ML20237E846

Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI

ML20237E846
Person / Time
Site:	Comanche Peak
Issue date:	08/28/1998
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20237E845	List: ML20237E843 ML20237E846
References
NUDOCS 9809010220
Download: ML20237E846 (113)

Text

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1.010SEJAND; APPLICATION 1.01 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases, 1-01-A,P ACTION 1 ACTIONS shall be that part of a Technical Specification wMeh that prescribes 1-01-A :

rc;; dial ;c;surc; rcquired Required; Actionsito be..taken under designated reconditions within"the specified,CompletionjTimes.

ACTUATION LOGIC TEST 0 An ACTUATION LOGIC TEST shall be the application of various simulated or 1-01-A actual input combinations in conjunction with each possible interlock logic state required for 0PERABILITY,of.a: logic circuit and verification of the required logic output. The ACTUATION LOGIC TEST shall, as a minimum, include a 1 32 A continuity check, ;; a inimum, of output devices.

0 1.1 2 ANAE-GG CHANNEL OPERATIONAL TEST (C0T) -3 An "f ALOC C:l^f02 L OPCTICh"L TEST Al COT shall be the injection of a 1-02-A simulated or? actual signal into the r,bmal as close to the sensor as oracHeahlit"o vaMfv OPERABILITY Affall' devices in the channel required for I

{

channel'OPEliABILITY. includir7;"Tl s Jdent: in thd chenaci,'such ai sler:5, E

i6tdl3hs,i3ispl;ys,'"'"

fdFitics: r" " "9rfr the :pecific' %

1j2j f

1 Q:f;ty1functionC:'

The COT._may_be_ performed by means of any series or

_/

0 1.1 1 l

sequenpai,_uver apping or totalfchannelfstepsGc that Inc entirc chenaci isY o.1.1 2 i

f4'sted3The ^ff," LOC C: ffCEL OPERATIO"!"L TEST COT;sna t i include adjustments. as l

e (channeLOP_ERABIL_ITguch that the setpoints are within the(; p necessary. of the required alarm, interlock and/or Trip Set equired neces_sary range dilu GLbut u y.

AXIAL FLUX DIFFERENCE (AFD)j 4 AXIAL TL"X OIITEREtiCE AFD shall be the difference in normalized flux signals

141-A ' N.

between the top and bottom halves of a four sectica an excore neutron detector, l

l CHANNEL CALIBRATION 4

I A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the 1-6 channe1Loutput2such such se that it responds within the @cie_ss.arV ccquired 130f 0 1.1 2 range and accuracy to known fa).uds!ofthe3idtmieterithat2the~chen.nel; monitors]

valucs of input.- The CHANNEL CALIBRATION shall encompass all: devices in;the channe1JreqQired for74hannel;0PERABILITT3 thd:rce pacat; the catir; channcl, including the rcquircd suchS353 f,71;r.,,;. int 61';H.~ displays, and trip

~

function;.T;regir;d t;~pcr_faEtt.Gpaificd;;;fcty functici.:(:M C.alibratio.n ofMgstrumentlchannels~with;re_sistancestemperature~detectorj(RTD) or 1 03-M i

thermocoup]els. ensorsimay.consi st' ofinglinp] acelqualitativelas sess_sent ;of_ sensor m 1.0 006 behayforJandArnalic_a]jbrationioffitheitem, a.injing; adjustable devic _es;in_the channel?E.IfigicLGD;ing.;l;nisi;1c l;MJattCasticgfred C"."?! L e

GAL 46RAHON~;helLjacj3dc.;;'inplicGrer;~colitr;tj;p.; trit 3gr [cs_,th;;;ti;;i e

5Un169TElO55I3.3iIIIUC ISCC"Ily~$53IO3.l5d.MUliS5 NCMlIE l

I 9809010220 900028 7/29/98 PDR ADOCK 05000445 1-1 P

PDR

liO?;USEAND, APPLICATION 1

I.

1 21 DEFINITIONS l

l l

LEAL @GE 3 g ontinued) b.:

Unidentified: LEAKAGE All LEAKAGE 1(exl cept R.C_P_ seal.lwater injection orileakoff)ithat;is.not I

1.dentified;LEAKAGEi i

c.

