M M l r.:T.?? l 2 1 CPSESMarkup ofNUREG-1431 - ITS3.3 3.3-56 10B0/98

Containment?Milettert Purgc cr.d a " houst Isolation Instrumentation $MfSM I 3.3.6 SURVEILLANCE REWIREMENTS , ........................................N0TE --- ------- - --- ----- - -- - Refer to Tahla ~4 't 1 1 to determine which SR Co , ure .. a. ..u - unc lon. SURVEILLANCE FREWENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours SR 3.3.6.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.6.3 Perform MASTER RELAY TEST. 31 days on a , STAGGERED TEST BASIS SR 3.3.6.4 Perform COT. 92 days 1 SR 3.3.6.5 Perform SLAVE RELAY TEST. 92 days SR 3.3.6.6 ZTC "crificaticr. of setpcint is act r; quired. I;rfer; TA00T. RE1RLWid? 13 acaths l SR 3.3.6.7 Perform CHANNEL CALIBRATION. Igmonths M2i? _ .-. e_- - - - p y HAGEBED.EESI 3.3 31 g 0 3.3 55 , f ! CPSES Markup ofNUREG-1431 - ITS 3.3 B 3.3-60 10BOM8

                     .                    . _ .       . -             -           - ~         - .    - _ . .     .   .--   -

1 l i RTS Instrumentation l B 3.3.1

BASES l l to perform maintenance to one of the diverse features g 0 3.3G i MEBOB6--TM alicwabic ti;c for perfer;ing ;;intercrec l f th: divers f::ture: l: : hour; for the r:::aa: : tat:d tmder Condition R. The Completion Time of 48 hours for Required Action U.1 is ; reasonable considering that in this Condition there is one i remaining diverse feature for the affected RTB, and one OPERABLE RTB capable of performing the safety function and given the low probability of an event occurring during this interval. l I h1 tiith two RTS trair:s incperabic, no automatic capability is

                             ;vailabic to shut down the reactor, and i;;cdiate plant shutdow ,                                 )

in accordancc with LCO 2.0.2 is ccquired. l SURVEILLANCE The SRs for each RTS Function are identified by the SRs REQUIREMENTS column of Table 3.3.1-1 for that Functiongig@ESR5M@g. A Note has been added to the SR Table statin 9 that

                                                                          ' - - ' ' ~   - - -     ~"         l03.355     l Table 3.3.113 determines which SRs                                                                ,

Ipfif sti4rj apply to which RTS Functions. omma:mme,VRjffc~atf6rrifs

                              &#BMRea               w           -

Note that each channel of process protection supplies both trains of the RTS. When testing Channel I, Train A and l Train B must be examined. Similarly, Train A and Train B must be examined when testir,g Channel II, Channel III, and

 .                            Channel IV (if applicable). The CHANNEL CALIBRATION and COTS are performed in a manner that is consistent with the assumptions used in analytically calculating the required channel accuracies.

Revicwcr's Notc. Cartain ircqucacies are based on approval tcpical reports. In order for a liccascc to usc thcsc ti;cs, the liccascc ;ust justify the ircqucncies as rcquired by the staff SER for the topical report. SR 3.3.1.1 Performance of the CHANNEL CHECK once every 12 hours ensures that j' gross failure of instrumentation has not occurred. A CHANNEL L CHECK is normally a comparison of the parameter indicated on one j CPSES Markup ofNUREG-1431 Bases -ITS 3.3 .B 3.3-S0 10/3088

ESFAS Instrumentation B 3.3.2 BASES L.1. L.2.1 and L.2.2 Condition L applies to the P 11, P 12 pnttTB4 interlocks. 0-3.3 G 1 With one gg;iggggliguchanne1LQ inoperable, the i operator must verify that the interlock is in the required state for the existing unit conditionggjeerggjpn'Dfjthe permisMWjlgmflikterWINSMR. This action manually accomplishes the function of the interlock. Determination must be made within 1 hour. The 1 hour Completion Time is equal to the time allowed by LCO 3.0.3 to initiate shutdown actions in the event of a complete loss of ESFAS function. If the interlock is not in the required state (or placed in the required state) for the existing unit condition, the unit must be placed in H00E 3 within the next 6 hours and MODE 4 within the following 6 hours. The allowed Completion Times are reasonab1_e, based on operating ; experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. Placing the unit in H0DE 4 removes all requirements for OPERABILITY of these interlocks. - I l SURVEILLANCE The SRs for each ESFAS Function are identified by the SRs REQUIREMENTS column of Table 3.3.21_MJjiR 373:2Z10. ) 1 A Note has been added to the SR Table to clarify that I Table '4 33-1 determines which SRs ptheKth8trM d[MErf-E_7',,;t.ti"f==Manolv to whichTsaa 0-3.3-55 l Functions J C r_ ~ ~ -

                                                              ; acmassTuM6tR128t10tCRd y      e- T            a- -:4ilg***2!B".32LADA Note that each channel of process protection supplies both trains of the ESFAS. When testing channel I, train A and train B must be examined. Similarly, train A and train B must be examined when testing channel II, channel III. and channel IV tif applicable). The CHANNEL CALIBRATION and COTS are performed in a manner that is consistent with the assumptions used in analytically calculating the required channel accuracies.

Rcvia cr*3 ';tc. Certain Trcqucacia: i re bc;cd en ;pproved topical icpert:. In Order for ; licca:cc to u;c thc;c tinc;. the licenscc must ju;tify thc frequcacics es required by the staff SER f;r thc topical report. (cciitinued) ll CPSESMarkup ofNUREG-1431 Bases -3 3 B 3.3-116 10/30/98

ESFAS Instrumentation . B 3.3.2

BASES accident analysis. Response Time r' ^ 'Tvcrification] o.1,1 4

                                              . .w.:. ~ - .- .. 1 acceptance criter in the Technical Raa"4ramants Manual (Ref. 7 0-3.3-55 1

response times are in the analyses. The analyses model the overall or total elapsed time, from the point at which the parameter exceeds the Trip Setpoint value at the sensor, to the point at which the equipment in both trains reaches the required functional state (e.g., pumps at rated discharge pressure, valves in full open or closed position). For channels that include dynamic transfer functions (e.g., lag, lead / lag, rate / lag, etc.), the response time legt_Keay te]i verification Eny be performed with the transfer functions set to en with th; result'.ng resurcd rcsponse ti;;;c cgicd to the appropriate TS." respen:;c tin. lelteractcly, the response ti;;;c test can be pcrfered with the tin constant:; sct to their ac;;;inal valuc provided the rcquired re'ipen';c ti.c is onelytically calculated as u;;;ing the ti;;;c constants are set at their noMnal values. The response time may be N 8sured verified by a series of overlapping tests such that the entire response time is n6 M . T i* E JJJ&h69hmkJnair *&isd am_delJan**EMM JMM 0-3.3-55 l g ,.:_.... . j.2. .- x m 1 =,;.%g.g.E.,3;;, e 9 c. ,a - .. .- . . . f . rul/~,(.,4 i .. 4 ,3 q, 0 1.1 4 f . q .1.y .

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atf6n3fot 6ttuh DFtett2 (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-121 10/3088

L Containment "sc;; ad Exhs;t Vetuat1M Isolation Instrumentation i B 3.3.6 BASES (continued) C.1 and C.2 ; Condition C applies to all Containment 3pnDBal;Wii ." urge ad Exheest Isolation Functions and addresses the train orientation of the SSPS and the master and slave relays for these Functions, j It also addresses the faDure of tgg rultipic radiation i

monitoring channels, or the inability to restore ; single f;iled JW36 channel to OPERABLE status in the time 3 allowed for Required Action A.1. If ; train is inegr;bic, j multipi; chancis er; inegrals, er the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action to place and maintain i containment pr;; ad sh;u: t )3rLti]atiog isolation valves in their closed position is met or the applicable Conditions of 0 3.3 43 3 LCO 3.9.4, " Containment Penetrations," are met for each valve; made inoperable by failure of isolation instrumentation. 6; pote fal]sr2h@orlDrDigtlipgreitere261jef3alWC20TheJohned
1.jscOitith.]la_stgsMggrLt netteteur-UnTurtmmfatgagg i The Completion Time for these Required Actions is Immediately.

l A Note states that Condition C is applicable during CORE j ALTERATIONS and during movement of irradiated fuel assemblies ; I within containment. ! l 4 4 SURVEILLANCE A Note has been added to the SR Table to clarif$ REQUIREMENTS T .6 1 determines which SRs M t Mla ntapapru5 e apply to which Conta'1n n l ru. , .. ~ .un Isolation Functions.

                                                                         .- .~.                  .,

a.3.3 55 l

                                                                                               -azuzn m

SR 3.3.6.1 Performar.ce of the CHANNEL CHECK once every 12 hours ensures that a gross failure of instrumentation has not occurred. A41%NNEb C"ECK is r.erni!y ; s ,,;ri;; of the praetcr irdicated en era chenxi t; ; :i;iler prut;r en other chan;13. It is b;xd-on the nN'.ica th;t in:tr_rr.t chenx1; _.,nitoring th; xn parameteMhould rad ;,,,,caintaly the xx v;1ac. Significent daistim; b; tuna the ta in;tru. cat chsa;is could bc = irdic; tim ;f saxiv; in:trun..". drift in ex ;f the chmaels er ;f nthing n;n ;.ere Krieu;. A CHANNEL CHECK will detect CPSESMarkup efNUREG-H31 Bases -HS3.3 B 3.3-1 H JW30M8

            ..   --              . __ -.            . _ -   ~ - . . -          _ . . . -           -.     - - . _.

l CHANGE NUMBER JUSTIFICATION 3.3 53 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 54 Function 18.b (P-7) of ITS Table 3.3.11 is clarified MatElig i F21M6. COTS and Channel 0 3.3 54 Calibrations apply to the P 10 and P 13 inputs, not to the P-7 logic function. 5:7 :o .w E a ::p.+ m o x x 3-his change is an admi.dstrative clarification to address the relation; ips between these inter 1xks in the plant's design. .. 1.<.u- ;%

                     . f r b.;x r V? l O M :'  Y '                       .:.,R l                    Met +nammerran

! MN099M2 3.3 55 This change revis 'TS E 3.314 and 9 3 3.2.10 to verifyNirc'* response time gt g jth1 G igits Mr@d;gggg@commodating those channels Uun, nave no reyunse Lime reyun emem.s per the current l licensing basis. [As such, line item references to these SRs in l Tables 3.3.1-1 and 3.3.2-1 can be deleted. The current TS do not ' identify which functions have a required response time.] The response time limits and the identification of those functions thet have required response times are currently listed in a licensee 1 controlled document: not in the current TS. This change makes the l ITS consistent with this aspect of the current TS. [A similar 0-3.3 55 revision to the ITS 3.3.6 SR Note hasjalso been made regarding SR. l 3.3.6.8.] 3.3 56 This change revises ITS 3.3.2 Condition J to reflect current TS Table [3.3 2], Action Statement [23a which has been revised and . renumbered as 23f in the CTS markup] for Functional Unit [6.e]. [The required action is to place the channel in trip within 6 hours rather than to restore operability within 48 hours.] CP 3.3 005 3.3-57 ht acd. ConstREE!Rf2lBhSER!idllEMotWilAcDiat2sliBGfddbl l ligERLesMR&MIB3RBMWERkidlM1016BEEEE I 3.3 58 Not applicable to CPSES. See Conversion Corparison Table (Enclosure 6B). 3.3 59 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). l 3.3 60 Consistent with the plant design and current licensing basis. l Surveillance Requirement [ 3.3.2.3 is] not used by any function listed in Table 3.3.21. Therefore, as an administrative change. SR 3.3.2.3 is changed to *Not used." i 3.3 61 This change revises the ITS SR 3.3.2.11 Frequency to [18] months per current TS Table 4.3 2 Functinnal Unit [10.b], which is the DC AU. 001 ESFAS P 4 permissive. The 18 month frequency for the surveillance CPSESDifferencesfrom NUREG-H31 -ITS 3.3 6 10B088 4

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.3 Page 9 of 22 TECH SPEC CHANGE APPLICABILITY NUPSER 1 JIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3 49 ITS SR 3.3.1.8 is revised to extend the conditional COT Yes Yes Yes Yes frequency for power and intermediate range channels from 4 hours after reducing power below P-10 to 12 hours, based on operating experience regarding the time needed to perform the COTS. It stands to reason that if 4 hours are allowed for 2 Source Range COTS. 12 hours should be allowed for 6 Intermediate Range and Power Range COTS. 3.3 50 ITS SR 3.3.1.12 is deleted per the current TS. Where cited No - see CN Yes Yes Yes in Table 3.3.2-1, a change to SR 3.3.1.10 has been made. 3.3-101. 3.3 51 ITS ACTION B.2 of LCO 3.3.7 is deleted. since DCPP cannot Yes No No No operate CRVS with both pressurization systems running at the same time. 3.3-52 Added Note [(1)] to ITS Table 3.3.1-1 per the current TS as No - adopted ISTS Yes Yes Yes an operator aid to note the dual RTS/ESFAS functions of SG format. Water Level Low-Low. 3.3-53 ,The REQUIRED CHANNELS description for Functions 2.a and Yes No No No l J.b.(1). of ITS Table 3.3.2-1. are revised per DCPP CTS to note that only two switches (one per train) exist and that both must be coincident for manual initiation. 3.3 54 Function 18.b (P-7) of ITS Table 3.3.1-1 is clarified M Yes Yes "; G;d !E Yes

v. t. , .. y 3.34

            ..<,...n.
                                        . _.              -- ]. COTS                                           formet- g and Channel Calibrations apply to the P-10 and P-13 inputs.

not to the P 7 logic function. 3.3 55 Revise ITS SR 3.1 1 1A'anri SR 3.3.2 10 to verify C j ;fS"; will LD Yes Y p 6; will b; response times g[ ret;ir.;d ir. !TS l_ g mir;d i- !5 accommodating those channels that have no response time \ T;bl;; for .cyired (T;bic; f; . 4 17-requirements per the current licensing basis. [As such. "- ; tie ;. $ s I Turd i; ;.

          'ine-ites references to these SRs in Tables 3.3.1-1 and                                               '

J.3.2 1 can be deleted. A similar revision to the ITS s' 3.3.6 SR Nate has also been made regarding SR 3.3.6.8.] [ CPSES Conversion Comparison Table -ITS3.3 IW3M98

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-63 APPLICABILITY: DC, CP, WC, CA ! l REQUEST: Revise ITS Table 3.3.2-1 [ Note (g)] per current TS Table [3.3-2] Noto [b]. This revision is a clarification to the operator that describes the circumstances under which the [Steamline Pressure Negative Rate-High function may be blocked when below the] P-11 permissive. l Comment: The wording of the applicability notes (b) and (g) in the ITS is more limiting than the CTS applicability, therefore, the change is more restrictive and should i be documented as such. The CTS notes that the functions must be operable in Mode 3 ' j but may be blocked below the P-11 setpoint. The ITS does not require operability below j the P-11 setpoint in Mode 3. The blocking instruction to the operators belongs in the j Bases, j i l FLOG RESPONSE: NRC deleted the reference to note (g) at the 9/15/98 meeting. ITS Note (b) has been revised to reflect the intent of CTS # note requirements for DCPP, Callaway, and WCGS, and the (a) note requirements for CPSES, as described in new DOC 2-22-A. ITS note j j (b) now states that the Functions are required above P-11 and are required below P-11 unless : I blocked. ITS Note (g) is revised to reflect the CTS ## for DCPP, Callaway, and WCNOC, and (b) note for CPSES, requirements. ITS Note (g) now states that the Function is required below P-11, however, it is blocked below P-11 when Si on Steam Line Pressure-Low is not blocked. In addition to these revisions, the CTS ## note for DCPP Callaway, and WCGS, and (b) note i for CPSES, is revised to move the descriptive information related to the automatic blocking of l these functions to the baas via DOC 2-50-LG. l ATTACHED PAGES: Enci 2 3/4 3-26 Enci3A 17 and 19 Enci 3B 13 and 16 EnctSA 3.3-34 and 3.3-37 EnciSB B 3.3-74, B 3.3-75 'B 3.3-88 and B 3.3-89 l l i 4

TABLE 3.3 2 (Continued) TABLE NOTATIONS Trip function may be blocked in this MODE below the P 11 (Pressurizer 2 22 A Pressure Interlock) Setpoint. 2-50 LG 6 en ;uts.T.ctically bloded eb;;g I' 11 be unblocked below F 11 oy DiocKing use aaiety ATIJet,i,iun un ivw steam line pressure. _

Not applicable if each affected main steam isolation valve and its N associated upstream drain pot isolation valve per steam line is closed Ms.ift 1 andjdeactivated. 0207 d

y , 7hg 3.jj3jg33 gf e gjfjgggjgg 4,n.4 erc st a licable for P2'-09 LGt!] cntry int; O E 3.

The channel which provides a steam generator water level control signal (if one of three specific trip channels is selected to provide input into 2 52 A steam generator water level control) must be placed in the tripped 0 3.3 65 condition within 6 hours and maintained in the tripped condition with the exception that the channel may be taken out of the tripped condition for up to 4 nours to allow testing of redundant channels.

Not applicable if Preferred Offsite Source Breaker is open. , 02-11~A-R1 i 8 Notlappl icablCWheRallinain';feedwaterlisol ation3nd: bypass ~ valves ?are clqsediand,;deactivatedjpriglatelbgelosed,magalval ve; F207WLS$ j 1 l ACTION STATEMENTS ACTION 12 - Deleted, j l ! ACTION 13 - Deleted. I l l 1 l l l l l i i l CPSESMarkup ofCTS 3N.3 3N 3-26 103088

1 l 1 l i CHANGE ffEBIB NSHC DESCRIPTION 1 2 20 A The Functional Unit for Containment Vent Isolation is moved to ITS 3.3.6. There are no technical differences introduced by this process. 2 21 LS 22 In current TS Table 3.3 2 , Action 17.1 replaces Action 17 for RWST Level Low Low. Action 17.1 allows a channel to be placed in bypass for testing, which is less restrictive than placing the channel in the tripped posit Mn as i required by the current TS. 2-22 A Not L'=d. }he!CW[ajhofgable2[322Lis y 0 3.3 63 t_achnicallregti1Valentato;IJWp6te3br,7ab]e1312-T. I j J l 2-23 A Not applicable to CPSES. See Conversion Comparison Table l (Enclosure 38). l 2 24 LS 19 The Required Action for an inoperable SI sequencer is revised per ITS 3.8.1 Condition F to extend the time i available for restoration of an inoperable SI sequencer from 6 hours to 12 hours. 2-25 A Thc icquircx .t for =nal actuation of ; singic ni a-2 25 stx; isolation valvc is not = ELF faction, bt is ; safety function for the SC'll cvcat and has kcn ;;ved fr;; current TS T;bic [3.3 2]. censistent with NUl1EC 1431 Rcv.1. The ESI fantien requi.c3 isolation of all intact .