Pressure Boundary LEAKAGE LEAKAGE'.(except SG; LEAKAGE) through 'a nonisolable faultiin an'RCS component body.ipipe wall Tor.ve;ssel wal.1l a

l MASTER RELAY TEST l

h47 A MASTER RELAY TEST shall consist of be4he energizingeMen of each equir master relay and verifyingication the of OPERABILITY of each@

aste p 141-A..

relay..The RELAY TEST shall heluda a enntinuity check-or eacn l

associat uir.

ave relayfThe HASTER RELAY TEST may be performea 1 3o.4

}4

{means;of any; series:of Tequential.C.verlapping or total steps.

o a.i.1 3

~

"E"SER'S' 0F *E PUSLIC 1.IS "C"SER(S' CI " PUSLIC ;c;n; en indi;idual in a contrclicd or Uh'PIS"ICTED 112-A S ARCA. llc;.cvcr. an individual is act

---Scr of the public during any pcried in

hich the individual rc;; ivc; on occupational dc;c.

OFFSITE 00SE CALCULATI^1: "'?"JAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and

.1-IFA P,,

parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.3 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release

~

Reports required by Specifications 6.9.1.3 and 6.9.1.4.

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I crsesxark up ofcrs-1.o 1.s 7/29/98 u

IEGHUSGAWJAPPLICAIION El DEFINITIONS RATED THERMAL POWER (RTP) 1-20 BTE RATEG-THEfB%L-POWER shall be a total reactor core heat transfer rate to

s. m. # d -

the reactor coolant of 3411 Mwt.

41-A REACTOR TRIP SYSTEM (RTS) RESPONSE TIME 1-29 _The RIS REACTOR "I!' SYSTE!i RESPONSE TIME shall be the time interval from j

when the monitored parameter exceeds its RTSJtTrip sSetpoint at the channel sensor until loss of stationary gripper coil voltage. The;r.esponse:tiseimay_be; verified by v14 BAT'M.

,m I

meansfotanyTsetieslof;sequentialaverlapping, lor totalMtepsiso3that the1 entire a

te_sponseltimelisly.erifiedj l

i REPORTABI:E-EVENT l

1.30 A RC"0RTABLE ["Cl2 ;hcil bc eny cf thc;c ccaditica: ;pccificd in 10CTR50.73.

61-19A5m3d l

SHUTDOWN MARGIN (SDM) l 1-3150)I Sl4RB0WN-MARGIN shall be the instantaneous amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition assuming all rod cluster control assemblies (RCCAs) (shutdcwn and ccatrol) are fully 91-26MM.

l inserted except for the single RCCA red clu:ter c;x:bly of highest reactivity worth which is assumed to be fully withdrawn. With any_RCCAinoicapablelof!being fuMEinsetted Atheireactivity; worth iof;the3CCAi nust s.be: accounted.;forlin;the dP3N!BN!ationio_fiSDMEand l

l (NEW1 10;M00ES?l;AndEtheifuel and moderatoritemperaturestareichanged,tolhelhot m

2erolpoweri temperatures) t SITE-600NBARY ugWW I'

1.32 The SITE 000NDA"Y shell bc that linc :s shcwn in ri;;urc 5.13.

SLAVE RELAY TEST 1-33 A SLAVE RELAY TEST shall con:

f be-the energizingeti+= d aae

' ired slave relay and verifyingicetic??

PERARTITTY of eac d Q$ red' slave

~'

4141 AdH

._ m relay. The SLAVE RELAY TEST shal de@Dir,1 ;.7 a cort 1nuity check-l f associatadfequir.eMestattle actuauon oevMhe SLAvg lg c ;;;ini;1N.

1 3o.3 REtKr to!i gysne performed'by means"or anymser_2e % sequa gfa m overja o.1,1 1 e

Q3!!ta11stepys i

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CPSES Mark-up ofCTS-1.0

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7/29/98 i

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l'.0JEUSEfAN0l APPLICATION 171 DEFINITIONS 1

SOURGE-GHEEK 1.34 A 500"C: CllECK shall bc th; qu;1itative asses =cr,t of chani rcspas; wha the char.r.cl scascr is sp;xd to ; scurs ;f inre;xd r;dic;ctivity.

11-22-A,*

STAGGERED TEST BASIS 1-35 A STAGGERED TEST BASIS shall consist oft the testing ofl.one;.of,the 1-23-A '.

A tcst =hedule for n systems, subsystems, tre4tts channels or other designated components obtained by dividing the specificd test interval ints a cqual subintcrvols. =d during the interva11specified by the Surveillance Frequency.1sol.that allssystems,1 subsystems,' channels, or other_ designated ~'omponents.;are tested during~p; Surveillance Frequency c

intervals,fwhe.re..niis t_he; total number of. systems $ subsystems, channels,~orrothe.r1 designated components in the a.ssociated function.

b.

Thc testing of cac systa;;;. subsysten, train, or other dcsignated

poncr,t at the b giar,ing -f c;ch ;ubirtcrvel.

. THERMAL POWER 1-36 THERMAL POWER shall be the total core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE OPERATIO@L TEST- (TADOT) 1-37 A TADOT lli!i' ACTUAT!"O OC'.'ICC 0"C"'TIO"*L T""T shall consist of nna"Han the tTrib7lActuatina <hvice and verifying OPERABILITjYngdi.;;aJ.12devjces jn) '1411 $.

he chaJinei. ;;;h; Gle =. ;=cr:ca, q.5(;y:. ad/or trip funti=-

frequited:forjtriplagttfatfrig7deVideTOPERABILITYJ3td ricieTthc~C if"

( c.df;tTfur.ction(1.fimtmutmaygg-Agby means ~oLany. series'of 1 30 A 56G aial *toverlappingioritd_taTfcharthe)Tsteps',z';; ;r.;; _.

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CPSES Mark-up of CTS - 1.0 1-9 7/29/98 1

1

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1 CHANGE MjnBE8 HSBC DESCRIPTION 1 27 H

Not applicable to CPSES. See Conversion Comparison Table (enclosure 38).

i 1 28 LG Not applicable to CPSES. See Conversion Comparison Table (enclosure 38).

1-29 LS 3 This change revises the definition of QPTR to allow measuring QPTR with moveable incore detectors when one or more excore detector channels are inoperable. The change makes the CTS definition of QPTR consistent with ITS SR 3.2.4.2 as modified by TSTF 109.

1 30 A

nsistent with TSTF 205 30 Rev.1, the definitions a.1.1 1 g

of Channel Operational Test (C0T), Master; Relay;Testi Slave _ Relay; test _[ ];and TAD 0T are expanded to include the details of acceptable performance methodology.

Performance of these tests in a series of sequential,

/

overlapping, or total chanci steps provides the necessary

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assurance of appropriate operation of the ent# e channel.:

g relay,orZdevjg.e,^ respectively. This change also makes the i

COT. [ ] Master; Relay;TesttSlave;Re]ay;.tes.t and TADOT

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definitions consistent with the current TS and the NURE -

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1431 definition of channel calibration which already contains similar wording.

1 31 A

Definition pific plant vstafs which are defined by the plant design are deleted consistent with NUREG 1431.

The definitions contained in ITS 1.0 are intended for definitions that are necessary for the understanding of the specifications and can be generically defined for most plants. Definitions of systems that are not used in the specifications, or are specific to a particular plant (or only a few plants) are no longer defined in this section.

Where necessary, such terms are defined in the Bases for the applicable specifications.

1-32 A

The definitions of channel calibration. COT, [ ] and 0 1.1 2 TAD 0T are reworded consistent with TSTF 205 64 to clarify the phrase ' entire channel" thus reducing the potential for inconsistent interpretation of the phrase as experienced by a number of plants. Msim1]acIglariligat. ion 1sl providedifoQctyatioGogicLT,est.

1 33 A

This change revises the CTS definition of Core Alterations to delete "or manipulation" and " conservative" consistent with NUREG-1431. The words as used in the definition were redundant and deleting the words does not alter the meaning of the definition.

l CPSES Description ofChanges to CTS 1.0 6

7/29/98 l

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l INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 f

f TRAVELER #

STATUS DIFFERENCE COMMENTS l

1 l

l TSTF 19, Rev 1 Net Incorporated NA1.1 12 gg[approledQ

,,v m ory,o.ou o,

of traveler cut-TR 1.0 00(

off date.

n TSTF-30. Rcv 1 )Incorporated 1.1_ 9 TSTE;205 m.1-n

\\d 0 1.1 1 TSTF-64 Incorpor;ted M4 0 1.1 2 TSTF-SS Incorporated W

0 1.1 9 TSTF;52,lRev.1 Incorporated 1.1-13 Incorporated 0 3.6.1 6 Draft Rev 1 per 03.6.1-6 TSTF-111, Rev 1 Incorporated 1.1 5 WOC 57. Rev 1 Incorporated 1.1-6 NRC approved.