                                      ;ta; 1i           3. =t individ=1 li x s. OPEIXILI"I Of individual lixs is anssed undcr ITS LC0 3.7.2 with the Ogletien Tix a dinusxd in the 3/4.7 pxkagc. N_o1; M

( 2 26 LS 21 The Required Action for an inoperable Control Room 0226 I i [ Emergency Recirculation] [ Manual Initiation, or SSPS] channel is modified to g provide appropr Ac =tions with the axbcr of OPEPX,LE chenacis [tw;] 1:33 then the aski of Rcquircd Oknxis, consistent with NUREG 1431 Rev.1. EnigMf 3 Mggemate ! BestsEtxtatecamssessmagstammartele1 ant _

                                        ?           Op.@?RESEtIRGElWREREBfftMttpWWem

! [ERNRCR2ecirttilat10GDBWB]Rn139tWfEpriSSPS3 BGEFghMg3 Depending on the initial mode of ! E operation, the modified action requires either: l } 1) [CREFS] to be placed in its [ emergency recirculation mode (one train) and the other train declared

<                                                    inoperable and the Required Action for an inoperable                ,

I CPSES Description of Changes to CTS 3/4.3 17 JMM8

   ._-             .    -     .    . -.               .      .                   ~            -                .-

CHANGE NUMBER !EC DESCRIPTION 2 39 LG Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2 40 A This administrative change affects tne .aanner in which the current TS 4.0.4 exception for testing the TDAFW pump is presented. This exception allows entry into MODE 3 to perform the turbine driven auxiliary feedwater pump response time testing. In NUREG 1431. Rev.1, the current TS 4.0.4 exception from [ Table 3.3-2, Notation d and Section 4.7.1.2.b.2)] is reflected in the ITS SR 3.3.2.10 notes. 2 41 EG-36 NotusedicppliccbictoC"_SCS. _.. _ en, Sec Conversion CA 3.3 009 e o . y Z. T. .Z._ .e .t,. s_ ..m

                                                        . _.            re _ _3.   . . . ..,.

2 42 bG-38 NotJ- osed.'_cppliccbic to C"SCS. re__,_.. _ nos Scc Conversion CA-3.3-002 e . r. 1. .Z... . ,. .t..e

                                        .                          , _ ..~...s              ..,.                                     ,

2-43 LG Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2-44 A Not applicable to CPSES. See Conversion Comparison iable (Enclosure 38). 2 45 LG Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 2 46 LS 42 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38). 2-47 H The ESFAS Tables of the current TS do not include the Aui.omatic Actuation Logic and Actuation Relays for the Control Room Emergency Recirculation Functional Unit. They were not included because they are simple, direct-acting, and are tested as part of other ESFAS or CREFS testing. This function is added to be consistent with ITS 3.3.7. 2-48 LS-28 Not applicable to CPSES. See Conversion Comparison Table i (Enclosure 3B).

            !?AR                         HQ D Lsed
                                      ~                                                                                "'

m gj)0, l.G ane mo:JM(WtEgGsD]e:13;Eg]li438t1961toisoW 0 3.3-63 l N f.B M S S $41 g glangt m j e

lentanalnGagustgasmso amannuaissees?)

Batut nitJIM apete !, ^ CPSESDescription ofChanges to CTS 3N.3 19 103088

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 13 cf 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY CANYON PEAK 2-20 The Functional Unit for Containment Vent Isolation is moved to ITS 3.3.6. There Yes Yes No - see CN No see A are no technical differences introduced by this process. 2-05-M. CN 2-05-M. 2 21 In CPSES current TS Table 3.3-2. Action 17.1 replaces Action 17 for RWST Level No Yes No No LS 22 Low-Low and Action 17.2 replaces Action 17 for SG Water Level - High High. 6 Urd Lhefl3 (a]inote;9f2TablelfalhAhlsitectnica))y. equivalent 3tof!TS N/ Ayes N/ Ayes */ Ayes N/A 2-22 j 2 o-3.3.t3E> eng MtWb)?ilablefM3;241g Yes 2-23 This change revises ACTIONS [14, 27, 27a, 34, and 34a] in current TS Table 3.3-3 No - already in No - already Yes Yes A to clarify that the 12 hour A0T to get to MODE 3 includes 6 hours for current TS. in current Ts. restoration followed by a 6 hour shutdown to MODE 3. 2 24 At CPSES, the Required Action for an inoperable SI sequencer is revised per No Yes No No LS-19 ITS 3.8.1 Condition F to extend the time available for restoration of an inoperable SI sequencer from 6 hours to 12 hours. E o 2 2-i l A _.. IN'N.. - ~$ .5 3 352II toI.

                 --               . . , m   ._m y,". .. - IoNU.
                                                                ~ . !55._ .. 3 N... ,..I.~ !. ..
                                                                          .    .                  GTSr M                                               see-GN e5x;xd ur.ir T LEO 3..2.           NotNsed                                                                                                2                                                                                                                                                         ES                                                                                                                                                         M 2 26     The Required Action for an inoperable Control Room [ Emergency Recirculation]          No - not in     Yes                   Yes            Yes LS-21    [ Manual Initiation on SSPS] channel is modified to provide appropriate actions        current TS.

wi-:1 the ntster of OPERABLE channels [tm] less than the number of Required Channels. 2 27 The CPSES Action Statement for the loss of offsite power - start motor driven No Yes No No A auxiliary feedwater pumps is modified to require that if the Action Statements are not satisfied, the plant t,e taken to MODE 4 to exit the LCO Applicability. The CTS requires that MODE 5 be entered; however, because the function is only applicable $n MODES 1, 2. and 3. the LCO would be exited prior to MODE 5, and MODE 5 entry is not a requirement. 2-28 This change moves DCPP information inserted by LA 114/115 on contairment spray fes No No No LG and safety injection coincidence to the Bases. CPSES Conversion Comparison Table - CTS 3M.3 10/3038

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 16 cf 22 TECH SPEC CHANGE APPLICABILITY DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER CANYON PEAK Callaway's Operability requirements associated with the shutdown portion of one No No No Yes 2 43 LG sequencer required to be OPERABLE in NODES 5 and 6 and which corresponds to the required DG, are moved to ITS 3.8.2 with the explicit link found in the ITS 3.B.2 LCO Bases. 2 44 Current Action Statement 32 of TS Table 3.3-3 for Functional Unit 32. RWST Level No - not in No - not in No - not in Yes A Low-Low Coincident with Safety Injection, is revised to delete the last current TS. current TS. current TS. paragrsph that states a channel may be tripped for up to 4 hours for i surveillance testing to reflect the practical application of this allowance. 2-45 Current TS Table 4.^ :ste (3) is revised to move the -during refueling" No - not in No - not in Yes Yes LG clarification c! se 18 month surveillance interval for the seven slave relays current TS. current TS. to the Bases for ITS SR 3.3.2.6. SR 3.3.6.5 and SR 3.3.7.5. 2-46 Relaxations associated with Separate Condition entry for the RCP-Undervoltage. No - not in No - already Yes Yes LS-42 RCP-Underfrequency, and Auxiliary Feedwater - Trip of all Nain Feedwater Pumps current TS. in current TS. Functions are justified. 2 47 - This change adds the Automatic Actuation Logic and Actuation Relays function to No - see CN 3- Yes No - already No - already in - N the ESFAS Functional Unit for (Control Room Emergency Recirculation]. 08 N. in current current TS. TS. 2-48 A new Action 15 is added and applied to Functional Units 7.a.2) and 7.b.1) that Yes No - se" No - see No - see LS 28 allows the affected Emergency Diesel Generater to be declared inoperable and CN 2-32-LS-23. CN 2-18 LS- CN 2-18 LS-31. requires entry into Specification 3.8.1.1 when more than one relay per bus is 31. inoperable. Current Action 16 of the DCPP TS does not address the above situation and requires entry into LCO 3.0.3. W IMLmsed m m m _m _ yn hHi IlunCIsabEmtexcisTableinAghiniDLgdse$tptytttheidesedptlyeyatettal taletsetoitbegautomatiethlhofitthesineclockato;the11TSDJ12LBasest yes Yes yes I 0-3 3-6' k - M M Mtenento%PSE32GT5LTableGE19,"fepplied;1ethEIufbiWUdihandifegqwetet Noi Yes M M Dol.ptionLEunct1Malttin11Mt.mts1refigsted;dn.gTSITable);3i2115Functichel l0-3.3-65 l 8 Mttr#DEfeopM4pH M M CPSES Conversion Comparison Table - CTS 3N.3 10/3088

1 1 1 i ESFAS Instrumentation 1 3.3.2 Table 3.3.21 (page 1 of 10) Engineered Safety Feature Actuation System Instrumentation APPLICABLE i I MODES OR OTHER y SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE y FUNCTION CONDITIONS CHANNELS COM)lTIONS REQUIREENTS VALUEW

1. Safety Injection

a. Manual Initiation 1.2.3.4 2 B SR 3.3.2.8 NA E

b. Automatic 1.2.3.4 2 trains C SR 3.3.2.2 NA M Actuation Logic SR 3.3.2.4 ,

and Actuation SR 3.3.2.6 i Relays I

c. Contairment 1.2.3 3 D SR 3.3.2.1 R3.8'psig . 3.5 pi; g g.p3 yj Pressure - High 1 SR 3.3.;. B-66 SR 3.3.2.

                                                                                                                                                = :.:.:.10                                                                    +3.3 55M

d. Pressurizer 1.2.3* 3$ D SR 3.3.2.1 (1803.6 i L"50 pi; g gipsgij Pressure - Low SR 3.3.2.5 psig SR 3.3.2.9 1939 N323-551 en,

                                                                                                                                                 -     .,. ,. .e . e. n.

e. Steam Line 1.2.35 3 per SR 3.3.2.1 635 e475 Pressure steam SR 3.3..'.5 (593.5 ps41 f*' s B-PS40 line D SR 3.3.2.9 psig fi+ Low "" 3. . .10 .( Unit:4 W3:3-5511 7578.4 psig*

                                                                                                                                                                                    @llL2)

W -Htgh idr3 3-pee B [5" .3.2.1: . [105' pi; s 4 971 F3cS?01$ aiu ati;1 eteem " . . . pe+s Pressure 44ne C" . . .",a e ___ , , , n,,__.___.. en, E4nes

                  ,"ig 'e _._St:            .    = Fl =__ '-

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B-per B " 2.2.2.1 cn, , , , e, fe+ M gg

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44ne en,

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                                                                                                                                                         , , , ,n en. ye,....v (continued)

(a) Rev4scr' 'etc. L'n't ,,,.;1'i; i;pi;nnt;ti;; ny ..t:1. ;;ly ".lis-ti; ';; = 0;p.-# ; en 0;tFi t I Study att d.';;; nd by 15.; ="t J!tGI]citt9pNjpg'gfgyAstes;tettisti liiii 3Dm"8M4ECfsiC'thCidK8stpMotU (b) Above the P 11 (Pressurizer Pressure) interlockhbetterM250.luggss:D)ockejd 3.3 63 , (c) Time constants used in the lead / lag controller are ti a 31 semm am t, s 3 seconds. 0 3.3 63 1

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CPSESMarkup ofNUREG-1431 - ITS3.3 . 3.3-34 10B0M8

ESFAS Instrumentation 1 1 3.3.2 Table 3.3.2 1 (page 4 of 10) Engineered Safety Feature Actuation System Instrument: tion APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE N FUNCTION COICITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE"3 1 1

4. Steam Line Isolation l (continued)

b. Automatic Actuation 1.2"' . 3"' 2 trains G SR 3.3.2.2 NA in Logic and Actuation SR 3.3.2.4 Relays SR 3.3.2.6 J l

c. Containment 1. 2"' . 3"' 43 D SR 3.3.2.1 R6'.8.psig s-4-M n g.p3 g l Pressure - High 2 SR 3.3.2.5 fn41 pe4g j SR 3.3.2.9 13.3-55~ 1 !

c :.:.c.10 i I i

d. Steam Line Pressure 1.2 "'. 3 per D SR 3.3.2.1 6M e-6M l (1) Low 3*'"' steam SR 3.3.2.5 $J93;5 ps4*f. p B-PS74 1 line SR 3.3.2.9 psfg'O 5" .2.2.14 ruuttD g;3,3 554 kien 4 -

i W f' .l

(UgjtjM ; 1 l (2) Negative 34"" 3 per D SR 3.3.2.1 s 'H8;f"3 4 gug.P5WI I Rate - High steam SR 3.3.2.5 psi ps%es" I line SR 3.3.2.9 101-6 53134555 l C 3.3.2.10 ptWee

     ;. 'igh 5ts; "1;.c '- Tw:     4,2*,-3"          2-per          B         5".3.2.2.1         fe)       H+          $3;3 01;g St a; Lin;;                                 steen                   SiHHhers Mme                     5" 3.3.0 ^

SlHi-Sn' hie C;incii...t .;it5 4,2*r 4-pee B C" 3.2.2.1 a [550.5;*" 2 :::::"" T,,, --- L;w Lc.; 3** 4eep 5" 3.0.2.5 2 2.3.2." 0" 2.2.2.10 (continued) (a) 0;.ic.;;r'; ";tc. 'Jn't ;g;i'i; i 9 1 -...; tim; ny _.t;i =1; "l;;;bi; '.';?;; 4..J:n; = 0;tgint Study ;;th;d;l;;; and by th; un't ge3Hgggg]GCpe[1n, PfjjGisittM4MDysgo

          $tttjig MC,thi;BasesEthi;IdiCMtisiUbtM (b) Above the P-11 (Pressurizer Pressure) Interlock                oE NJOsg M ]Eg                                      3 (c) Time constants used in the lead / lag controller are i a    t H seconds and t, s 5 seconds.                                      ,

(g Below the P 11 (Pressurizer Pressure) InterlockM)eJJpqkig!Je]aErJ3te!Cgttty e ) jglpgjorEt3sf$ team 3,gDr_essggDer1rget~ttl CP 3.3 ED (h) Time constant utilized in the rate / lag controller is s seconds. (1) Except when all MSIVs'engthe1CDssRCMcDpatt1HsCRjptstCggolat1MAlVM are closedy.4 ; RNRSMRQ< { R3353

   . C?SE.S Markup ofNUREG-1431 - ITS 3.3                   ,3.3-37                                         10/30/98

ESFAS Instrumentation B 3.3.2 BASES APPLICABLE d. Safety Iniection-Pressurizer Pressure - Low SAFETY ANALYSES, (continued) LCO, and APPLICABILITY This Function must be OPERABLE in H0 DES 1. 2, and 3 N *3 I (above P 1pcW P-312p3]gEblockec) to mitigate the consequences of an iELG inside containment. This signal may be manually blocked by the operator below the P 11 setpoint. Automatic SI actuation below this pressure setpoint is then performed by the Containment Pressure-High 1 signal. This Function is not required to be OPERABLE in H0DE 3 below the P 11 setpoint. Other ESF functions are used to detect accident conditions and actuate the ESF systems in this MODE. In H0 DES 4, 5, and 6. this Function is not needed for accident detection and mitigation.

e. Safety Iniection-Steam Line Pressure Mt Steam Line Pressure-Low Steam Line Pressure-Low provides protection against the following accidents:

                                  . SLB:
                                  . Feed line break; and
                                  .      Inadvertent opening of an SG relief or an SG safety valve.

Steam Line Pressure-Low provides no input to any control functions. Thus, three OPERABLE channels on each steam line are sufficient to satisfy the protective requirements with a two out of three logic on each steam line. (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-74 10/3088

l l l ESFAS Instrumentation B 3.3.2 BASES APPLICABLE fB Steam Line Pressure-Low (continued) SAFETY ANALYSES, LCO, and With the transmitters typically located APPLICABILITY inside the steam tunnels, it is possible for them to experience adverse environmental conditions during a seccadary side break. Therefore, the Trip Setpoint reflects both steady state and adverse environmental instrument uncertainties. This Function is anticipatory in nature and has a typical lead / lag ratio of 50/5. Steam Line Pressure-Low must be OPERABLE in 0 3.3 63 H0 DES 1. 2. and 3 (above P 11 difiithelcrPF11% dihTess7blockg5 when a secondary side break or stuck open valve could result in the rapid depressurization of the steam lines. This signal may be manually blocked by the operator below the P-11 setpoint. Below P-11 feed line break is not a'- l concern. Inside containment SLB will be terminated by l automatic SI actuation via Containment Pressure-High 1 and outside containment SLB will be j terminated by the Steam Line Pressure-Negative Rate-High signal for steam line isolation. This Function is not required to be OPERABLE in MODE 4, 5, or 6 because there is insufficient energy in the secondary side of the unit to-eetex = =cidat. bit 6f i Elncegl l (O Stc= Line Prc::urc "ich Diff'r=tial Prc ure Scrac= Stc= Linc St;= Linc Pic33urc "igh Differintial Irc33urc l j Scra=r. Stc = Lines providc; pictcction : gainst the fcih;in; xcidat;; ! = SLB; ', ; Tccd line brcok; cad ' (continued) CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 B 3.3-75 10B088

i I ESFAS Instrumentation B 3.3.2 BASES l

d. Steam Line Isolation-Steam Line Pressure l

0) Steam Line Pressure-Low Steam Line Pressure-Low provides closure of the HSIVs in the event of an SLB to maintain at least one infaulted SG as a heat sink for the reactor, and to

                            ' limit the mass and energy release to containment.