0115 15p-233

' m 74, Rev 1 Incorporated 1.1-3 0141 F 270 WOC 00, Rev 1 Incorporated 1.1 11 0 1.4 1

M267, i

1 l

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or TEST (C0T) actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of all 1.1 1

~~'

l19 deviceslinithe: channel.;requiredlforschannel OPERABILITY required inplading ;11 g y;p;nts ir._the 011 lg 0 1.1 2 ch;gn;],1;pchi;s'alors.;. intcricck;, display;. and j

trip functions rcqujicd tGerferr th 7 = ed

,=c;ns

..m.

. -.m.. w.. s.,~.,.., m r,.....

[tcps':0 that th; entire chenac];i;_tc:tcMe wt snall f;ny;;ric; ;7);qucqtiel.Loycr.1;pping;;r total chonnel g

rna reauired alarm, inuuae adJustme.nts, as necesserv-m interlock. and trip setpoints knired'for channe W r : " W n th Drcquircu i

gERABILI.

O that the setpoi j

nec_essary' nge and accura The;COTimay be; performed;by meansfof(anycse.r1.e.s pf sequentialJoverlaooinacor1 total t

anne]istepp-CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel l

with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

4 CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant operation within these limits l

is addressed in individual Specifications.

i DOSE EQUIVALENT I 131 DOSE EQUIVALENT I 131 shall be that concentration of I 131 l

(microcuries/ gram) that alone would produce the same j

thyroid dose as the quantity and isotopic mixture of I 131 I-132. I-133. I 134, and I 135 actually present. The j

thyroid dose conv9rsion factors used for this calculation l

shall be those listed in Table 2III oflTIDf14844)

RB3d l

AECB1962CCal culatiof ofiDi stance ; Factors"forIP.oWer and Test Re.actoriS1.tesE'or2thoseR1sted;inlTable:Ei7 Jot Reguhtory;Gu_jdeW109G 8eyRIENRCE197750CC""J0; Suppl Estl.;tcJertX p;;G02:212,~ Tob]Giti ed, Je;-.i ticd 00- G iuiV0lestliil l oisCI A T90p G L 11 M UC G ; C RICkC M Urdte;tlyity".$

(continued)

CPSESMark-up ofNUREG-1431ITS-1.0 1.1-2 7/29/98

Definitions 1.1 1.1 Definitions (continued)

LEAKAGE b.

Unidentified LEAKAGE (continued)

All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE:

c.

Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

A MASTFR RFPTES' shall consist of energizing MASTER RELAY TEST T

each uir master al=y and erifyina the-1.1 9 OPE f each uired:maste relay. The

,0 1.1-1 MASTER RELAY TEST sh inch i.

continuity chec of oach'assnciata%uireQlave reg

/

e_ MASTER;RELAYcTESTmay:be perfo nu oy means.of any u

serjes;otsequenti al,f oyerl appi ng. or; total; steps 2 MODE A MODE snail correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.11 with fuel in the reactor vessel.

OPERABLE -0PERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem train, component, or device to perform its specified safety function (s) are also capable of performing their rela'ed support function (s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a.

Described in Chapter 14. -Initial Test Proi; rom of

?B.PSW the FSAR; f

b.

Authorized under the provisions of 10 CFR 50.59; or c.

Otherwise approvea by the Nuclear Regulatory Commission.

(continued)

CPSESMark-up ofNUREG-1431ITS-1.0 1.1-4 7/29/98

Definitions 1.1 1.1 Definitions (continued) b.

In H0 DES 1 and 2, the fuel and moderator temperatures are changed to the r,cair.01 zero gpsp]

g.;;- dc;igr. irici hot 2zeroIpoweritemperatutes;

' ~ ' ~

~

w SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each requirgslave relay and verifying the 119 OPERABILITY of each requited slave relay. The 0 1.1 1 SLAVE RELAY TEST shall include, a; : air.imus, a continuity check of associated testable actuation devices. The1 SLAVE: RELAY;TESEmay;be? performed by meansAf;:any; series;ofjsequentialgovetlappinglot w.no

.w STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERHAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE A TAD 0T shall consist of operating the trip OPERATIONAL TEST actuating device and verifying the the OPERABILITY offallidevicesJj E the; channel.