This Function provides closure of the MSIVs in the event of a feed line break to ensure a supply of steam for the turbine driven AFW pump. Steam Line Pressure-Low was discussed previously under SI Function 1.e.l. Steam Line Pressure-Low Function must be OPERABLE in MODES 1, 2, and 3 (above P 11) with any main steam valve open, when a secondary side break or stuck open valve could result in the rapid depressurization of the steam lines. This signal may be manually i h1nckad by the operator below the P 11 setpoint.- ) IfjMJbelowA11j ghe funcjt on aus1[hyl 0-3.343 l , manyggah a "7wblodrid./En insTae containment SLB will be terminated by automatic actuation via Containment Pressure-High 2. Stuck valve transients and outside containment SLBs will be terminated by the Steam Line Pressure-Negative Rate-High signal for Steam Line Isolation ! (1) Steam Line Pressure-Low (continued) below P-11 when SI has been manually blocked. The Steam Line Isolation Function is required in . H0 DES 2 and 3 unless all MSIVs are closed grLd 0 3.3 G 1 l RECIMRigl. This function is not required to be l OPERABLE in MODES 4, 5, and 6 because there is l l insufficient energy in the secondary side of the unit l to have er, acciir.t. ggfMr1 i (2) Steam Line Pressure-Necative Rate-Hiah Steam Line Pressure-Negative Rate-High provides closure of the HSIVs for an SLB when less than the P 11 setpoint to maintain at least one unfaulted SG as (continued) CPSESMarkup ofNUREG-H31 Bases -3.3 . B JJ-88 10/3088

1 ESFAS Instrumentation B 3.3.2 BASES heat sink for the reactor, and to limit the mass and energy release to containment. When the operator manually blocks the Steam Line Pressure-Low main steam i isolation signal when less than the P 11 setpoint, the ' Steam Line Pressure-Negative Rate-High signal is ; automatically enabled. Steam Line Pressure-Negative I Rcte-High provides no input to any control functions. l Thus, three OPERABLE channels g0gegl(steesThat are ! sufficient to satisfy requirements with a ' two out of three logic -- -- ' "- 1 Steam Line Pressure-Necative Rata Mich must be 0 3 3-63 I OPERABl_F in MODE 3 when/hSteepljneJIessjM mummmmmmme i y ll( bcW @ JockedINic;- then the P 11 en a secondary side break or stuck open i valve could result in the rapid depressurization of the steam line(s). In MODES 1 and 2, and in MODE 3, when above the P 11 setpoint, this signal is automatically disabled and the Steam Line Pressure-Low signil is automatically enabled. The Steam Line Isolation Function is required to be OPERABLE in MODES 2 and 3 unless all MSIVs are closed aideactMated. In MODES 4, 5, and 6, there is insufficient energy in the primary and secondary sides to have an SLB or other accident that would result in a release of significant enough quantities of energy to cause a3}gnJffganj cooldown of the RCS. While the transmitters may experience elevated ambient temperatures due to an SLB, the trip function is based on rate of change, not the absolute accuracy of the indicated steam pressure. Therefore, the Trip Setpoint reflects only steady state instrument uncertainties. c, f. Ste= Line Iscistion !!ich Stc= Tiew in Two Stc= i 4. _.. r.- 4. m.

                                                                                                         .                    1
                                     -.         . . . .     ... mm. . . r. _._ ._-.._.__<.2,__u.-_m.
                                                                                        .. , , -      . .u. u. .

St:= Line Trc;;urc Low 'Thic: =d Tour Lec., Unit;' ! R,cac fi.nctions (4.c end 4.f) provide cle ure of the ",SIVs during en SLS er indvertcat ep;ning of :n 50 relicf or ; afety velve, to =intain et ice-t ene unf;ulted 00 e; ; bcet sink for the raector and t; li;;;it th; =33 end incrgy rcice c j to centeira nt. l (continued)

CPSES Markup ofNUREG-H31 Bases - ITS 3.3 B 3.3-89 1030A8

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-65 APPLICABILITY: CP REQUEST: A note is added to the steam generator water level - high-high trip function to reflect the CPSES design and current TS. In the CPSES design, only three channels of the four steam generator water level signals provide input to this trip function. Therefore, in order to satisfy the single failure criterion, if s?e of these three channels is used as input to the steam generator water level control system, its associated bistable must be placed in the tripped state. Comment: Revise Action I or delete proposed footnote p depending on the instrument loop design. If using an operable channel in the control circuitry renders the channel inoperable (not capable of performing its intended isolation function, then delete the footnote because ITS Action I provides the appropriate remedial actions. In this case a Bases notation can be made to direct current compliance with TS. If on the other hand the channel should be declared inoperable and the ITS Action I does not provide the appropriate actions, then propose new ITS cctions. Also, justify the plant specific nature of the CPSES design that results in this TS dilemma, FLOG RESPONSE: As agreed upon at the " September meeting," footnote (p) is revised to read "A channel selected for use as input to the SG water level controller must be declared inoperable." Once the channelis declared inoperable, Condition I would be entered. This change remains consistent with the CTS. . ATTACHED PAGES: Enct2 3/4 3-26 Enci 3A 19a Enci38 16 f EnciSA 3.3-39 Enci5B B 3.3-94 l Encl 6A 7 ! i i t 1

l l J l TABLE 3.3-2 (Continued) l TABLE NOTATIONS l Trip function may be blocked in this H0DE below the P 11 (Pressurizer 2 22 A Pressure Interlock) Setpoint. 2 50 LG

Trip function eutc;; tic;11y block;d abov " 11 :nd may be unblocked ,

below P 11 by blocking the Safety Injection on low steam line pressure. '

Not applicable if each affected main steam isolation valve and its E-67-L4 associated upstream drain pot isolation valve per steam line is closed 218181 0- 07 MdideM1 vat!!q.

1 d 7 gj3j;,; gf e- ;jfjgggj;- 4,n,4 3 g ;g 3 ]jggh]g fgp gg;09M3 m...., ...~..m , , . The channel which provides a steam generator water level control signal (if one of three specific trip channels is selected to provide input into 2-52 lI A , steam generator water level control) must be placed in the tripped Q 3 3 65 j condition within 6 hours and maintained in the tripped condition with the k exception that the channel may be taken out of the tripped condition for V up to 4 hours to allow testing of redundant channels. , i Not applicable if Preferred Offsite Source Breaker is open. . F2 H W ; i

       '        tiotlapplicabletsn7IDInsinfeedwaterifsolatiosneypasrvalves rare close(and:deactsvatedmrisolated;b     ed   g elosediaangar g lye;                  12 07:-rs3 ACTION STATEMENTS I

ACTION 12 - Deleted. ! ACTION 13 - Deleted. s CPSESMarkup ofCTS 3N.3 3M 3-26 1020n3

CHANGE NUMBER NSHC DESCRIPTION g , c. ,- . , 5. , . - . . . n ,. .g s - 4 .n y .gr .a . . . . . m

r. , ' s . * *. Y 1 y. . s . .

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                                     ; y n ; = ; ;. b . _.;.,a                .
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                                   -etausmaammentwateryggine f-,   c b i             p .. a :- t. 4.. 5PJ : .9-l w M. A u DMjMf]

MMlegt!!EIRithDWHfv2t2NRetBERL13ttifeflit!!t3na:1geC; tactTrain1nwngttemetsMallefwictimeDreamvalerrt f RERJLR#2thW.31!EIDeM2TGerS3GRiligill!@ tim!! c_t!aggje g@ M siggpp1Kabli;tolCPSESMSee3geltetsfon?tomparison2 Table IliMMDd3!OR 2-35A M LipDepl1Cjibje36TCPSES*SSed: Conversion:,CompatisonlTable iliE2elat!!E4BE 2155 M Ng8MMMM. nh7,DieWWf2ifatstillDSteauCHth" 0207 633EZN# ERIT!T4 1EEpta!sttrp4testat3hr.UiEtacRDaBIRGERQs3 6 74 W N 21B Wt!"#nd entstmentausgsmessoamanes',mamasaamamentatte annenHnam11erwarnessawwnundmimmastamamsunauernianziemes a !

                                   .                                                                                     *NSEFRdVI                 l B

ggg LSig ,tswrable n 9. ; ,; .q

                                       ;,                                                                             . 9i p.ff . ;,,e J.

g ,e .97L . ( } y .? .-,. 3.:*7 y.f q. f ' . g' a.i, v i: [. h . .; 3 . g 8 Nelsestestahbr CTahid HElllER M B 3 01 A The requirements of this current TS [3.3.3.1] are moved to [three] separate specifications in the improved TS. The RCS Leakage Detection requirements are moved to improved TS 3.4.15. [ ] The Control Room requirements are moved to improved TS 3.3.7. [The Containment Ventilation requirements are moved to improved TS 3.3.6.] CPSES Description of Changes to CTS 3N.3 19e 1020M8

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 16 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER' DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY CANYON PEAK Callaway's Operability requirements associated with the shutdown portion of one No No No Yes 2-43 LG sequera:er required to be OPERABLE in NODES 5 and 6 and which corresponds to the required DG. are moved to ITS 3.8.2 with the explicit link found in the ITS 3.8.2 LCO Bases. 2-44 Current Action Statement 32 of TS Table 3.3-3 for Functional Unit 32. RWST Level No - not in No - not in No - not in Yes A - Low-Low Coincident with Safety Injection. is revised to delete the last current TS. current TS. current TS. paragraph that states a channel may be tripped for up to 4 hours for surveillance testing to reflect the practical application of this allowance. 2-45 Current TS Table 4.3-2 Note (3) is revised to move the "during refueling

No - not in No - not in Yes Yes LG clarification of the 18 month surveillance interval for the seven slave relays current TS. current TS.

to the Bases for ITS SR 3.3.2.6. SR 3.3.6.5. and SR 3.3.7.5. 2-46 Relaxations associated with Separate Condition entry for the RCP Undervoltage. No - not in No - already Yes Yes LS-42 RCP-Underfrequency, and Auxiliary Feedwater - Trip of all Nain Feedwater Pteps current TS. in current TS. Functions are justified. 2 47 This change adds the Automatic Actuation Logic and Actuation Relays Function to No - see CN 3- Yes No - already No - already in N the ESFAS Functional Unit for [ Control Room Emergency Recirculation]. 08-N. in current current TS. TS. 2 48 A new Action 15 is added and applied to Functional Units 7.a.2) and 7.b.1) that Yes No - see No - see No - see LS-28 allows the affected Emergency Diesel Generator to be declared inoperable and CN 2 32-LS-23. CN 2-18 LS- CN 2-18-LS-31. requires entry into Specification 3.8.1.1 when more than one relay per bus is 31. inoperable. Current Action 16 of the DCPP TS does not address the above situation and requires entry into LCO 3.0.3. RjR Must4 M M M M Edq TlwiCik[b]ifioppfofjTablefDfS12}$lSWeV1Mditetsomthe desctiptive;matettal les Tes les M l Q-3.3-6' ll C ntiatedatoithetsutomatictblockimettthmurit4!ggekttoltMdIEhagsasesi - ifM Lheahanneladetaftfft@fM4Alfe!ntsnapvoq1toltheII.IE sasesifor21.TS;p.h 61 yes No M M l Q-3.3-6 r C ,-

                                                                                                                             .- ~                            1 f                                                                                                        yes BW      legegego mrggaspanipf1tettantianumLnelTriplandIFgahnstet                         Noj                           M              l10 Do3atjot!!functionsKumtg5LbRtssteflecteenmITs2 Tele 1313iU1;1Juncetonal
                                                                                                                                              - Q-3.3 6'- l   '

8 IRLt&bg8fLx3talaEm s CPSES Conversion Comparison Table - CTS 3N.3 10B088

i l ESFAS Instrumentation 3.3.2 Table 3.3.21 (page 6 of 10) l Engineered Safety Feature Actuation System Instrumentation 1 APPLICABLE MODES OR OTHER Mie SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION COWITIONS CHANNELS COWITIONS REQUIREENTS VALUEM

i Ot; ; Li = n kti m

             . . . . . . . . .,_a, h "i f. "i t. Ot;= F1;.;                 44*v-3*                  iHMee               9              0" 2.2.2.1            ; l100': ;f                s-{-t ef steen                              64-3ra+s               f;1' ;ta;                --fe1+

Mme 0" 2.2.2.0 'i;.; ;t ful' e*een CM01d 4 0" 2.2.2.10 ind ;ts; M pressure fui' ind ! steen Pre *S"Pe 4 O i xi i... it'. O f;ty "ef;r t; T;ncti= 1 ' f;ty Inj utien' fr ;1' ' 'ti; tion f;;ti a; N3.360111 l

njuth; =d r;;;i..a..t; )

1 a

5. Turbine Trip and Feedwater Isolation .

I

a. Automatic Actuation 1.2(3) . 2 trains H EG} SR 3.3.2.2 NA NA ggg g g l Logic and Actuation E33* SR 3.3.2.4

. Relays SR 3.3.2.6 . b. SG Water 1,24J'. 3 per I E9} SR 3.3.2.1 84-24 m g ] i Level - High High 9}* SG* SR 3.3.2.5 K3Qt (P-14) SR 3.3.2.9 M.Daf'3.991 0" 2.2.2.10 3 00 0 3.3d GEN mammmuy WM M

c. SafetyInjection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

i d (continued) 1 (a) ";;i; r'; 5t;. W it 6 ;ifi; i;;l - ...;ti;= n y _ .t;i. enly I' h .tk W h; i,~.d.ns ; 2 ;r.idRig

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3.3 65 Q.3.3 65 [ L _ J 3.3-39 10B0M8

    ^ CPSESMarkup ofNUREG-1431- ITS 3.3                                                                                                                  ,

I ESFAS Instrumentation B 3.3.2 ! BASES j the AFW System is automatically started. The SI signal was

 !                               previously discussed.

I a. Turbine Trio and Feedwater Isolation- Automatic ,

8C_tuation Loaic and Actuation Relavs !

Automatic Actuation Logic and Actuation Relays consist of l the same features and operate in the same manner as described for ESFAS Function 1.b. l i b. Turbine Trio and Feedwater Isolation-Steam , Generator Water Level-Hiah Hiah (P-14) h i This signal provides protection against excessive feedwater i flow. The ESFAS SG water level instruments provide input to the SG Water Level Control SystemEdhBBK'.EC4BBilrW8E,1iG WateGAMUilglMlgLNBgE2iiMBtR3 fen ' Thcr;for , th; att __A...u._ ,__2_ _ . . . . L_ _L,_ A_ .2m_i__; L_u __ 2__..A Uw buu b IVi s IwyIw nau d b ww uwaw bv W 4 ks ad bus r%s uv ks a uss e i s ywe. s . 21. . _ _ L. AL_ _ _ _ A _ _1 ..._h__ /. .L J _L __m AL__ ___..J__ AL. s u i s us b bv busw vvy a bs v s dJ d bwsu g wi a s ws a usuJ bu sus a a wqu u a w bgsw pret;; tion function ;;tuation) and ; :ingic f;ilur; in th; oth r chersacis providir.g th; pret ; tier, function ;;tuation.

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1 0 3.3 65 l 1 (continued) i j CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3-94 10/3088

CHANGE EtEER JUSTIFICATION 3.3-63 This change revises ITS Table 3.3.2-1 [ Note (g)] per current TS Table [3.3 2] Note [b]. This revision is a clarification to the operator that describes the circumstances under which the [Steamline Pressure ' Negative Rate - High function may be blocked when below the] P 11 permissive. 3.3 64 This change revises ITS Table 3.3.21 Note (j) to exclude the MFRVs. consistent with current TS [ 3.7.1.6]. [The note defining the applicability is also revised to add an alternate method of main feedwater isolation, if available. The use of close manual valves serves the same safety function as a closed and deactivated valve.] 0 2-07 ! When31DLSIVsRandtthefr_w3frWpo_t.,3llola_t10!!"ValvesT1nd LfEIVs3fEclodydjDindldeaj:tWatfd}Kth6Iin.Matjonflequired;to inttjatethe:clo_ state;ofthesge alvesgetvesypurposondistherefore; 1not7equireditolbOpernble] 1

3.3 65 A note is added to the steam generator water level high high trip ! function to reflect the CPSES design and current TS. In the CPSES l design, only three channels of the four steam generator water level l signals provide input to this trip function. Therefore. in order to I satisfy the single failure criterion, if one of these three channels

1 is used as input to the Steam Generator Water Level Control Syst ! its associated bistable must be olaced in the tripped state / _q I _heMBilifLreguirement3ElgiplTWhEthr Lugh;footnotel(pT;to ')3365 T.able3.gt211Hhigh3ggdXgE&tlgT&tf.tcted3tiannellto3e_31gelated inoperJ!ble223hGstiM3M83BMBGond1ER!ELguld3heEM entfreERELimesentat:foistaateltstMgheltortentmi

                          ~1teWRs2                                                                     i N                                                                            1 3.3 66        Not applicable to CPSES. See Conversion Comparison Table                          j (Enclosure 68).

3.3 67 This change adds in PAHS, CPSES specific operability requirements and Required Actions for the T hot and T cold indications consistent with both the current licensing basis and the intent of NUREG 1431. If a T hot indication is unavailable, equivalent information is available from the Core Exit Temperature indication which is also a RG 1.97 variable. Similarly. if a T-cold indication is unavailable, equivalent information may be derived through the use of the steam generator pressure and steam tables. because the RCS cold leg temperature closely follows the steam pnerator saturation temperature. The modification to ITS Condition C represents the best conversion of the current TS to the generic ITS that is consistent with the plant design.

3.3 68 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 69 Not used. CPSESDifferencesfrom NUREG-1431 -HS3.3 7 10BOM8

JUSTIFICATION FOR DIFFERENCES FROM NUREG 1431 NUREG 1431 Section 3.3 This enclosure contains a brief description / justification for each marked up technical change to NUREG 1431 Revision 1 to make them plant-specific or to incorporate generic changes resulting from the Industry /lRC generic change process. The change numbers 'are referenced directly from the NUREG 1431 mark ups. For Enclosures 3A, 38, 4, 6A, and 68, text in brackets "[ ]" indicates the information is plant-specific and is not common to all the Joint Licensing Subcommittee (JLS) plants. Empty brackets indicate that other JLS plants may have plant specific information in that location. CHANGE ~ NUISER DESCRIPTION 3.3 01 This trip function or design feature is not included in the plant design or it is not credited and has no safety function. 3.3 02 For the Reactor Trip on Turbine Trip function based on turbine stop valve position, 4 of 4 channels are required to close to less than it open in order ~ > generate the reactor trip signal. Thus, it is acceptable to have more than one Turbine Stop Valve Closure reactor trip function channel inoperable and placed in trip per current TS Table 3.31, Functional Unit [16.b], ACTION Statement [10]. In addition, the 4 hour bypass note applies only to the [ Low Fluid Oil Pressure] channels. ITS 3.3.1 ConditionPhasbeenrevised,{ 3.3 03 CJ ~ Not applicable to CPSES. See Conversion Comparison Table

(Enclosure 68). 3.3 04 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 05 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 06 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 07 Note 3 is added to ITS SR 3.3.1.11 to be consistent with the current TS Table 4.3 1 Note [5]. This ensures that this exception for power and intermediate range detector plateau voltage verification, as discussed in the ITS BASES for SR 3.3.1.11, is included in the Technical Specifications rather than being only found in the BASES. The note replaces the exception to LCO 4.0.4 in the current TS. 3.3 08 This change ' deletes the Reviewer's Note in ITS Tables 3.3.11 and 3.3.2-1 and adds a Note reflecting the Allowable Value as the LSSS. Trip Setpoints are listed in the Bases as one of the allowed formats , approved by the NRC. These changes are acceptable as administrative i changes to match an approved format. CPSESDWerencesfrom NUREG-1431 -ITS3.3 1 IW3088

CONVERSION CONPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.3 Page 1 of 22 TECH SPEC CHANGE APPLICABILITY NUlBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-01 This trip function or design feature is not included in the Yes Yes Yes ' Yes plant design or it is not credited and has no safety function. 3.3-02 It is acceptable to have more than one Turbine Stop Valve Yes Yes Yes Yes Closure - reactor trip function channels inoperable and placed in trip per current TS Table 3.3-1. Functional Unit [16.b]. ACTION Statement [10]. In addition. the _ 4 hour bypass note applies only to the id Oil - - -_ Pressure] channels. ITS 3.3.1 '

       @ ition P has been revised 3.3-03 This change to ITS 3.3.1 Condition R is consistent with the  Yes                      No - not in current No - not in current   Yes (current TS per current licensing basis. A 4-hour ACT for SSPS logic                                  TS.                 TS.                  OL Amendment No. 64 surveillance testing has little usefulness if the RTBs                                                                        dated 10-9-91) cannot be bypassed for the duration of that testing. RTB surveillance testing retains the current 2-hour A0T.