1.1 1 required;forttjplactuating; device 0PERABILITY; 119 0-1.1 1 f-TAB 0T4 of required ir.cludjg;Mii._ gn:Og

(-

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ehennehts:gtsteth The TAD 0T shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the nece~s.sary r; quired accuracy. The]TADOTimay:,belperformed byJueens oftanKsettesIofisequentiallievetlappijitotitotal_

channe1.;gep_s; l

CPSESMark-up ofNUREG-1431ITS-1.0 1.1-6 7/19/98

CHANGE NUMBER JUSTIFICATION the requirements contained in the PTLR. Referenced methodologies for the PTLR would contain the methodology used to develop the heatup and cooldown figures, as well as the methodology for developing the a.i.i.5

[LTOP] setpoints. This change is consistent with Traveler WOC 57 ReWTSTfi23L LOdditjongthe?PTLR[defjnjtiory10cludesithelf0Ry Mit: settings 1consigentJithitheltraveler,is: change;to3TS;,Segtion;5j 5j 6.

1.1 7 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68).

1.1 8 Not: app 11 cable;to CPSES;1SeelConversi_on_Compatisonlable O'l l'9 (enclosu'ref 68); The reactor vcssel hc;d closurc bolt requirc cats for "0005 4. S and 5 arc clarified. Thc propused ch;ng; reviscs footnote b for "00:S 4 cad S to refer to "Rcquired reactor vessel hcad closure bcits fully tensioned" and note c for "00 5 is revised tc read

" Required reactor vessel head closure bcits less than fully tensioned."

The transition point bet cca ",00ES S and 5 would also be clarified as occurring when the rcquired reactor vcssci hced closure bcits cr; icss than fully tensioned. The rcquired numbcr of closure bcits, which may bc less than the total numbcr is catablished by analysis that d : castrates adcquate 0 ring compression to prcvent ic;kage and castfees that ASti Section III strcss limits for affected ccapcacnts are not exceeded. This chang; is consistcnt with TSTI 00.

1.1 9 C

1 stent with TSTF 205?20 Rcv.1. tne definitions of Channel 0'l'I'l

\\

perational Test (C0T),daster; Relay;Te.st;iSlaveiRelay Test l []

and Trip Actuating Device Operational Test (TAD 0T) are expanded to include the details of acceptable performance methodology.

Performance of these tests in a series of sequential, overlapping, or total channci steps provides the necessary assurance of appropriate operation of the ent4re channel, relay;oridevicel1respectively. This change also makes the COT, Mastert elay, Test 2SlavejelayJest; and R

TADOT definitions consistent with the definition of channel cal atTbn which already contains similar wording.

l 1.1 10 Not applicable to CPSES. See conversion comparison table (enclosure 68).

1.1 11 Adds new example to ITS Section 1.4 to clarify surveillance frequencies that are contingent on both a specified frequency and plant conditions.

i The ITS contains many Surveillance Frequencies that are contingent on

{

both a "specified Frequency" and plant conditions. For example. "Within 7 days prior to the initiation of Physics Tests," and " Prior to entering H00E 4 from H00E 5 if not performed within the previous 92 days." These Frequencies do not fall clearly under any of the existing Section 1.4 examples. The proposed example is needed to make clear that 1) the SR 3.0.2 extension of 1.25 times the specified frequency applies to the specified Frequency, and 2) that the interval allowed to perform a missed Surveillance by SR 3.0.3 applies.

SR 3.0.2 is clear that the 1.25 extension may be applied to "the interval specified in the frequency", so the proposed change does not l-CPSES Differencesfrom NUREG-1431 -ITS 1.0 2

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i-

l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-2 APPLICABILITY: CA, CP, DC, WC REQUEST:

CTS 1.3, Analog Channel Operations Test CTS 1.5, Channel Calibration CTS 1.35, Trip Actuating Device Operational Test (Wolf Creek)

CTS 1.36, Trip Actuating Device Operational Test (Callaway]

CTS 1.37, Trip Actuating Device Operational Test (Comanche Peak]

CTS 1.38, Trip Actuating Device Operational Test (Diablo Canyon)

DOC 1-32-A ITS 1.1, Channel Calibration ITS 1.1, Channel Operational Test (COT)

ITS 1.1, Trip Actuating Device Operational Test (TADOT)

JFD 1.1-1 These are changes to both the CTS and the STS and are considered generic changes.

Therefore, they are beyond the scope of the conversion review. The DOC states that these changes are consistent with TSTF-64.

Comment: If NRC has not approved TSTF-64 by the time the draft safety evaluation is prepared, then these changes should be withdrawn from the conversion submittal at that time.