3.3 04 This change represents the Callaway plant design as it No - see CK No - not in current No - not in current Yes (current TS per relates to the SG Water Level-Low Low Environmental 3.3 46 TS. TS. OL Amendment No. 43 Allowance Modifier (EAM) and Trip Time Delay (TTD) dated 4 14 89) circuitry. ITS Table 3.3.1 1 and Table 3.3.2 1 entries and the associated Required Actions have been enhanced to remove the redundancy in the current TS and add shutdown actions when inoperable channels aren't tripped per their Completion Time. 3.3-05 This change to ITS SR 3.3.1.3 Note 1 represents the current No not in current No - not in current No - not in current Yes (current TS per TS as it relates to the Overtemperature aT AFDt f (al) TS. TS. TS. OL Amendment No. 84 penalty function. dated 11-8-93) 3.3 06 Retains current TS power requirement of 75% RTP in the ITS Yes No - See CN 3.3-97. No - See CN 3.3-97. No - See CN 3.3-97 SR 3.3.1.6 Note concerning when the incore/excore calibration is perfonned. The ISTS proposal would require , unnecessary delays in the post refuel power ascension. The

Note is further revised to permit achieving equalibrium conditions (per CTS 4.2.2.2.d.1) prior to performing the required surveillance.

CPSES Conversion Comparison Table -ITS3.3 10(3088 ..

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-20 APPLICABILITY: DC, CP, WC, CA l REQUEST: Reject - Move contents of note to Bases. FLOG RESPONSE: JFD 3.3-20 proposed adding a note to ITS SR 3.3.3.2 for WCGS, Callaway and DCPP and ITS SR 3.3.3.3 for CPSES consistent with the CTS. The ITS is revised to move the contents of the note to the ITS Bases. DOC 8-09-LG has been initiated for moving the CTS footnote to the ITS Bases. The DOC states:

        "The CTS [3.3.3.3

footnote) associated with the [ Containment Area Radiation (High Range)) instrumentation provides details of methods of performance of the instrument channel calibration. These details are moved to the ITS Bases. These details are not necessary to ensure te associated Post Accident Monitoring (PAM) instrument is Operable. The requirements of ITS LCO 3.3.3 and the associated Surveillances are adequate for ensuring the associated PAM instrument is Operable. As such, these details are not required to be in the TS to provide adequate protection of the public health and safety. Moving these details maintains consistency with NUREG-1431. Any change to these details will be made in accordance with the Bases Control Program described in ITS Section 5.5.11."

ATTACHED PAGES: Enci2 3/4 3-53 Enci 3A 24a Enci 3B 21 EnclSA 3.3-47 Enci5B B 3.3-145 Encl 6A 2 Enci 6B 3 l l l

         ~- .- -                    -              -_ - -         - . . , _ . . _ _ - - -            - ..   .- - -. -.             .

1 l l INSTRUMENTATION 1 63 A j ACCIDENT MONITORING INSTRIMENTATION 0 1 A GEN ! LIMITING CONDITION FOR OPERATION 3.3.3.3 The accident monitoring instrumentation ch;r.nci; Basiplu shown in Table 3.3-6 shall be OPERABLE. 1 APPLICABILITY: H0 DES 1. 2. and 3. ACTION: l

a. As shown in Table 3.3 6.
b. The provisions of Specification 3.0.4 are not applicable.

gllElQ Separate 3Lon@tipOmttMtTalloj!BdWor'atacgiDJ!q1.jpg] M4M O' i SURVEILLANCE REQUIREMENTS 4.3.3.3 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL CHECK;Wg 7'T l tachirtiglgredM~Minnrlit1RinatTis"hetFiODunlRUltlEtH1414, 2

CP 3.3 ED l and

b. At least on r 18 months by performance of a CHANNEL CALIBRATI

l l

l 8 09 LG Q 3.3 20 l Cent;in int Arce ";di; tic . Cligh ",;ng;) C".'????CL CALI","ATION .4y ;;n;i;t of ;r. cic; tic,ni; ;;libr; tion of th; ch;r.ncl, not including th; itc;ter. for eenge ; j i;;i; ;bev 10 "/h :nd ; en; point ;;11br;tien dei of th; itc;ter beiw 10 "/1 l with n in:t:11;d er portabi; r-- : ;;ur;;. t I 1 CPSESMarkup ofCTS3N.3 3M 3-53 10BOM8 l i l l I

CHANGE NUMBE8 RSilC DESCRIPTION ACTION 33 has been deleted because, after revision to be consistent with NUREG 1431, it is identical to ACTION 32. These changes are less restrictive in that the required channel restoration times are increased and the option of submitting special reports in lieu of a plant shutdown is provided. T 8 09 [.G Et S cd. at#d V th g,g g

                                    . ;,. x . c :: , . .... a + r.
                                     ,                             /,~..  .s.0             \

NCiotWIWDRMfithesM5talBimtMattonMheut JCate M secessarysommessbeisscutw1ostJuident P!!LtwinELEL*Dl!LSEutt!nt01!GMl! fat @221helmuireme _ s ofEIT571COR3737pkfithelins'sociaterSurveillance_s3rg m"@rNns1w2Ethggssli4B!IEWKBustrumentlig gpersiglGggigglLgghp_syggitsglBrmBMunoitsfitolbe 1Eth!9EER!DM!niclBlegettmWJghQublic taalhMY3EMOV1EIRhttHkt4BsMintains to!ai18tnGGRlalGRIB!E!E17EdB10SaleMBDhescidetailg M1B!BuMGEBRXa$lanceittthism3Msimpattortroof AteEB!GREEUMissfomMun 8-10 - Not Used. 8 11 LS-30 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). I l l l CPSES Description of Changes to CTS 3N.3 24a 108088 A

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 21 cf 22 TECH SPEC CHANGE APPLICABILITY NUl6ER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY CANYON PEAK This CPSES-specific change revises the definition of Core Exit Temperature No Yes No No 8 07 A thermocouple channels. The change clarifies that 2 Core Exit Temperature thermocouple channels per quadrant per train with each channel consisting of , 1 thermocouple, is the same as 2 channels per quadrant with each channel consisting of 2 thermocouples. 8-08 Consistent with NUREG-1431 Rev.1. this change extends the requirement to No Yes No No LS-27 restore the inoperable channel to operable status from 7 days to 30 days. ; Consistent with NUREG-1431. this change extends the requirement to restore the inoperable channel to operable status from 48 hours to 7 days. Finally, consistent with NUREG-1431 this change replaces the requirement to shut down the plant with a requirement to submit a report describing an alternate, preplanned method of monitoring the process. Because the T and T m channels are single channel functions (1/ loop) with adequate alternate functions available, the action statements for these functions are revised consistent with the philosophy of NUREG-1431. The restoration time for inoperable channels with adequate alternate functions is decreased from 90 days in current TS to 30 days in the improved TS: however, the option of providing a written report describing an alternate, preplanned method of monitoring the process is allowed. If the above conditions are not met. 7 days are allowed for function restoration prior to initiating a required shutdown. ACTION 33 has been deleted because. after revision to be consistent with NUREG-1431, it is identical to ACTION 32. ; These changes are less restrictive in that the required channel restoration times are increased and the option of submitting special reports in lieu of a . plant shutdown is provided. es ! 8 .D9 7"ct L J . N/ Ayes N/Aygg N/Aygg N/A

        , =====e wqre issewum                                          -m             .     ..

M -

n. . . --

8-10 Not used. N/A N/A N/A N/A 8 11 This change revises the DCPP current TS 3.3.3.6 to conform to NUREG-1431 , Yes No No No LS-30 Revision 1 and revises current TS Table 3.3-10 to both add and delete ' instruments per the Reviewer's Note on ISTS Table 3.3.3-1. CPSES Conversion Comparison Table - CTS 3M.3 1030M8

PAM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

       ........................................N0TE                                       - -----                -- - ---.. ---............

SR 3.3.3.1 and SR 3.3.3.23 apply to each PAM instrumentation Function in . 7. T~ T7

                                                                                                                                                                                                                                         ~      ~

Table 3.3.3 1 . . 4 ,u. f r . ' .. 3 SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized. lliR3l3J..] ;r==m" E--MNOTEFevEEEETFT-25 #3;3 27;d 8PRUcab.lg3010gigggeg)anDitqihghnelslonlM r=w---1-g:z-2-mEgLrg?w-- ==== EEinte3HANNEL]EIBRATicin 92idays SR 3.3.3.23 - - - - - NOTE--- - ---- --- - Ncutrer, detceter ;r cxchd:d fra;;; R3.&7011 Pi, o .t a.ktitPt .. . Pma m t T.nn<> AT..T.ni.t if MDRMMMM4QC RIJS M I M

                                                                                                     - - , . . - '                                                ]                                                                    S-9-00 Q 3.3 20
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                                    . . ,          ..a_.             ..
                                          .. . . .          .. ,.             : : rl .    ..._...;...

thah 4 , f Perform CHANNEL CALIBRATION. 16 months M t CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-47 10B088

PAM Instrumentation B 3.3.3 BASES during normal operational use of the displays associated with the LCO required channels. N

                                                 ; A;.Se                   . s . , J . . -. . .. . .                                       -
                                                                                                                                                         ; o.            '!,e..      .

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CP 3.3 001 renceum-1seersuste 06tC0CoondeMm1 SMivetititE2flRialEEnantatmX0rlstants3ftettainetlisi tM3dK8PfaQtRRELtalf.4WaWMifR3CIWililiddEO38 Mcattatematith23&Issantraggggggs; tor;f,hMIMiggeQgn1teg;g Il!!108Re!@MDanGannamistecqueenga_mg SR 3.3.3.03 A CHANNEL CALIBRATION is performed every }8 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies'that the channel responds to measured parameter with the necessary range and accuracy. This SR is modified by a Note that excludes neutton detecteNhglitMMirAddtgBMdfdl GIBER 2MU TPc ::libretier. ethed for reutron it;;ter; i; ;;;ccified ir. tre 1on me s-s m Bases of LCO 3.3.1, " Reactor Trip System (RTS) Instrumentation." ..t- 4 p. J+

                                                 . m .J .i . . .,                             ..;.                              ..-                               .

y.6;,".i TR-3.3 004 yspy. ... .. .

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L s.. . .a . .. .. .. . . - .. . . ., , _ % ; .. r . nientanamianisasumin The Frequency is based on operating experience 3 1NelodilEthtNEstDENBBIENGGAR/lasugsg r etW M - u tW oR20Rlhe eith CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-145 10B088

            . _ .         . . _ _ ~ -                        _.          -

! CHANGE I l NUMBER JUSTIFICATION l 3.3 09 Not applicable to CPSES. See Conversion Comparison Table i (Enclosure 6B). l 3.3-10 Not applicable to CPSES. See Conversion Comparison Table 1 (Enclosure 6B). 3.3 11 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). l l 3.3 12 This change corrects a typo in the inequality sign of ITS Table 3.3.21 l l Note (h). The time constant should be "2" the specified value. 3.3 13 Not applicable to CPSES. See Conversion Comparison Table i (Enclosure 6B). l i 3.3-14 Not applicable to CPSES. See Conversion Comparison Table ! (Enclosure 6B). l 1 3.3 15 The channel check surveillance (SR 3.3.2.1) is deleted from the P 11 [and P-12] interlocks because channel checks are not applicable for ! permissive functions. This change is consistent with the current TS. l 3.3-16 This change [ ] deletes SR 3.3.2.9 from Function 6.g in ITS ., l Table 3.3.21. [ ] The deleted surveillance is a CHANNEL CALIBRATION , which is not applicable to this trip function, since it is not credited l in any accident analysis. These changes are consistent with current TS [ ] Table 4.3-2 Functional Unit [6.e]. 3.3 17 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-18 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3-19 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 20 This changc ;dds nott 2 on [Containocat Arca Radiction ('ligh Rangch

                                                                                          "  0 3.3 20 I calibration in ITS SR [3.3.3.3] to bc consistant with current TS Tabic [4.3.3.3.5 footnotc). This note is :::cptabic as it rcficcts th uniquc calibratica rcquircccats of thcsc high range radiatica monitors ;s dcfined in the currcat TS%e _

3.3-21 Not applicable to CPSES. See Conversion Comparison Table j (Enclosure 6B). 3.3 22 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). i. CPSES Differencesfrom NUREG-1431 -ITS 3.3 2 1020R8

i CONVERSION CONPARISON TABLE FOR DIFFERENCES FROM NUREG 1431. SECTION 3.3 Page 3 of 22 TECH SPEC CHANGE APPLICABILITY , NUMER DESCRIPTION DIABLO CANYON CONANCHE PEAK WOLF CREEK CALLAWAY i 3.3 15 The CHANNEL CHECK surveillance (SR 3.3.2.1) is deleted from Yes Yes Yes . Yes the P-11 [and P-12] interlock because CHANNEL CHECKS are not applicable for permissive functions. This change is consistent with the current TS. 3.3-16 [ ] deleted SR 3.3.2.9 from Function 6.g in ITS Table No - not in current Yes Yes (Note [(p)] per Yes (Note [(n)] per 3.3.2 1. [] These changes are consistent with current TS TS. current TS.) current TS. OL Amendment No. 26 [ ] Table 4.3 2 Functional Unit [6.e]. . dated 7-29-87) 3.3 17 New CONDITION [P] is added for Function 6.h of ITS Table No - not in current No - not in current Yes Yes 3.3.2-1. consistent with current TS Table 3.3-3 ACTION TS. TS. Statement [15]. Revises ITS 3.3.2 Condition K to be consistent with current No - not in current No - not in current No - see CN Yes (current TS per 3.3 18 TS Table 3.3 3 ACTION Statement 32, as revised per TS. TS. 3.3 134. OL Amendment No. 64 Enclosure 2. for Functional Unit 7.b. dated 10-9-91) 3.3 19 18 month test interval previously approved by MtC for No - not in current No - not in current Yes (justified per Yes (justified per selected slave relays which, if tested at power could TS. TS. SLNRC 84 0038 dated SLMtC 84-0038 dated result in plant trips or unseh- _ 2 ?? 01:- 2-27-84)

             .".di-d 7.;;; 2 ;- [0;-ti._... ".r;; "ed% tim ( :1@ " . )]                          Veq                  Vesg                   Vesp h-20       calitc; tim ir "0 5" [3.2.2.3] t; b; . . . .t.. /. d th Ves!W}

0 3.3- ! '

cur. ;-.t r, T;tk [?.0.3.3.5 6..~;G. teggend _ s I i r CPSES Conversion Comparison TnMe -ITS3.3 IW3618

i l i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-24 APPLICABILITY: CP, WC, CA REQUEST: Changes improved TS Table 3.3.4-1 to reflect current TS [3.3.3.2.11). Deletes references to " controls" in the table (see also CN 3.3-94) and changes

Required Number of Functions" to " Required Channels" since the Table has been revised to include only instrumentation.

Comment: TSTF travelerrs required for deviation from NUREG-1431 unless justified by design. Table column header " required channels" does not agree with LCO statement. Revise Table 3.3.4-1 to adopt STS format for conformance to " separate ! l condition entry for each function." FLOG RESPONSE: For CPSES, ITS Table 3.3.4-1 column header is revised to maintain the NUREG-1431 wording," REQUIRED NUMBER OF FUNCTIONS," as discussed during the August 14,1998 meeting. Additional changes to ITS Table 3.3.4-1 are made as discussed at the meeting. For WCGS and Callaway, after further discussions with Operations personnel, the ITS Table 3.3.4-1 column header is being maintained as " REQUIRED CHANNELS." Maintaining this wording is consistent with other ITS Section 3.3 tables and with CTS Table 3.3-9. Maintaining the column header as " REQUIRED CHANNELS"is not in conflict with the LCO statemer)t with the additional changes made to the Table to identify the specific instrument as a function and each function requires only one channel to be OPERABLE. Maintaining the column header potentially prevents a confusion factor when other ITS Section 3.3 tables have the same function listed and specify the number of required channels whereas ITS Table 3.3.4-1 would specify a required number of functions. Additional changes to ITS Table 3.3.4-1 are made as discussed at the meeting. ATTACHED PAGES: Enci5A 3.3-52 EnctSB B 3.3-146, and B 3.3-148 Enci6A 3 Enci 6B 4 i v .m

i 1 Remote Shutdown System l 3.3.4 Table 3.3.4-1 (page 1 of 1) g l Remote Shutdown Systes In;tr. :-t;ti;r. cr.d C;-tr;Q,,. M. F - n.,._a.__.__._, . . ...m_._ ,<2._. 2._...2,,._2._.. r__..___,.. _ ,. 2 __. _-. .~. ... ,.. ._. ... . __. .__..

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Remote Shutdown System B 3.3.4 B 3.3 INSTRUMENTATION B 3.3.4 Remote Shutdown System BASES BACKGROUND A safe shutdown condition is defined as MODE 3. With the unit in MODE 3, the Auxiliary Feedwater (AFW) System and the steam generator (SG) safety valves or the SG atmospheric dump tyljef valves 90VenllRI$J can be used to remove core decay heat and meet all safety requirements. The long term supply of water for the AFW System and the ability to borate the Reactor Coolant System (RCS) from outside the control room allows extended operation in MODE 3. If the control room becomes inaccessible, the operators can establish control at the re e tc Up_t2 Shutdown Panel, and place and maintain the unit in MODE 3. Not all controls and necessary transfer switches are located at the resta Hot Shutdowntanel. Some controls and transfer switches will'- CP 3.3 009 have to be operated locally at the switchgear, motor control panels, titM:tfinsfegatp] or other local stations. The unit automatically reaches MODE 3 following a unit shutdown and can be maintained safely in MODE 3 for an extended period of time. The OPERABILITY of theM qremote shutdow'n 0 3.3 24 controlg and timBMERumnwu.-.m... functions ensures there is sufficient information available on selected unit parameters to place and maintain the unit in MODE 3 should the control room become inaccessible, g!g cp.3.3 002

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[ y 4, g. ,1 J o 6,6 (continued) CPSESMarksp ofNUREG-1431 Bases -ITS 3.3 B 3.3146 10B088

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m E D MR$t MilRDB M m W 21 The remote shutdown instrument and control circuits covered by ! this LCO do not need to be energized to be considered OPERABLE. This LCO is intended to ensure the instruments and control r circuits will be OPERABLE if unit conditions require that the Remote Shutdown System be placed in operation. 4 e

APPLICABILITY The Remote Shutdown System LC0 is applicable in H0 DES 1, 2, and 3. This is required so that the unit can be placed and s

                                                                                                                                                                                                 .(continued) i CPSESMarkup ofNUREG-1431 Bases -ITS 3,3                                               B 3.3-148                                                                                                                  10B088

CHANGE NUMBER JUSTIFICATION 3.3 23 Modifies ITS Surveillance Requirement 3.3.4.2 to include power circuits per Current TS 4.3.3.2.2. This change is made to match the plant design which includes transfer switches for power circuits as well as control circuits. 3.3 24 This change revises improved TS Table 3.3.41 to reflect current g,3'3,24 TS [3.3.3.2.1], deletes references to " controls" in the table (cce N.y [f. _bfb.....~

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                                                                                    .~..m.  .y ir.:trumentatioyArreviseo, tne table is now consistent with~the format or the other tables in ITS Section 3.3 ITS and is technically                   l the same as the current TS requirements.

l 3.3 25 Not applicable to CPSES. See Conversion Comparison Table j (Enclosure 63). l 3.3 26 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 27 This change modifies SR 3.3.3.2 and SR 3.3.3.3 to allow for different surveillance frequencies for the hydrogen monitors than other PAMS components. The manufacturer for the CPSES hydrogen monitors specifies a more frequent calibration frequency than required for the other PAMS instruments. The more frequent calibration is required to assure _ function operability. 3.3 28 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 29 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 30 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). ) 3.3 31 The current TS require the response times associated with the [undervoltage and degraded voltage diesel generator start functions and the] containment [ ventilation] isolation functions to be verified against the specific response time values contained in the [TRM]. The ITS is revised to match the current TS and the response time values are [ retained in the TRH]. As is done with the Reactor Trip System and the ESFAS instrumentation, this method is an appropriate way to control response times. [SR 3.3.5.4 and SR 3.3.6.8] are added to require the response time verification. 3.3 32 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). , 3.3 33 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). CPSESDifferencesfrom NUREG-1431 -ITS3.3 3 102088 l

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3 Page 4 of 22 TECH SPEC CHANGE APPLICABILITY DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUPSER 3.3 21 ITS 3.3.3 was revised to reflect current TS 3.3.3.6. No - see CN 3.3-71. No - see CN 3.3-70. Yes (see Amendment' Yes (see UURC-3023 Containment Isolation Valve Position (and Notes) and No. 89) dated 5-20 94 and Condensate Storage Tank Level were deleted. [ Combined the Amenseent No. 103 power and source range neutron flux entries into a single dated 10 20-%) neutron flux entry.] Consolidated the Thermocouple / Core Cooling Detection System entries. Changed number of required channels for RCS temperature to 2 for both hot and cold leg temperature. Changed Containment Pressure Wide Range to Containment Pressure Normal Range and added Refueling Water Storage Tank Level. Steam Line Pressure, and SG Water Level (Narrow Range) Functions as these are current TS requirements. Changed the required number of channels for SG Water Level (Wide Range) and AFW Flow Rate from 2 per SG to 1 per SG and added corresponding notes to Conditions A and C. 3.3-22 Consistent with current TS [3.3.3.5]. [RCP breaker Yes No not in current Yes Yes indication is excluded from CHANNEL CHECKS and reactor trip TS. breaker and RCP breaker indications are excluded fron] , CHANNEL CALIBRATIONS in ITS SR 3.3.4.3 since these SRs have no meaning for [these] functions. CPSES specific change that modifies ITS Surveillance No Yes No No j 3.3 23 Requirement 3.3.4.2 to include power circuits. 3.3 24 Changes improved TS Table 3.3.41 to reflect current TS No - see CN Yes Yes Yes [3.3.3.2.11]. Deletes references to

controls
in 3.3-128. E 0 3.3- !4 Er table f ue also CN 3.3 96 ..d ;L..,.; -";gi ;d !L,-M y BummamasM, M, .ctb.;" te -";& i red O_h" ;i .cc tk T; tic M; RJ. k

                         " -- Q ir.c hd; miy '...^.. - .J.;ti =.                                                                                                             #

3.3 25 Adds Applicability Note consistent with that found in No - see CN 3.3-84. No - not in current Yes Yes. improved TS Table 3.3.11 (i.e., source range neutron flux TS. is only required below the P 6 interlock). This is , consistent with current TS Table 3.3-9. i CPSES Conversion Comparison TaNe -ITS3.3 JW3W98 i w w.s + - __. __ _ _ _ _ . _ . ._-___m_ _ _ _ . . . _ _ _ _ _ _ ._m.___-__am._______mm_._ . _ _ . _ _ _ _ _ _ _ _ - ---_____._.__________.___w-- w. - - - v-

 .. . .~ - - - . - - - - .-                            .. --              - - -      - . - - - _ . . - - . - . - _ .      - . . . - - -

l 1 ADDITIONAL INFORMATION COVER SHEET l l ADDITIONAL INFORMATION NO: O 3.3-31 APPLICABILITY: DC, CP, CA, WC i REQUEST: The current TS require the response times associated with the [undervoltage and degraded voltage diesel generator start functions and the] containment [ ventilation) isolation functions to be verified against the specific response time values contained in the [TRM]. The , ITS is revised to match the current TS and the response time values are [ retained in the TRM]. l As is done with the reactor trip system and the ESFAS instrumentation, this method is an l appropriate way to control response times. [SR 3.3.5.4 and SR 3.3.6.8] are added to require l the response time verifications. ! Comment: {DC} 3.3-31 discusses response time. Clarify the use of this evaluation for the changes to ITS T3.3.6-1 footnotes (a) and (b). l {CP, CW} Revise SR 3.3.6.8 in response to disposition of 3.3-55 to delete reference to

                             " required."

FLOG RESPONSE: For DCPP, JFD 3.3-79 should be applied to footnotes (a) and (b). Table 3.3.6-1 footnote (a)is further revised by JFD 3.3-79. Callaway and CPSES have addressed the second comment in their response to Comment Number O 3.3-55. Note that the Callaway l response to Comment Number O 3.3-32 results in the re-numbering of ITS 3.3.6 surveillance l requirements. ., ) l JFD 3.3-31 is also applicable to Wolf Creek as identified in the response to Comment Number Q 3.3-55. ATTACHED PAGES: I None l l I A

. _ .- - . - - = - _ _ . . - . . . .- - - - . - - ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-37 APPLICABILITY: DC, CP REQUEST: Several ITS Required Action Notes are modified to allow a channel to be placed in bypass for surveillance testing. [This change, incorporating bypass test instrumentatie Nas approved for CPSES through Amendments 47 and 33 for Units 1 and 2, iespectively.] Comment: Reject for CP application to 3.3.1 Action D.1& E.1 & M.1 -The ITS proposes generic changes to the STS that are not included in an approved TSTF. The ISTS notes allowing bypass for testing are based on WCAP-10271. Provide a reference that shows staff approval of the proposed deviation from the ITS based on the accepted analysis of WCAP-10271. FLOG RESPONSE: The changes in 3.3.1 Actions D.1, E.1 and M.1 have been confirmed to be consistent with the CTS for CPSES. In verifying these actions, it was discovered that the note for the condition for Turbine Trip (condition P in the STS) had not been modified to reflect the bypass for testing allowed by the CTS. The conditions for Turbine Trip have been revised in the response to RAI 3.3-02. In addition to those changes, the note to new Required Action O.1 is revised to read "The inoperable channel or another channel may ..." to incorporate the bypass testing allowed by the CTS. The word overlooked in the first sentence of the DCPP response has been replaced with the following "not included in the mark-up of ITS LCO 3.3.1 ACTIONS E.1 and M.1. Also see Additional Information Number DC 3.3-003. ATTACHED PAGES: Enci5A 3.3-8 Enci5B B 3.3-46a

-m

RTS Instrumentation 3.3.1 ACTIONS (continued) l i CONDITION REQUIRED ACTION COMPLETION TIME 1 O. 0.c "acter 0;;1:nt "u;;;p "0TE 3G "rcckcr ";sition cher.r.cl The ireperabic chenac1 ;;;ay be in;pcr;bic. typ ssed fer up to 4 hours for 0-3.3 37 M' surveiller. - ^^-tir. ef ett-- f RWE!KfM1!ORG Dt35EE18thkitit4 ; FN 3.3 02 M'Lnope!'el8!i] m mx .C @ M O'3' '

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ir p cianne 10 j - chor.rel =y be byp;ssed inoperable. I for up t; 4 hours for ' 1 survei"ence testing ;f othcr _ 3 3j202 1 k t.eare.s. ' N J P.1 Place channelg in trip. 6 hours E l I P.2 Reduce THERMAL POWER to 10 hours 4 '

                                               < [21 lj (continued) l 1

. CPSESMarkup ofNUREG-1431- ITS 3.3 3.3-8 10B088

RTS Instrumentation B 3.3.1 BASES , I a.3.3 37 hlNtt'111N@StV6t]T U: I Wci n ~ :an: . . . @ . ' .s bOE lt. jar!Iftit X J og tf,M G IC h 0 v M

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i , 1 l I / (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3-46a 10B088

ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: Q 3.3-40 APPLICABILITY: DC, CP, WC, CA REQUEST: Add "and setpoint adjustment" to ITS 3.3.1 Condition E, similar to the Note for Condition D. j l Comment: Reject - The ITS proposes generic changes to the STS that are not included in an approved TSTF. The justification is inadequate. Adequate justification would be the format is not usable, or the requirements represent unsafe practices or may result in an operational hardship. FLOG RESPONSE: The FLOG withdraws the changes associated with JFD 3.3-40. ATTACHED PAGES: Enci 2 3/4 3-6 Enci 3A 6 Enci5A 3.3-4 Enci5B B 3.3-41 Encl 6A 4 Encl 6B 7 - t I t ! l i. j, P

TABLE 3.3 1 (Continued) l ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the M4einum M Channels 0"E"XLE ccquir;nat, restore the inoperable y"v.. " channel to OPERABLE status within 48 hours or be in HOT l STANDBY within the next 6 hours. l ACTION 2 - With the number of OPERABLE channels one less than the Tote + Nu.ici ;f ggR,jggd Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours,

b. O,c ",ini;;;;;;; Cher.r 1 0"E"XLE requir;nat i; ; ret, yg43.ggq

hs.cvcr. gggthe inoperable channel or another channel may be bypassed for up to 4 hours for "1,17; A d. l setpojntlad,$1stment;ot surveillance testing per Spaific; tion 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER end the 1148 6

                                                                          ";wcr ",;ng; Ncutren Ela Trip S:tpcint is reduad t; ic:: then er cquel t; 05t of "#EO                +-s-A il:E""'L "0L'E", within 412 hours: or, ifithe              0-3.3 120 PdWerZtlIGDMlBl$tplCQE1J!put[tCthf.@ADRANT POWER TILT RATIO 152fgogetabje)~9he3RR is                               ,

l monitored at least once per 12 hoursi per 1 66.Ls Spaific;tien 4.2.4.1. 03.3..i

       -                                                  !!eg             pgiertifisGDe'JirglWUSTAleBYMthin32 JiourA I

MJIONZ2[15 With;th0ggegCpidtggggghedspl@ng2eq01;hayjg l gequirep3timatimilmantagessgil!ER;RENg0griproce~ed E l l provmmssaamiersonasmsm*menced: ggigig l g]' 6dBsfitCttW3ripplld M.

bJ pptERMe.31mMIESEBh!IlmilHERMlJm3 Meal!E!!!!if [.[3 40 l bg G E-r t- Za="4C;rs 5vd$0rVeillaD!3

! a m.m.wamamenmannearneo t l ACTION 3 - With the number of channels OPERABLE one less than the Mminum g ! BeiqGirdEChannels 0"E"XLE rcquircxat erd with the " E""J.L "0',JE",icvel.

                                         ;.                  Sci;W th; " 5 (Intczndi;te "sens; Ncution El=                             $1 E E Interix!0 Sctp; int, rester; the inspcrobic chenrel t; i

0"E"#LE st;tus prior t; ircreesing T"E""*L "0L'E", eb;vc the " 5 Setpcint,

          ,,____m___                                                  ..___..;_;m____m._m mand ="m"d!Pi Rr""r . - T_-                                                      _- __ mMat3 5%%Wm
                                                                                       --~---.a,n.----..m=--

g , l -_ __ Q 3.3 120 CPSESMarkup of CTS 3M.3 3M 3-6 10B088

   . .-    . - - - - - - _ - -                          ._- - - . - - - . .                 . . - - _ . -                 _ _ =

i CHANGE NLDBER NSRG DESCRIPTION 1-17 A Consistent with NUREG-1431 Rev.1. LCO 3.3.1 Required Action D Note, current TS Table 3.3 1 ACTION _ o.3,3 40 Statement 2 - . m . - ,..-_ _... .. k;c % been modified by a Note that asiows the bypass to be used for surveillance testing or setpoint adjustment. Setpoint ' l adjustment can be performed at power and may be required by other Technical Specifications. The reason for placing the channel in bypass does not affect the impact of having l the channel in bypass. l 1-18 LS 7 The current TS requirement to reduce the Power Range Neutron Flux Trip setpoint in the event a power range flux channel is inoperable is deleted. This deletion is consistent with NUREG-1431 Rev.1 and justified by:

1) The loss of one channel does not impact the reliability of the Reactor Trip System because the affected channel is placed in trip. It may, however, impact the ability to measure the QPTR. If the plant wishes to !

remain at 100% RTP, then the QPTR must'be l measured using the movable incore detectors. 1 Otherwise. the power level must be reduced to i 75% RTP. If the plant chooses to reduce power rather than measure QPTR using the movable incere detectors, the peaking factor surveillances must still be performed on the required frequency.

2) The loss of one channel does not necessarily indicate any core tilt. but rather the inability to measure core tilt with the -

excore instrumentation. On this basis, there is no justification for reducing the Trip Setpoint, and incurring the potential for a reactor trip, when there is no indication of an abnormal condition existing in the core. NUREG-1431 Rev. I also allows 12 hours to reduce the thermal power to less than 75t RTP rather than the 4 hours required by the current TS. If the Power Range Neutron Flux trip function is inoperable, but the input to the QPTR is operable, the ISTS do not require that the QPTR be monitored every 12 hours. l CPSES Description of Changer to CTS 3N.3 6 10/3088 9

2 I a , RTS Instrumentation 3.3.1 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME J I , E. One channel inoperable. --- - ------NOTE - ------- - l The inoperable channel g M j W

                                                        . i    0 ay be bypassed i

for up to 4 hours for l surveillance tactina k J [ f other 973-46 I channels. 0 3.3 40 i i l E.1 Place channel in trip. 6 hours 3 E I E.2 Be in H0DE 3. 12 hours i F. TliE""fi "0 'E", : "5 F.1 Reduce THERHAL POWER to M2 hours

                                                                                                              -     163.3007dt end < " 10, One                          < P 6.

Intermediate Range k3 341558 Neutron Flux channel E _ inoperable. F.2 Increase THERMAL POWER to M2 hours

                                                   > P 10.

G. I'E"".'i "" 'E" : " 5 end G.1 Suspend operations involving Immediately c " 10. Two Intermediate positive reactivity j Range Neutron Flux additions. channels inoperable. 6ND G.2 Reduce THERMAL POWER to 2 hours

                                                   < P 6.