These changes will not be reviewed on a plant-specific basis.

FLOG RESPONSE: TSTF-64 has been withdrawn by the TSTF. However, changes addressed in TSTF-64 have been subsumed by TSTF-205. Revision 1 of TSTF-205 is currently undergoing final review by the TSTF members. After final wording changes for the COT definition as well as Section 3.3 Bases changes to establish the requirements for relay contact surveillance testing (issue originally raised at Peach Bottom) are agreed upon, Revision 1 will be submitted for NRC review. The attached pages represent the definition changes to be included in Revision 1. The Section 3.3 Bases changes will be addressed under that Section's review.

ATTACHED PAGES:

l I

Enct 2 1-1,1-2 and 1-9 j

Enci 3A 6

Enci 38 4

EnclSA Traveler Sheet, 1.1-1,1.1-2, and 1.1-6 l

Encl 6A 1

l Encl 6B 1

i i

i

l l

1;010SEfAfDi, APPLICATION j

1 1.01 DEFINITIONS f

\\

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

~ ~ ~ ~

H43.M!<.

l ACTION M ACTIONS shall be that part of a Technical Specification wheh,that prescribes rc;cdial sc::urcs rcquired RequiredActionsito_beltaken under designated 141-C.

l eCondi tions ytthinitl4speci fled;Compl.etionJTimes.

ACTUATION LOGIC TEST

)

M An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinaHnns in conjunction wi+h Ph possible interlock logic 141-A l

stateceau1 red for OPERABILITY of,a logic 'circu and verification of the i

required logic output. The Au uAi sa LGGh, it T all as a minimum, include a 1 32 A continuity check, a; ; minimu;. of output devices.

0 1.1 2 ANAEGG CHANNEL OPERATIONAL TEST (C0T)-

M An ft" LOC ClL*f$ L OPEP^TIONAL TEST AiCOT shall be the injection of a a

142-A X simulated orJactual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices;fn the;channellrequired for i

chagnel10PERAB.ILITY; i_ncludin ;" gcapciqstsj;; the chen ci, uch c alcras, 1-30 A interlock:, displ.cy:, :nd/or trip function; igquired to perfo%th; pccifjcd 1 32 A sofgty?;ngjog's'. The COT may_be; performed by;means.of.'any series _of a.1.1 1 j

segue.ntia]Eov~erlapping or.itotalichannetsteps3c that thc Antire cM.ncLis a.1.1-2 tested 3 The "fi^ LOC C:L'""" OPEP^TIO'L*L TEST COT!shall include adjustments. as necessiry, of tbdgehalarm, interlock add /or Trio Setpointsfr,equjred for 2

change]10RERABILITrjsuch that the setpoints are within the rcquired necessary range and accu y AXIAL FLUX DIFFERENCE CAFD)]

1-4 AXIAL TLUX OIffEPsE"CC AFD shall be the difference in normalized flux signals between the top and bottom hHves of a four ;cction an excore neutron detector.

.#dDd CHANNEL CALIBRATION l

l M A CHANNEL CAI N" shall be the adjustment, as necessarv. of the _

1 32 A channelpemej$Uch such 8t

e. it mnonds within theJiergssad required;,v to known djijles3f.M-wyr. natal)EtLitatjnglia'ojnitors.

tutr a.1.1 2 ranae an saluc: cf input. The CHANNEL CALIBRATION shall encompass a])idevice,s i.ngh,e chajih61Re!LUfrRQopsh&nhelHOPERAB111111] G7MM.,;;;the catirc -henndy i

I includin-the rcquired ;c_hl:3ca cr, cler;4, intcricck, dispicy1 :nd "r4 dnction;.T Mired tC;c.-fr^2.C:2 ifiF" ^r'-r-tic;i-Pnftaljbr.ation offnstrumentscha_nneisswun: resisjiameJegperature; detect;orAK. uEor 1 03 M thento@uplgjensprs3anonsistIgDat1MnD1ateTqualitattveJssessj!!egtjLhsen_sor TR-1.0-006 be_hpigfa@JLiornali_caMbratWJ!G1hel_e_ggLn]DEadju_st_ab10dey1,ce.s3,1njthe y,.. _,_

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CPSES Mark-up of CTS - 1.0 1-1 7/29/98 L

II020SE AND APPLICATION 1

l 1~1 DEFINITIONS 132 A The CHANNEL CALIBRATION end may be performed by meanslofjany series of Q 1.1 2 sequenti_al, overlapping c;'jbrat'cri, or total channel steps ich that the erstir^

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CHANNEL CHECK

-h6 A CHANNEL CHECK shall be the qualitative assessment,1bylobservation; of channel behavior during operation by observaticri. This determination shall

$ 1-01-A include, where possible, comparison of the channel indication andhe status to wMh-other indications end/or status derived from independent instrument channels measuring the same parameter.