H. Igggg] li.1 "; ster; channel (s' to "rier to 59 $S54 ll E"".'i ^~#'E", < " 5. On; 0"E""2EE :tetus. incr;;;ing or two Interr.; diet; T E""."1 "O.lE" to "ar.g: "cutren flux >-P-6 chenacis inegrebl;. , (continued) i CPSESMarkup ofNUREG-1431- ITS3.3 3.3-4 10B088 l

1 RTS Instrumentation l B 3.3.1 l BASES

                         ;        50 "atcr Lcycl ' .; coincident with Stcc: Flow /Fcadwater                         ;

Flow "ic:stch. A known inoperable channel must be placed in the tripped ! condition within 6 hours. Placing the channel in the tripped condition results in a partial trip condition requiring only one-out of two logic for actuation of the two out of three trips and one out of three logic for actuation of the two out of four trips. The 6 hours allowed to place the inoperable channel in 4 the tripped condition is justified in Reference 715] l l If the operable channel cannot be placed in the trip condition ' within the specified Completion Time, the unit must be placed in a MODE where these Functions are not required OPERABLE. An additional 6 hours is allowed to place the unit in MODE 3. Six hours is a reasonable time, based on operating experience, to l place the unit in MODE 3 from full power in an orderly manner and without challenging unit systems. The Required Actions have been modified by a Note that allows placing the inoperable channel in the bypassed condition f'or up ) to 4 hours while perhinn rniitina curve 111ance testing of the nthar channale Cir=C;116TdlMylst'r,gg - li?E,1bisy ...;17EO. cmp;1G5;idition~to~aiiCMira 0-3.3-@ .;l , cdf0% .^OG:.,%..'.Q;;f1 W 4 hour time limit is ! justified in Reference 7- g; - F.1 and F.2 Condition F applies to the Intermediate Range Neutron Flux trip when THERMAL POWER is above the P 6 setpoint and below the P-10 setpoint and one channel is inoperable. Above the P 6 setpoint and below the P-10 setpoint, the NIS intermediate range detector performs the monitoring Functions. If THERMAL POWER is greater than the P 6 setpoint but less than the P 10 setpoint, 22J hours is allowed to reduce THEP. MAL POWER below the P-6 setpoint or increase to THERMAL POWER above the P 10 setpoint. The NIS Intermediate Range Neutron Flux channels must be OPERABLE when the power level is above the capability of the source range, P 6, and below the capability of the power range, P 10. If THERMAL POWER is greater than the P 10 setpoint, the NIS power range detectors perform the monitoring and protection functions and the intermediate range is not required. The Completion Times allow for a slow and controlled power adjustment above P 10 or below (continued) CPSES Markup ofbTJREG-1431 Bases -ITS 3.3 B 3.3-41 10B088

i CHANGE NUMBER JUSTIFICATION 3.3-34 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3-35 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). 3.3 36 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-37 Several ITS Required Action Notes are modified to allow a channel to be placed in bypass for surveillance testing. [This change. incorporating bypass test instrumentation, was approved for CPSES through Amendments 47 and 33 for Units 1 and 2. respectively.] 3.3-38 The CPSES design uses the N 16 based overtemperature and overpower protective functions. Several changes to the setpoints. Required i Actions and Surveillances of NUREG 1431 are required to maintain the current licensing basis. 3.3-39 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 68). ;

                                                                          . Condition 3.3-40

[7similar toscth:edds "end sctpcint odjust; cat" Notc for Condition D. Sctpoint adjusta nt is ., o.3,3 4o g rc-quired by the "aquir;d Actions of othcr spGifications. The clarity and consistency of the specificati;n is cahoried by oddins 'iis

                    ,Qadition E. in the same-monncr ;3 Condition ". Not_3sedi i

3.3-41 ITS 3.3.1 Condition L is deleted to match the plant specific design CA 3.3 016 and the currcat TS for the source range neutron flux function in Mode

3. 4. and 5 with the Rod Control System incapable of rod withdrawal and all rods not fully inserted. Under these conditions, the source range instrumentation does not provide a Reactor Trip System function.

The source range channels provide only indication [ ] when in this Applicability. Requirements related to the source range neutron flux channels in Modes 3. 4 and 5 when all rods are fully inserted and are not capable of being withdrawn have therefore been [ relocated outside of technical specifications]. This change is consistent with traveler TSTF 135. 3.3-42 This change deletes ITS 3.3.1 Condition N per traveler TSTF-169. l Condition H is appropriate for Function 10.a to prevent sequential ; entry into Condition N followed by H and exceeding the evaluated , Completion Time in Wr,AP 10271-P A. Supplement 2. Rev.1. With this ! change, there is no need to list separate Functions 10.A and 10.b and combining the Functions eliminates Applicability questions similar to the Condition M vs. N concern above. 3.3 43 This change revises ITS 3.3.1 Condition R Notes 1 and 2 per traveler TSTF 168. The 2 hour A0T should not be limited to only UVTA/STA (l CPSES Differencesfrom NUREG-1431 -ITS 3.3 4 10/30M8

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, $ECTION 3.3 Page 7 cf 22 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION No - not in current No - not in current No - not in current Yes (current TS per 3.3-36 Revisions reflect revised BDNS setpoint in current TS. TS. TS. TS. OL Amendment No. 94 dated 3 7-95) Yes Yes No - not in current No - not in current 3.3 37 Several ITS Required Action Notes are modified to allow a design or TS. design or TS. channel to be placed in bypass for surveillance testing. [This change, incorporating bypass test instrumentation. was approved for CPSES through #sendments 47 and 33 for Units 1 and 2. respectively.] Yes No No The CPSES design uses the N 16 based overtemperature and No 3.3-38 overpower protective functions. Several changes to the setpoints. Required Actions and Surveillances of NUREG-1431 are required to maintain the current licensing basis. No - not in current No - not in current Yes Yes 3.3 39 Improved TS Table 3.3.7 1 is changed to be consistent with TS. current TS Table 3.3-3. The Actuation Logic was split to TS. reflect the SSPS, with only NODE 1-4 Applicability, and BOP-ESFAS portions and associated SR requirements in the current TS. f Ie-4 dr. int ;dju_..t" to 17, 3.3.1 Ce;2 bA C. VesM VesM VesN6 3.3-40 y w e:e = = C_; =ac. n : gy No - see CN Yes Yes Yes 3.3 41 ITS 3.3.1 Condition L * ; deleted to match the plant-specific design and t t ;w .m/. F, for the Source Range 3.3 123. Neutron Flux Function in NODES 3. 4. and 5 with the Rod Control System incapable of rod withdrawal and all rods l CA-3.3-0 .6 l fully inserted. Under these conditions. the source range instrumentation does not provide a Reactor Trip System Function. The source range channels provide only indication [ ] when in this Applicability. Requirements

related to the source range neutron flux channels in ,

N0 DES 3, 4, and 5 when all rods are fully inserted and are not capable of being withdrawn have therefore been ' [ relocated outside of the technical specifications). 1W3&98 CPSES Conversion Comparison Table -ITS 3.3

                                                                                                                                                                                                                                                 . -      .- -      .~.

ADDITIONAL INFORMATION COVEf1 SHEET ADDITIONAL INFORMATION NO: Q 3.3-43 APPLICABILITY: DC, CP, WC, CA REQUEST: Revise ITS 3.3.1 Condition R Notes 1 and 2 per traveler TSTF-168. The 2-hour AOT should not be limited to only UVTA/STA maintenance. Comment: TSTF Pending NRR review. Based on 8/14/98 meeting -TSTF rejected based on WCAP-14333 which prohibits " maintenance bypass." FLOG RESPONSE: TSTF-168 has been approved by the NRC. Therefore, the FLOG continues to pursue the changes associated with JFD 3.3-43. ATTACHED PAGES: EnctSA Travelar Status Sheet l 4 l 4 4 l

 ._         _ _ ~                        .      .        _ _ _ _            . .        .      __ .        . .     . .

I i INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 TRAVELER # STATUS DIFFERENCE # C0lHENTS TSTF-19. Rev. 1 Not]ncorporated NA ";t

                                                                          ",.",O;ppr;;;d   as of
                                                                     ...      ,              _m      l TR-3.: -004 l
                                                                     .. ... 2._i.._. ..w M RNIN M.

TS" 30."cv. 2 - Incorper; tad &+-34 TSTF-37, Rev. 1 Not Incorporated NA ITS 5.6.8 still addresses PAM reports. Sections after ITS 5.6.7 were not renumbered. , TSTF-51 Not Incorporated NA Requires plant specific reanalysis to establish decay time dependence for fuel handling accident.

                     !!st I nciper;ted                             [ ] A11;= bic "clucs j

ETF-91 NA for 1;;; cf v;1t;;c and {] 3.on3 g degrad d voltage will rc=in in the TS. TSTF-111, Rev. 1 Incorporated NA TSTF-135j9te973 "arti:11y Incorporated 3.3 41 Trevcicr is tc; breed - x ;pc in n;turc. W@ 33rJA 3_M should h;vc ban 33jlp]I] xveral x p;retc trovclers. I 3.3 93 "ertions of the trr.vcler that 3.3 95, significently clarify 373BE egrability rcquir;xats have 3.3 122, ban ixerper; tad. 3,3.iBai! TSTF-161.gggg Incorporated 3.3-79 40tMBadWWC @7 y Incorporated 3.3 43 (,BttigttrJt9ERESC TSTF 168 M 0 3. mammemummme 43 E TSTF 169 Incorporated 3.3-42 61 l TR-3.1 003 l W9G-196mrz2fg Incorporated 3.3 49 l o.3, 49 g 1 I EEgfE" reposed Incorporated 3.3 107 "00 ltini-Creup Action 0 3.. 107 E l tr;;cler Itc;;; #145. l

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.3-44 APPLICABILITY: DC, CP, WC, CA , i REQUEST: Revise ITS 3.3.1 Conditions S and T and ITS 3.3.2 Condition L, as well as the number of Required Channels [] in Tables 3.3.1-1 and 3.3.2-1, to reflect current TS ACTION j Statements [7 and 18]. Comment: [ Reject]- The proposed ITS Conditions are presented as "one or more inoperable channels" which is a generic change to the STS. Provide a citation for the approved TSTF that this change is based on. The number of applicable ITS channels is proposed to be one less than the CTS total channels. The proposed changes are not consistent with the STS. Revise ITS T3.3.1-1 to include the CTS ' total" channels as the ITS " required" channels. The CTS markup changes the total number of channels for the P-11 interlock (CTS function Ba) from 3 channels to 2. This is counter to the format of the improved tech specs and this is a change to the CTS. All installed channels should be required to be operable and actions provided for any channel out of service. If the impact of a single inoperable channelis very low, the required action may be minimal. [See also comments to DOC 1-37A) i FLOG RESPONSE: In response to the first comment, the changes to ITS 3.3.1 Conditions S and T and to ITS 3.3.2 Condition L do not require an approved TSTF traveler. These changes are taken directly from the CTS ACTIONS which cover conditions with *less than the Minimum Number of Channels", not just one permissive channel inoperable. The ITS will not be changed. In response to the second and third comments, the CTS markup to change the number of required channels has been deleted and all permissive P-8, P-9, P-10, and P-11 channels will be required OPERABLE in ITS Tables 3.3.1-1 and 3.3.2-1. DOC 1-37-A has been changed to DOC 1-37-M since this is a more restrictive change. Comment Number 1-37-A is also resolved by this response. ATTACHED PAGES: Enct2 3/4 3-4 and 3/4 3-25 Enci 3A 10 and 11 Enci3B 7 Enci5A 3.3-21 and 3.3-43 Enci 5B B 3.3-31, B 3.3-32 and B 3.3-33 Enci 6A 5 Enci 68 8

TABLE 3.3-1 (Continued) REACTOR TRIP SYSTEM INSTRUMENTATION RERRRED MINIMUM rg TOTAL "0. CY""CLS O?J:"ELS APPLICABLE ,7 4 j FUNCTIONAL UNIT OF-CHANNELS "J "tIP 0"E"X LE MODES ACTION 4J

16. Turbine Trip

a. Low Fluid Oil 3 2 2 l' 6M 1,11,g Pressure 0 3.3 02

b. Turbine Stop Valve 4 4 4 l' 1011 Closure

17. Safety Injection Input 2 1 2 1, 2 13 from ESFAS

18. Reactor Trip System Interlocks

a. Intermediate Range 2 1 2 26 7 Neutron Flux, P-6

b. Low Power Reactor Trips Block, P-7 53py

1) " 10 Inst 411tperatrajn 2 s 1-2 73 T KT7'

2) P 13 InWt 2 1 2 -1 1 l

c. Power Range Neutron Flux, P 8 483 2 3 1 73

d. Power Range Neutron Flux, P-9 4 6-4 2 3 l' l'37 4

e. Power Range Neutron Flux, P 10 4 2 3 1, 2 7 ,

CMARfUrsf151LeggtttesMPjl31st mgyTa, d2fl52751[Eiftydiyng!!!?figElggs . y b

19. Reactor Trip Breakers' 2 1 2 1, 2 8 - 14 - 4 2 1 2 3', 4', 5 9 B6MMge P-3.

NEM

                     .6                                                                                                                  ,

PJEglitetWiperIRTB ,- gga>y;;4= - n Q;LTeeachlpelr RTB i!3*fLi'Efd 2B12W1 g L

20. Automatic Trip and 2 1 2 1, 2 13 Interlock Logic 2 1 2 3', 4', S' 9 CPSESMarkup ofC753N.3 3M 3-4 1030A3

TABLE 3.3-2 : ENGINFFRED SAFETY FEATURES AC111ATION SYSTEM INSTRlMENTATION M MHHMM =~*7"r ** ? , 4 -

                                                                                                                                                     "JT1 O.         C"/"" LS          0"f?5LS             APPLICABLE FUNCTIONAL UNIT                                                                                                                           OF-CHANNELS     TO lit!"          0"E"X LE                    MODES       ACTION E:               t

10. Engineered Safety Features Actuation System Interlocks" - - - - - - - - - - - - -

                                                                                                                                                                                                                                        ~N                                            :

Pressurizer

                                                                                                                                                                 '._.         2                 2                    1,2,3       18                                    1-37-4

a. 0-3.3-44

                     -Pressure P-11

b. Reactor Trip, P-4 2 2- 2 1,2,3 20 .

t

11. Solid State Safeguards Sequencer (SSSS)

a. Safety Injection 1/ train 1/ train 1/ train 1, 2, 3, 4 26 Sequence Wdb. ,.:

b. Blackout Sequence 1/ train 1/trair. 1/ train 1,2,3,4 25 l

l t b i CPSESMarkup ofCTS3N.3 3M 3-25 5A537 ;

CHANGE NUMBER }L9]C DESCRIPTION TS has no Specification 4.0.4 exception, this 4 hour allowance is less restrictive. 1 28 A Note [9] is revised to require the P 6 and P 10 interlock verification to be performed during all source range COTS. These permissives are verified to be in their correct state prior to entry into MODES 3, 4, and 5 during shutdown and after leaving MODES 3. 4, and 5 during startup. This change is consistent with NUREG 1431 Rev.1. A Not applicable to CPSES. See Conversion Comparison Table 1 29 (Enclosure 3B). M Not applicable to CPSES. See Conversion Comparison Table 1 30 (Enclosure 3B). A One time surveillance waivers are deleted. They are no 1-31 longer applicable. 1 32 LG [ Note (11) of current TS Table 4.31 is revised to move the independent UVTA and STA verification to the BASES for ITS SR 3.3.1.4.] [ ] Notes [(14) and (16) and the 18 month TAD 0T for the automatic undervoltage trip] of current TS . Table 4.31 are moved to the BASES for ITS SR 3.3.1.14. These changes are consistent with NUREG 1431 Rev.1. 1-33 TR 1 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38). 1 34 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 1-35 LG Not applicable to CPSES. See Conversion Comparison Table i (Enclosure 3B). 1 36 H Not applicable to CPSES. See Conversion Comparison ' Table (Enclosure 38). In the current TS, the "Hinimum Channels OPERABLE" is 1 37 MJ one less than the " Total Number of Channels" for Functional Units [18.c] (P 8), [18.d](P 9), and [18.e](P 10) in Table 3.31 and Functional Unit [10.a] (P 11) in Table [3.3-2]. For these Reactor Trip System and ESFAS interlocks, current ACTION Statements [7 and 18] for an inoperable channel are based on the " Minimum Channels OPERABLE" columns in Tables 3.31 and [3.3 2]. In the improved TS, only the " Total Number of Channels" information is retained in the LCO and that column is 10 10/30198 CPSES Description of Changes to CTS 3M.3

CHANGE NUMBER RSE DESCRIPTION relabeled as the " Required Channels", as discussed in CN 1 04 LG and CN 1-43 A. Required Actions in improved TS 3.3.1 Conditions S and T and improved TS 3.3.2

                                                                                    ._ Required Channels %

_ 0 3.3 44 a ,a . . . .. . g;y ., ; . ., ..y ;.o . s v . L gggg Ther;ferc. the rquir;d p;rr.issiv; channel: f;r th;;; Functional 'Jnit; er; r;;ised in th; current TS-Refer also to CN 1 51 LG for P 7. 1 38 R In MODES 3, 4, and 5 when all control rods are fully inserted and the Rod Control System is incapable of rod withdrawal, the source range neutron flux function does not provide input to any reactor trip function nor is it credited for mitigation of any analyzed event. (At one time, the source range neutron flux signal was credited in the analysis of the inadvertent boron dilution event: however, as described in a previous license amendment [20/06], this analysis was revised to credit other alarms.) Because the source range neutron flux function in these conditions does not satisfy any of the four - criteria of 10CFR50.36(c)(2)(ii), it is being deleted from the Technical Specifications. However, the operation of this function will continue to be maintained through plant procedures as it does provide important alternate indication to the reactor operators. 1-39 A This change adds Note [5] to Functional Units [2.b and 3] in current TS Table 4.31. Note [5] is currently listed against Functional Unite [2.a]. Testing methodology and the timing of the testing for the power range channels apply to all power range functions, not just power range - high. As such, this is an administrative change only. ITS SR 3.3.1.11 applies to all power range functions in a similar fashion. 1 40 LS 41 Not applicable ic CPSES. See Conversion Comparison Table (Enclosure 3B). 1 41 A Not applicable to CPSES. See Conversion Comparison Table 1 (Enclosure 38). 1-42 M Not applicable to CPSES. See Conversion Comparison Table (Enclosure 2b.'. 1-43 A The " Total Numbe." of Channels" columns in current TS 4 Tables 3.31 and C3.3 3] and the [" Minimum Channels j Operable") column in current TS Table [3.3 4] are CPSES Description of Changes to CTS 3N.3 11 1080/98

 ~ ..         . .   . _ _           , , . .     . . .                             .

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 7 of 22 TECH SPEC CHANGE APPLICABILITY NUPSER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALUNAY CANYON PEAK 1-34 Callaway's current ACTION Statement 5.b requirements for two inoperable source No No No Yes A range channels are divided between the reactor trip. indication, and BONS ' functions served by the source range channels. New ACTION Statement 4.1, added to current TS Table 3.3-1. retains the requirement to open the reactor trip breakers to serve the reactor trip function. The ACTION Statement 5.b requirements that are not related to reactor trip are moved to ITS 3.3.9. See also CN 1-30 N. 1-35 This change moves response time limit tables to the updated FSAR per Generic Yes No already No - already No - already LG Letter 93 08 and NUREG-1431 Rev. 1. moved to TRN. moved to USAR moved to FSAR Section 16.3. Section 16.3. 1-36 This DCPP specific change adds a requirement to perform a Channel Calibration on Yes No No No Functional Unit 17 every 18 months. In the current TS, the Minimum Channels OPERABLE" is one less than the " Total 1-37 A Number of Channels

for Functional Units (18.c] (P 8), [18.d](P-9), and Yes Yes Yes p

Yes

[18.e](P-10) in Table 3.3 1 and Functional Unit [10.a](P-11) in Table [3.3-2]. For these Reactor Trip System and ESFAS interlocks, current ACTION Statements [7 and 18] for an inoperable channel are based on the Minimum Channels OPERABLE" columns in Tables 3.3-1 and [3.3 2]. In the improved TS, M1y the " Total Number of Channels" information is retained in the LCO ami b r.ohan is relabele1 as the 1equired Channels", as discussed in CN 104 LG and CK 543-A. Required Actions in improved TS 3.3.1 Conditions 5 and T and improved TS 3.3.2 CorwH H - I = tied to the R-nired Channels.'$ggdlg[Dji$ndj)j0R3

                       .          < .. .      m      _                              ,

ffg$litei%8ll

                        , . . . ' " = J ._ . .J : 'r t"-- - r_ Mrd 'J,it; r , m ':;cd t th; c. . ...; TS.