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CPSES Mark-up of CTS-1.0 1-2 7/29/98

1E020SE@iD; APP,LICATION 111 DEFINITIONS SOURGE-G4EEK 1.M A SOU"C" CliEC" 3 Mil be the qu litativc assess: cat of chanci rcspcasc when m122-A1.,,.

tk donaci scr.scr is aposcd to ; source of increased radica-tivity.

STAGGERED TEST BASIS 1-35 A STAGGERED TEST BASIS shall consist oft the testing of one of the 1-23-A A tcst sckdult for a systems, subsystems, teams channels, or other a.

designated components obtair.cd by dividir.; the spccificd test interval ir,t; a cqual subintervals, and during the intervalf specified by the Surveillance Frequencydso,that all systems,; subsystems.' channels, or other; designated l components are. tested during n, Surveillance Frequency intervals, where niis;the; total number of systems,7 subsystems; i

f channels, or otherldesignated components in the associated function.

l I

b.

Thc testing of cac systca, subystem. train, or othcr dcsignated cc,vspcacnt at the beginning of cach subinterve.l.

THERMAL POWER 1-36 THEPJiAL POWER shall be the total core heat transfer rate to the reacto:'

coolant.

TRIP ACTUATING DEyICE OPERATIONAL TEST (TAD 0D A TADOT T"I" AC"JATINC OE" ICE 0"E""TIO""L TEST shall consist of operating

...m 1-37

~

' l-41-AM the tTrip ah5tuating dBevice and verifying OPERABILITY;cf inclMit.g all devices,in t M Channe17, M IG G lor s.. iTitCrl^<d",. dicpic2-Ond/cr trip functicis requj tedlott. tiplactpating ide@eRERABILIUdtGgf.ct;,;K::pGjffsd

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l 1

CPSES Mark-up ofCTS - 1.0 1-9 7/29/98 j

2

. CHANGE l-NUMBER NSHQ DESCRIPTION t

1 27 H

Not applicable to CPSES. See Conversion Comparison Table (enclosure 38).

1 28 LG Not applicable to CPSES. See Conversion Comparison Table (enclosure 38).

1 29 LS 3 This change revises the definition of QPTR to allow measuring QPTR with moveable incore detectors when one or more excore detector channels are inoperable. The change makes the CTS definition of QPTR consistent with ITS SR 3.2.4.2 as modified by TSTF 109.

1 30 A

Consistent with TSTF 205 30 Rev.1. the definitions o.1,1 1 of Channel Operational Test (C0T), Master _RelayjT.est; Slave:Relayitestj[ ]land TAD 0T are expanded to include the details of acceptable performance methodology.

Performance of these tests in a series of sequential, overlapping, or total cha-el steps provides the necessary assurance of appropriate operation of the ent4re channel; relay:otdevicel respectively. This change also makes the COT. [ ] HasteriRelayJTest;;S1 ave:Relayi est and TAD 0T t

definitions co.1tistant with the current TS and the NUREG-1431 definitir..t of channel calibration which already contains similar wording.

1-31 A

Definitions of specific plant systess which are defined by the plant design are deleted consistent with NUREG 1431.

The definitions contained in ITS 1.0 are intended for definitions that are necessary for the understanding of the specifications and can be generically defined for most plants. Definitions of systems that are not used in the specifications, or are specific to a particular plant (or only a few plants) are no longer defined in this section.

Where necessary, such terms are defined in the Bases for the applicable specifications.

1 32 A

e definitions of channel calibration, COT, [ ] and l 0 1.1 2 TADOT are reworded consistent with TSTF 205 64 to l

clarify the phrase ' entire channel" thus reducing the potential for inconsistent interpretation of the phrase as experienced by a number of plants. OsimilariclatificatioD sprovi.dedifotMctuationitogicITest.

1 33 A

This change revises the CTS definition of Core Alterations I

to delete "or manipulation" and " conservative" consistent I

with NUREG 1431. The words as used in the definition were redundant and deleting the words does not alter the meaning of the definition.