Refer also to CN 1-DI-LG for P 7. 1-38 The source range channel operability requirements in NODES 3, 4 and 5 when No - see CN 1- Yes - Yes - No - see CNs 1-R incapable of rod withdrawal are relocated to a licensee controlled doctaient. 09-N relocated to relocated to 10-LS-32. 1 '

                                                                                                           -                TRN                Chapter 16.3     N. and 1-34-A.

of the USAR. 1-39 This change adds Note [(5)] to Functional Units [2.b and 3] in current TS Yes Yes Yes Yes A Table 4.3-1. CPSES Conversion Comparison Table - CTS 3H.3 IW3M8 Neef.B 4+r

RTS Instrumentation 3.3.1 Table 3.3.1 1 (page 6 of 9) Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REgu! RED SURVEILLANCE ALLOWABLE Mfe FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE*8 GE4P9HW"

                                                                                                                                                      -] ~ ~ ~ ~

17. Safety 1,2 2 trains o SR 3.3.1.14 NA NA Injection (SI)

Input from Engineered Safety Feature Actuation System (ESFAS) 1

18. Resctor Trip 1 System Interlocks

a. Intermediate, 2'" 2 S SR 3.3.1.11 a 6E:}} amp t-+E-49 by#$.g l Range Neutron SR 3.3.1.13 any ,

Flux, P-6

b. Low Power 1 1 per T M233CC". NA Reactor Trips train E 3.3.1.5 m 3.3-54 Block, P-7 {'.'.}.))

                                                                                        .m  , . . . . . ,

0 3.3 54

c. Power Range 1 4 T 59:2 i ..

Neutron Flux, SR 3.3.1.11 D!NJ5RTP ; O 277 . . . _.i P-8 . SR 3.3.1.13 l

d. Power Range 1 4 5( T SM a := ;~7 ihB-44 i Neutron Flux, SR 3.3.1.11 T5583 RTP 0-3.3-44 !

P-9 m SR 3.3.1.13 j i

e. Power Range 1,2 4 56 S 7:e := ::7 7^~'~ l Neutron Flux, (~

SR 3.3.1.11 57,35RTP P-10 SR 3.3.1.13 and 4 M

D E M RTP 4M ' '

f. Turbine 1 2 T s-HME fopertse g = *.3.1.t D333 ttrrtrene ,

ggg SR 3.3.1.10 turbine power . 7 .. Pressure, P-13 SR 3.3.1.13 power

19. Reactor Trip 1,2 2 trains R SR 3.3.1.4 NA M Breakers (R75#3(k) EI) 3*', 4*', 5 *' 2 trains C SR 3.3.1.4 NA M TR 3.3-006 (continued)

(s) :.. e_ .'. .;.. ;;. . ; ro , h e ..,,; .. . .;.U. -, e .;. ; . .; ,- ;.t ; L;. V. '. _ J,r. J . . , . L ;4. . .;

     ;; ;,     U..J.;,, eJ L, J.,       . ;. ))iEMMFJ4WeM'MiggM; Red                                                                                  .. '

WR5MIPMiMHCffEsmM (b) With ;;;. mi..W ..J Rod Control System capable of rod withdrawal M'orytJg;;jece"pAMQU9 M (2) Below the P-6 (Intermediate Range Neutron Flux) interlocks. (k) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. 3.3 122 TR 3.3-006 CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-21 10B088

ESFAS Instrumentation ! 3.3.2 l \ i l Table 3.3.21 (page 10 of 10) i Engineered Safety Feature Actuation System Instrumentation APPLICABLE s 1

                                                                                                                                                                                                                                    ,.7..-

a .2 OTHER Mle ' SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE SE +M l FUNCTION COBOITIONS CHAN>ELS COBOITIONS REQUIREEKIS VALUEen 1 f

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8. ESFAS Interlocks B-0-44

a. Reactor Trip P 4 1.2.3 1 per F SR 3.3.2.11 NA Q.3.5 44 train. 2

, trains __

b. Pressurizer 1.2.3 q t. L 5" 2.2.2.1 s 1996 ;;'

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a St dy ;rc'.g .xd Ly tr.; . 't. Eurm3ewensanammaramurmattensmrutnusmuttanuttmee mit T., i. 1 t I r CPSESMarkup ofNUREG-1431 - ITS33 3.3-43 10B088

1 RTS Instrumentation B 3.3.1 BASES

                                                 . RCP Orc har Pesition (Tw L;;p;);
                                                 -    Undervoltage RCPs: and
                                                 . Underfrequency RCPs.

Trip Sctp;ints ;nd Allowable Values are not applicable to the P 7 interlock because it is a logic Function and thus has no parameter with which to associate an LSSS. The P 7 interlock is a logic Function with train and not channel identity. Therefore, the LC0 requires one channel per train of Low Power Reactor Trips Block, P 7 interlock to be OPERABLE in H00E 1. The low power trips are blocked below the P-7 setpoint and unblocked above the P 7 setpoint. In H00E 2, 3, 4, 5, or 6 this Function does not have to be OPERABLE because the interlock performs its Function when power level drops below 10% power, which is in H00E 1.'-

c. Power Ranoe Neutron Flux. P 8 The Power Range Neutron Flux, P 8 interlock is actuated at approximately 48% power as determined by two-out of four NIS power range detectors. The P 8 interlock automatically enables the Reactor Coolant Flow-Low (Single Loop) ;nd RCP Orckr P:sition (Singic L;;p) reactor trips on low flow in one or more RCS loops on increasing power. The LC0 requirement for this trip Function ensures that protection is provided against a loss of flow in any RCS loop that could result in DNB conditions in the core when greater than ;ppr;xi= tcly 48% power. On decreasing i

power, the reactor trip on low flow in any loop is l automatically blocked. The LCO require [C-hour channels of Power 0 3.3-44 Range Neutron Flux, r-o interlock to be OPERABLE l I in H0DE 1. In H0DE 1, a loss of flow in one RCS loop could result l in DNB conditions, so the Power Range Neutron Flux, l P 8 interlock must be OPERABLE. In H00E 2, 3, 4, 5. or 6, this Function does not have to be OPERABLE

,                                                                                                           i l

B3.3-31 10/3088 CPSES Markup ofNUREG-1431 Bases -ITS 3.3

RTS Instrumentation B 3.3.1 BASES l l because the core is not producing sufficient power to be concerned about DNB conditions.

d. Power Ranoe Neutron Flux. P 9 The Power Range Neutron Flux, P 9 interlock is actuated at approximately 50% power as determined by two-out of-four NIS power range detectors. The LCO requirement for this Function ensures that the Turbine Trip-Low Fluid Oil Pressure and Turbine Trip-Turbine Stop Valve Closure reactor trips are enabled above the P-9 setpoint. Above the P-9 setpoint, a turbine trip will cause a load rejection beyond the ;;pecity capacities of the Steam Dump and Rod Contro11 Systems. Systc; A reactor trip is automatically initiated on a turbine trip when it is above the P-9 setpoint, to minimize the transient on the reactor.

The LC0 requires g j;;..fg wur channels of Power ' 0-3.3-44 Range Neutron Flux, r ^ kerlock to be OPERABLE-in MODE 1. l In MODE 1, 8tLogy;Pj92a turbine trip could cause CP 3.3-009 l a load rejection beyond the capacity gap 6 cities of the Steam Dump KReattorIControllS.V$tets System, so the Power Range Neutron Flux interlock must be OPERABLE. In MODE 2, 3, 4, 5. or 6, this Function does not have to be OPERABLE because the reactor is not at a power level sufficient to have a load rejection beyond the cop; city of the Ste:: Ou;p ~ Systc;. 1 E

e. Power Ranae Neutron Flux. P-10 !

The Power Range Neutron Flux, P 10 interlock is actuated at cpproxi;ctcly 10% power, as determined by two out-of four NIS power range detectors. If power level falls below 10% RTP on 3 of 4 channels, the nuclear instrument trips will be automatically unblocked. The LCO requirement for the P 10 interlock ensures that the following Functions are performed: i

                                      .      on increasing power, the P 10 interlock allows the operator to manually block the Intermediate Range Neutron Flux reactor trip.

Note that blocking the reactor trip also blocks CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-32 10B088

l l l l RTS Instrumentation i B 3.3.1 BASES the signal to prevent automatic and manual rod withdrawal:

                                                  .       on increasing power, the P-10 interlock allows the operator to manually block the Power Range Neutron Flux-Low reactor trip;
                                                  .       on increasing power, the P-10 interlock automatically provides a backup signal to block the Source Range Neutron Flux reactor trip, and also to de energize the NIS source range detectors:
                                                  .       the P 10 interlock provides one of the two inputs to the P-7 interlock; and
                                                  .       on decreasing power, the P 10 interlock automatically enables the Power Range Neutron Flux-Low reactor trip and the Intermediate Range Neutron Flux reactor trip (and rod stop).      ,

BecausCo lev 4Tsand21-81_ldiglb]ey.) m e Ea.nc.; .f.2 .m-x' ? c R D A.y vdm.M L e -J m.- ?+': : 4 L3hliRR- ? % A .:.d- .;h + 2x 4 - + S 1), o The LC0 requires h -~ '

                                                                                        -"- -hannels of Power Range Neutron Flux, r-u interlock to be OPERABLE in N0DE 1 or 2.

OPERABILITY in H0DE 1 ensures the Function is available to perform its decreasing power Functions in the event of a reactor shutdown. This Function must be OPERABLE in MODE 2 to ensure that core protection is provided during a startup or shutdown by the Power Range Neutron Flux-Low and Intermediate Range Neutron Flux reactor trips. In MODE 3, 4, 5, or 6, this Function does not have to be OPERABLE because the reactor.is not at power and the Source Range Neutron i Flux reactor trip provides core protection. l l f. Turbine I=uhe Fir 3t:StsM Pressure. P 13 l l ! ! l CPSES Markup ofNUREG-1431 Bases -ITS 3.3 , B 3.3-33 103088 __m

CHANGE NUMBER JUSTIFICATION maintenance. This is consistent with the current TS and is acceptable because the specific maintenance activity which requires that a reactor trip breaker be bypassed does not affect the impact of having the breaker bypassed. [ Notes 1 and 2 are combined to reflect CTS Table 3.3-1, Action 8.] 3.3 44 3.3.1 Conditions S and T and ITS 3.3.2 g,3,3,44 g This change Condition.L. c y; wil :: the n;.;;cr c ;;qu;rcs incnac;; in dcbic: 3.3.1 1 :..-d 3.3.211 to ret tect current TS ACTION 5tatements [7 and 18]. The conditions apply to one or more channels [ ] because l the safety function is served with the interlock in the aporopriate l l state for existing plant conditiony:nc cmsung p;nt scsign on;y l fQuirc; 3 cf th; 4 chc;.aci; (2-cut of 3 for I' 11) for thc;c interlock 3 h bc egrchic. f 3.3 45 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-46 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). l 3.3 47 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).

3.3 48 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 49 ITS SR 3.3.1.8 is revised to extend the conditional COT frequency for power and intermediate range channels from 4 hours after reducing power below P 10 to 12 hours, based on operating experience regarding the time needed to perform the COTS. It stands to reason that if 4 hours are allowed for 2 Source Range COTS,12 hours should be allowed for ! 6 Intermediate Range and Power Range COTS. The SR continues to assure that the COTS are performed in a timely manner after the requisite plant conditions are entered. This change is consistent with o.3,3 49 traveler N W9G-106. 3.3 50 ITS SR 3.3.1.12 is deleted per the current TS. Where cited in Table 3.3.11, a change to SR 3.3.1.10 has been made. The plant-specific design does not use bypass loop RTDs for the protection system. 3.3 51 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). l 3.3 52 This change adds Note [(1)] to ITS Table 3.3.11 per the current TS as , an operator aid to note the dual RTS/ESFAS functions of SG Water Level l t Low Low. This is an administrative enhancement to reflect the plant's dual requirements for this function. i 5 10BOM8 CPSES Differencesfrom NUREG-1431 -ITS 3.3

Page 8 cf 22 CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431 SECTION 3.3 APPLICABILITY TECH SPEC CHANGE DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION 4 Yes Yes Yes Yes 3.3-42 Delete ITS 3.3.1 Condition N and combine Functions 30.a and 10.b per traveler TSTF-169. Yes Yes Yes 3.3 43 Revise ITS 3.3.1 Condition R Notes 1 and 2 per traveler Yes TSTF-168. The 2-hour A0T should not be limited to only (NTA/STA maintenance. Yes Yes Yes Yes 3.3-44 Revise ITS 3.3.1 Conditions S and T and ITS 3.3.2

                                                                                                                                                       ""'"                         D
                                                                                                                                                                                                                                                                           -    /

M N ..'". . _ 3 ~N ' s i. M..jto rersect cm m

                                                                                                   . ._                   -.                                        ia ACTION Statements [7 and 18].

A new CONDITION and SR are added for the current licensing Yes No - not in current No - not in current No - not in current 3.3-45 TS. TS. TS. basis required seismic trip. A new CONDITION and SR are added for the current licensing Yes No - not in current No - not in current No - not in current 3.3-46 TS. TS. basis required Steam Generator level low-low time delay TS. trip. These changes affect both ITS 3.3.1 and 3.3.2. Note 2 of SR 3.3.1.2 is revised to limit the power increase Yes No - not in current No - not in current No - not in current 3.3-47 TS. TS. to less than 30t per the current licensing basis before the TS. SR is complete. No Yes No 3.3 48 ITS SR 3.3.1.7 has a Note that provides a four hour delay No in the requirement to perform the Surveillance for source range instrumentation when entering NODE 3 from NODE 2. Wolf Creek has deleted this Note in accordance with current Surveillance Requirements and the revisions made in ITS Table 3.3-1. The requirements for this Surveillance will be maintained by ITS SR 3.3.1.8 indicated by the revision of SR 3.3.1.7 to SR 3.3.1.8 in Table 3.3.1-1 for each applicable function. SR 3.3.1.8 has been structured to cover NI instrtmentation Functions specified in ITS Table 3.3.1-1 and SR 3.3.1.7 has been structured to cover all other RTS instrumentation Functions. This is similar to ,- the way the NJREG has structured SR 3.3.1.10 and SR 3.3.1.11. CPSES Conversion Comparison Table -ITS3.3 10B088 L _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . - _ . . _ . . _ _ . ___m_..___.______--____m_ ____. _m__ _ _ _ _ _ _ _ _ - _ __ - v _

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.3-49 APPLICABILITY: DC, CP, WC, CA REQUEST: ITS SR 3.3.1.8 is revised to extend the conditional COT frequency for power and intermediate range channels from 4 hours after reducing power below P-10 to 12 hours, based on operating experience regarding the time needed to perform the COTS. It stands to reason that if 4 hours are allowed for 2 Source Range COTS,12 hours should be allowed for 6 Intermediate Range and Power Range COTS. - ' Comment: Reject - The ITS proposes generic changes to the STS that are not included in an approved TSTF. The justification is inadequate. Adequate justification would be the format is not usable, or the requirements represent unsafe practices or may result in an operational hardship. In support of a safety or operational hardship argument provide data to support the statement that operating experience shows 12 hours is required to perform the SR. l Additionaljustification required. FLOG RESPONSE: These conditional COTS on the power range neutron flux-Inw and intermediate range neutron flux channels are not in the current TS. The current TS requires only that COTS be performed on these Functions prior to startup. In order for the FLOG members to assume these more restrictive surveillance requirements, as discussed in DOC 1-22-M, sufficient time must be allowed for performing the COTS with consideration given t6the fact they are performed sequentially, not simultaneously, since the COTS are performed with the channel in trip. WOG-106, currently under NRC review as TSTF-242, was originated by Callaway based on a review of several years of work history records indicating that nuclear instrumentation system COTS require 1-2 hours to perform. These COTS are governed by continuous use procedures that require independent verification; four hours is insufficient time to perform the six COTS. Given the FLOG members' willingness to assume more restrictive requirements not found in the current TS, the allowed time should account for current plant practices. Twelve hours is a reasonable time period for performing six COTS on these channels. ATTACHED PAGES: Enci 3A 8 Enci5A Traveler Status Sheet Encl 6A 5 i l l

^m

CHANGE NUMBER NSiC DESCRIPTION interlocks are verified to be in their required state during all COTS on the Power Range Neutron Flux-Low and Intermediate Range Neutron Flux trip functions. These changes ary,, Inn

tent with NUREG-1431 Rev.1 and _

g,3,3,49 g travele murmim ',100 1-23 A This change adds new Note [(18)] to current TS Table 4.3-1 and new Note [(5)] to current TS Table 4.3 2 that explicitly require the 18 month calibrations to include verifications of affected time constants, consistent with NUREG 1431 Rev.1. 1-24 LS 9 This change reflects a relaxation in the performance of COTS prior to startup, consistent with NUREG 1431, Rev. 1. These COTS, for the Power Range Neutron Flux - Low. Intermediate Range Neutron Flux, and Source Range Neutron Flux trip functions, will not be required if performed within the previous 92 days. Note [(1)] of CTS Table 4.31 has been revised to extend this period from 31 days to 92 days. Note [(la)] is added for use with the turbine trip function TAD 0Ts, for which no such change was provided. 1 1-25 Alj NUREG-1431 Rev. 1 incorporates the current TS 4.0.4 p.125 exception for the surveillances covered by current TS Table 4.31 Notes (2), (3), and (6) into the ISTS SR 3.3.1.2, 3.3.1.3, and 3.3.1.6 surveillance frequencies. In the current TS, these surveillances have no time requirements.[ ] In general, the combined effect of current TS 4.0.3 and current TS 4.0.4 would allow [24 hours] for completion of a surveillance if it were not performed upon entry into the specified MODE or other condition for that surveillance. Current TS 4.0.3 allows [24 hours] for the completion of a surveillance once the appropriate MODE or plant condition is established. In the improved TS the TS 4.0.4 exceptions are incorporated as a NOTE in each affected surveillance. In converting to the NUREG-1431 format. ITS SR 3.3.1.2, SR 3.3.1.3, and SR 3.3.1.6 require these surveillances to be performed within [24] hours after THERMAL POWER is greater than or equal to 15% RTP (current TS Note (2) for the comparison of NIS power to calorimetric power), within [24] hours after 50% RTP (current TS Note (3) for the comparison of excore ' Axial Flux Difference (AFD) to incore AFD), and [within 72 hours after achieving equilibrium conditions with THERMAL POWER greater than or equal to 75t] RTP (current TS Note (6) for the incore excore calibration), respectively. Since these surveillances are conditional on THERMAL POWER h o CPSES Description of Changes to CTS 3M.3 8 10B088 l l m

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 ; i TRAVELER # STATUS DIFFERENCE # COMMENTS l 1 TSTF-19. Rev. 1 Netincorporated NA Net-NRC e,pprev;d es of TR-3.,-004

                                                           ...&.. u. .
                                                                        .A. .. . w.s M3 INMI                                                 ;
                                                           ;.%u.    .

"TF 35. 0;V. 2 Incorpreted S-3-34 I i TSTF 37. Rev. 1 Not Incorporated NA ITS 5.6.8 still addresses PAM j reports. Sections after ; ITS 5.6.7 were not renumbered. TSTF-51 Not Incorporated NA Requires plant-specific ; reanalysis to establish decay time dependence for fuel ; handling accident. ) TSTr 01 Not !nc;rp reted NA [ ] Allow bi; "clu;; TR 3 3-005 l t for los; cf volteg; :nd d;; red d v;1 tag; will r;;;in !

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                                                           ... .       n...

TSTF-111. Rev. 1 Incorporated NA TSTF-135ERey23 Partially 3.3 41 Trevcicr i; to; breed '- @@ , Incorporated 3:3?44 s;;p; in r.:tur;; should hav; b;;n 3:3790] 313191] 3;ver:1 :cper t; tr;v;1;rs. 3.3-93 P;rtion; cf the trav;1;r th:t 3.3-95. significantly ci;rify 3.J330M sp rebility r;quir;. cat: hov; 3.3-122, b;;n incorpreted. 3:3B42 Incorporated 3.3 79 AjppltWedibyltERG TSTF-161.BeI51 TSTF 168 Incorporated 3.3-43 ADtWiWd'bKtWAtC gy TSTF 169 Incorporated 3.3-42 @DHf8@Y ttieN2

 =105 M .           Incorporated           3.3 49 M irrep;;;d        Incorporated           3.3-107           = "ini Cresp Action          a.3, .107 I tre.v;1;r Itc; #145.                                     ;
                                                                                                             ;I'
                                                                                                             <L i

CHANGE NUMBER JUSTIFICATION maintenance. This is consistent with the current TS and is acceptable because the specific maintenance activity which requires that a reactor trip breaker be bypassed does not affect the impact of having the breaker bypassed. [ Notes 1 and 2 are combined to reflect CTS Table 3.3 1. Action 8.] 3.3 44 This change revises ITS 3.3.1 Conditions S and T and ITS 3.3.2 O'3'3 # Condition L. Os .;cil s the nu;bcr of "cquircd Ch;nacis in Tebics 3.3.11 nd 3.3.21. to reflect current TS ACTION State. gents [7 and 18]. The conditions apply to one or more channels [ ] because the safety function is served with the interlock in the appropriate state for existing plant conditions. The cxisting plant design only rcquires 3 of the 4 chsnacis (2 out of-3 for " 11) for thes; interlocks to bc eg rebic.- 3.3 45 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3 46 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). 3.3-47 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).

3.3 48 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B). i 3.3 49 ITS SR 3.3.1.8 is revised to extend the conditional COT frequency for I power and intermediate range channels from 4 hours after reducing power below P-10 to 12 hours, based on operating experience regarding the , l time needed to perform the COTS. It stands to reason that if 4 hours l l are allowed for 2 Source Range COTS 12 hours should be allowed for l 6 Intermediate Range and Power Range COTS. The SR continues to assure that the COTS are performed in a timely manner after the requisite plant cond)t4;;; ;rc ry. This change is consistent with _- o.3,3 49 l travele ,3,Ltsz421 '40C 100 3.3 50 ITS SR 3.3.1.12 is deleted per the current TS. Where cited in Table 3.3.11, a change to SR 3.3.1.10 has been made. The plant-specific design does not use bypass loop RTDs for the protection system. 3.3 51 Not applicable to CPSES. See Conversion Comparison Table l (Enclosure 6B). 3.3-52 This change adds Note [(1)] to ITS Table 3.3.1-1 per the current TS as an operator aid to note the dual RTS/ESFAS functions of SG Water Level Low Low. This is an administrative enhancement to reflect the plant's dual requirements for this function. l 10/3088 lc CPSES Differencesfrom NUREG-1431 -ITS 3.3 5

                                                                          ~                              *

             --    .         __    - _ = _      .            -                - _ _ . . - .        .- -

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 7-09 APPLICABILITY: CP, CA, DC REQUEST: Clarification is provided that Channel Checks are only required for normally energized instrumentation channels by adding "for each required instrumentation channel that is normally energized", per ITS [SR 3.3.3.1 and SR 3.3.4.1] to CTS [4.3.3.5.1 and 4.3.3.6]. Comment: [See LS 1 GEN] [ Application should include DC. Add list of instruments currently in this category in the LS for PAMs and RDS.] FLOG RESPONSE: The applicability of DOC 7-09 LS-43 has been revised to include DCPP. j l Per the agreement at the 8/14/98 meeting, a list of the de-energized instruments will be included in LS-43. ATTACHED PAGES: Enci 4 65 )

  -Enct5B B 3.3-144 and B 3.3-150                                                       -

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- i l

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e

IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 43 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS l The current TS require that CHANNEL CALIBRATIONS are performed for instrumentation l used in the Post Accident Monitoring [and Remote Shutdown] Systems on an 18 month l basis. Some of these instruments are then de energized and remain in this state until re energized for use in the management of plant events or for the performance of the CHANNEL CHECKS. CHANNEL CHECKS are performed more frequently than CHANNEL CALIBRATIONS for the purpose of detecting gross channel failures or excessive drift of one channel relative to other channels monitoring the same process variable. During the period that the channel is de-energized, it is not subject to the failure mechanisms or conditions that typically lead to instrument failure or excessive drift. Recognizing that de-energized channels are not subjected to the same failure mechanisms as energized channels, the current TS was revised to exempt instrumentation that is not normally energized from the performance of the periodic CHANNEL CHECKS. JfoRowing~arelthoselinsttunentsfttthatzareyrmal,]yJielenergized$ l Q-7 09 l [Chargiggipump30;CVCEchaggtpgla]! d y;5ealsZfloOndica, tion The proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:

               "The Commission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license for a facility licensed under 50.21 (b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety."

The following evaluation is provided for the three categories of the significant hazards consideration standards:

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The instrumentation affected by the proposed change does not provide any ; automatic reactor protection or ESFAS functions. The instrumentation is used i to provide indication to the reactor operators following a plant event. This j indication may be used by the plant staff to manage an event, but serves no i CPSESNo Significant Ha:ards Consideration - CTS 3N.3 65 10B088

l PAM Instrumentation l B 3.3.3 BASES are not equivalent, and provide a schedule for restoring the normal PAM channels. SURVEILLANCE A Note has been added to the SR Table to clarify that REQUIREMENTS SR 3.3.3.1 and SR 3.3.3.23 apply to each PAM instrumentation Function in Table 3.3.3-17unleiss'otherwiselnoted&SRl3.3.3.2 applies;only,toltheJydrogenimonitorsC SR 3.3/3.3.~ applies _to .all otherlPA, M jnstrumentat_1on. SR 3.3.3.1 l l Performance of the CHANNEL CHECK once every 31 days ensures that j a gross instrumentation failure has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the two instrument channels could be an. indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure: thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION. ,,~ ...,. . om.. ica instru;catation should bc compared to similar unit instru; cats locatcd throughout the unit-- Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including isolation, indication, and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. If the channels are within the criteria, it is an indication that the channels are OPERABLE. As specified in the SR, a CHANNEL CHECK is on19 r uired for those channal- +* are norma 11v anargha&do, , 1 0-7-09 l g'amentslistedlinaableA3233rateamrma11renergizev] The Frequency of 31 days is based on operating experience that demonstrates that channel failure is rare. The CHANNEL CHECK j supplements less formal, but more frequent, checks of channels l (continued) B 3.3-144

l Remote Shutdown System B 3.3.4 ; BASES i Completion Time is based on operating experience and the low probability of an event that would require evacuation of the control room. B.1 and B.2 If the Required Action and associated Completion Time of Condition A is not met, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours and to MODE 4 within 12 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and i without challenging unit systems. 1 SURVEILLANCE SR 3.3.4.1 REQUIREMENTS Performance of the CHANNEL CHECK once every 31 days ensures that , a gross failure of instrumentation has not occurred. A CHhNNEL l CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. CHANNEL CHECK will detect gross channel failure: thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION. Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including indication and readability. If the channels are within the criteria, it is an indication that the channels are OPERABLE. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. As specified in the Surveillance, a CHANNEL CHECK is only

                         , required for those channok which are normally enernN                 0-7 09 l i                          ~ u!e._excepqon otthe_Qharging pump;t_o;C)[CS3nd_RCP,sealsflow j                            indication;Iallfjnstr_umentsjistedlinlableM4jl are normal]y_e_nergiz_ed;;

(continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3150 1020A8

 .             .   .       __ . . . _     . _ _ - . . - . .- . _ _ _. .._ . - _.       ~ . - - _ . -

l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 7-10 APPLICABILITY: DC, CP ' l REQUEST: In the CTS, the determination that the steam generators are available for decay I heat removal, using instrumentation available at the remote shutdown panel, is based on steam ! generator level and auxiliary feedwater flow to the steam generator. In the ITS, it is recognized l that either of these indications is su'ricient. I Comment: Reject proposed CTS changes which replace requirements for both SG l level and AFW flow rate functions to be operable with an ITS allowance that g is j required to be operable. I {DC} Additionally, the SG leyv.gl and AFW ikLW RSS functions are missing from the ITS markup of Table 3.3.4-1. Thus these functions are not combined as stated in LS-26. 1 I FLOG RESPONSE: This change is no longer applicable since the separate SG level and AFW flow functions are being retained. For DCPP, the deletion of the SG level and AFW flow i i function from Table 3.3.4-1 was inadvertent and has been restored. 1 Also see the response to Comment Number Q 3.3-24 for CPSES and Q 3.3-128 for DCPP. l ATTACHED PAGES: ., t Encl 2 3/4 3-52 Enct 3A 23 Enci 38 20 Enct 4 1,56 and 57 l l

TABLE 3.3 5 7 01 A REMOTE SHUTDOWN HONITORING 4MSWWHEMTAT40N 0701

                                                                                                  .. gn . . . .;
                                                                                                  ..w .a: a Ji HIMINWH REAE W F       TOTAL l0.           GHANNELS N                                                   EOGATION       BE-G%NNEES          OPEMBEE REMERlB NUMBER.Gi 99ENEl:S Functions

1. Neutron Flux Monitors HSP 2 1

2. Wide Range RCS Temp.-T, HSP Ubeep 1/ Loop

3. Wide Range RCS Temp.-T, HSP Ubeep 1/ Loop *

4. Pressurizer Pressure HSP 1 1

5. Pressurizer Level HSP 2 1

6. Steam Generator Pressure HSP WSG 1/SG

7. S im Generator Level HSP WSG 1/SG 8-ij Auxiliary Feedwater Flow ate to Steam Generator HSP E/SG M

9. Condensate Storage Tank Level HSP 2 1 0 7 10

10. Charging Pump to CVCS HSP 1 1 Charging and RCP Seals -

Flow Indication i 1 l l i i HSP = Hot Shutdown Panel I SG

        = Steam Generator The requir; ;.-t: Of "f r5e Ch:nnch OPEP/3LE for "ide 9:nge P.CS Tc p.      T.,

re ~t; ;huthr. indication for Unit 2 era revised to 1/L;;p for thr;; (3) of the fel-31-A 4 four (4) "CS L;;ps. This revision is to r;;.:in in effect until CPSES Unit 2 , er.ter: =E 4 et the kginning of the sc;er,d refueling outesc for Unit & CPSES Markup of CTS 3N.3 3M 3-52 10B088

i ! CHANGE NUMBER ESEC DESCRIPTION i are not subjected to the same failure mechanisms as l energized channels, the current TS was revised to exempt ! instrumentation that is not normally energized from the l performance of the periodic CHANNEL CHECKS, consistent with NUREG-1431 Rev.1. 7 10 ES-26 tioKitised3:n the currcat TS. the dctereinction that th l :tc : scacrator; ;rc eveilabic for dccay hc;t rc;; val, \ using in:tru;catation vailabic et the rc;;tc shutdowr, o.7 19 , pencl. is be:cd on stes; scacrator icycl ;&d auxiliary fccd.;ctcr now to the stc;; scacrator. In the improved TS. it is rec;;niccd that either of thcsc indications is

                                    ;ufficient.;

7-11 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 7-12 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 3B). 8-01 A This change, consistent with NUREG 1431 Rev. 1, revises

                                    " Instrument" and " Channel" to " Function."

8 02 - Not Used. 8-03 A This change revises current TS Table [3.3-6] to clarify the number of channels required to be operable. This is an administrative change which deletes the " Minimum Channels Operable" column [and revises the "[ Total] No. of Channels" column to be the " Required Channels" column]. The required actions are now based on one channel inoperable or two channels inoperable, rather than "less than the Total Number" or "less than Minimum Number." This change is consistent with NUREG 1431 Rev.1. 8 04 LS-17 Consistent with NUREG 1431 Rev. 1 (ITS 3.3.3 Required i Actions C.1, E.1, and G.1), this change deletes the i requirement to initiate an alternate means of monitoring I within 72 hours when two channels of Containment Radiation Level [or RVLIS) are inoperable as specified in current TS [3.3.3.3, Action 32]. ; 8 05 A In conjunction with CN 8 03 A, this change rearranges the ACTION Statements for the single channel Functions (i.e., ! SG Water Level - Wide Range and AFW Flow Rate). No change l in A0T is requested, therefore this is an administrative change. l i CPSES Description of Changes to CTS 3N.3 23 102088

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 20 cf 22 TECH SPEC CHANGE APPLICABILITY DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY NUMBER CANYON PEAK 7 ir .: CTS. tt det.. .= tion ;i. th; ;;;s .~. ator; ;rc a;; :=:: 7;r dc=y Ves M Ves M %; =t in Ne-- O'7'" M10 n = r ; 2 1. . be;cd on ;tc= ,_.~. .t.

                                                         ;ir , in e. _ ..t;ti m ra i t t u :: thc .

1;=1 ;_d :=iliary !=d Ctr flg.: t; tt :t;= t; cce d;.r. p; m l. i; c_ . m.t n . M not fn l

                                  ,..~..;;r     I- tM !E. it i; cc.;F.;;;d tnt citkr of thc;; indi=th= i;                                                                                                                          eurre
                                  =fficient Neggeogd                                                                                                                                                                               nt-M-7-11    CTS SR 4.3.3.5.3 is deleted. This is duplicated in CTS 3.7.1.2 and covered in                                                    No - not in          No - not in            Yes                 No - retained A         ITS 3.7.5 for AFW System operability requirements.                                                                              current TS.          current TS.                                in ITS.

. 7-12 New Note excludes neutron detectors from CHANNEL CALIBRATION consistent with No - not in No - already Yes Yes A current TS Table 4.3-1. Functional Unit 6. Note 4 and with improved TS current TS. in current TS. SR 3.3.4.3. This change, consistent with NUREG-1431 Rev.1. revises " Channel

and Yes Yes Yes Yes 8-01 A
Instrument
to
Function."

Not used. N/A N/A N/A N/A 8-02 This change revises current TS Table [3.3-6] to clarify the number of channels Yes Yes Yes Yes 8-03 A required to be Operable. This is an administrative change which deletes the '

                                  *Ninimum Channels Operable" column [and revises the *[ Total] No. of Channels

column to be the
Required Channels
column]. The required actions are now based on one channel inoperable or two channels inoperable, rather than *1ess than the Total Number" or "less than Minimum Number."

8-04 Consistent with NUREG-1431 Rev. 1 (ITS 3.3.3 Required Actions C.1. E.1, and Yes Yes Yes Yes LS-17 G.1), this change deletes the requirement to initiate an alternate means of ; monitoring within 72 hours when two channels of Containment Radiation Level [or ; RVLIS) are inoperable as specified in current TS [3.3.3.3. ACTION 32]. 8-05 In conjunction with CN 8-03-A. this change rearranges the ACTION Statements for No - see CN No not in Yes Yes A the single channel Functions (i.e.. SG Water Level Wide Range and AFW Flow 8-11-LS 30. current TS. Rate). No change in A0T is requested, therefore this is an ackninistrative , change. , 8 06 Specific equipment ID numbers are moved to the ITS Bases. No - not in No - not in No - not in Yes LG i current TS. current TS. current TS. l [ i

 .                       CPSES Conversion Comparison Table - CTS 3N.3                                                                                                                                                         10/3&98 i

NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC) - CONTENTS I. Organization ............................................................ 3 II. Description of NSHC Eval uations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 III. Generic No Significant Hazards Considerations

                 *A"     Administrative                 Changes............................................. 6 1
                 "R"     Rel ocated Technical Speci fications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 "LG" - Less Restrictive (Moving Information Out of the Technical Speci fications) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11                                l 1

I l

                 "M" - More Restri cti ve Requirements. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13                                      i IV. Specific No Significant Hazards Considerations                                                    "LS" LS 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot Appl i cabl e LS-2.................................................................... 16 LS-3.................................................................... 18 LS - 4. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i c abl e LS 5.................................................................... 21                                                                            l L5-6.................................................................... 24 LS-7.................................................................... 26 LS - 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c abl e LS 9.................................................................... 29 LS-10................................................................... 31 LS 11................................................................... 33 LS-12...................................................................                                                                  35 LS  13...........................................................NotlUsed                                                                 37  0 2-17 LS-14...................................................................                                                                  39 LS-15...................................................................                                                                  41          ,

LS - 16 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e LS-17................................................................... 43 LS - 18 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not appl i cabl e , LS 19................................................................... 45 LS-20..............................................................Not Used LS 21................................................................... 47 LS-22................................................................... 49 LS-23................................................................... 51 LS 24................................................................... 54 LS 25...................................................... Nnt Used LS 26................................................. .ljot;Usedg.'.... 3 0 7 10 LS 27................................................................... 58 LS 28. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e LS - 29. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e (- l CPSESNo Signipcant Hazards Consideration - TS 3M.3 1 I t

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ML20196B881

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