CPSES Description of Changes to CTS 1.0 6

7/29/98

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N 1 M 1 L 1 L 1 A 1 A 1 A 1 A 1!

r INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 TRAVELER #

STATUS DIFFERENCE COMMENTS N

I TSTF 19, Rev 1 Net Incorporated NA121f12 NRCJppfoj_d-]

e Not appr;ved as of travelcr cut-l TR 1.0 00(

Off datG.

TSTi-30. Rev i Incorporated 1.1 9 TSTFf205 L1-1 0 1.1 1

~

'TSTT-54 Incorporated -l-1 Q 1.1 2 J

l TSTT SS Incorporated 14 0 1.1-9 TSTF-52,'_Rev 1 Incorporated 1.1-13 Incorporated a 3.6.1 6 Draft Rev.1 per Q3.6.-1-6 TSTF 111, Rev 1 Incorporated 1.1 5

'400 57. Rcv 1 Incorporated 1.1 6 NRC approyed..

TSTE;233 0-1.1-5

'400-74. Rev 1 Incorporated 1.1-3 2

0 1.4 1 TWJ270

'400-00. Rev 1 Incorporated 1.1-11 0 1.4 1 TSTE72E b

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Ier.m Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to L? taken under designated Conditions within specified Completion Times.

3 ACTUATION LOGIC TEST ACTUATION LOGIC TEST shall be the application of i

various simulated or actual input combinations in 1.1-1

\\

0 1.1 2 conjunction with each possible interlock logic state required for._0PERABILITY_ of a legic: circuit and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a Ha"4 +y ^^c ;f ;;tpu+ davices.

AXIAL FLUX DIFFERENCE AFD shall be the difference in norma'iized flux B-PS-(AFD) signals between the top.and bottom halves.of e tw; ;;; tion an excore neutron detector.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as output _suc hat it 1.1-1 essaryis.;d}h necessary, of the chan ange and 0 1.1 2 responds within th s

ac to kn aTuesiof;.use.yai o-ai.Er-that -t annetsonyor u

LHANNLL LALItiMAl1VN Jieli c-puds 3..r t.Nmllidevfcesjinithe' channel required.for channell0PERMILIW tig;;;,~;,, rere.tL the entir; chenaci.

46cluding the required ;gg!L3E;;n;;r;. ;1 era;. intcried"r I di; play;. ;nd trip function;.~l;6Mirt"~ r 'r:

p;sfi;d!J;'itTfenct4;g; calibration of instrument

. 9 "4+' r;;tt rc: L.gerature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the 1.1 12 channel. 'Jh;nc;;r ; ;;n;ing cl;;; cat i; repl;;;d. th; TR-1,0-006 next r;;uired C".'f5L C'LI"","TIO': ; hall includ; en l

l inplecc cre;; ;;libration that c,,;;.p;rc; the other

ing

1; rent;.;ith the r;;;ntly in;tell;d ;;n;ing i

ci;;;.;t. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping 1,1 1 c;libration?qr total channel steps c that the ;n' Q 1.1 2 cher..el i; ;;l;;r;;cc.1

/~

(continued)

CPSESMark-up ofNUREG.14.11ITS-1.0 1.1-1 7D988

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL A COT shall be the injection of a simulated or TEST (C0T) actual signal into the channel as close to the

- ~

sensor as practicable to verify the OPERABILITY of/alh 1.1 1 vices: in. tne. cnannel;requi rea. Ior enannel 119 0 1.1 1 OPERABILITY] r; quired in;]udjn; M ];;,,;i~a;; ir ;p;

.u

1. 1*I m ~ w-.mp - ~, - ~m. - ' w m u. -

i trip furetiens r; quired t; ;;rfc.-rtte r;;ified t(:;f;ty'furationN ETre COT ;;;;y b;. p;igir;d.by==:

. nyEE1;;3fJ;;;;;?i;l. G;-liPPt;;R t;t;li;I4ai~l

t?PO;ittet2.intiE L;P.;nr~lij..tated. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required;forichannel.

OPERABILITysothatthesetpointsarewithinther; quired necM ary; range and accuracy. The COTimay be per, formed;by means. off any ;serj es,. of;sequenti al. loverl appi.ng ;or total channelJtepsf CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle. specific parameter limits shall be (ietermined for each reload cycle in accordance with Specification 5.6.5.

Plan: operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I 131 shall be that concentration of I 131 (microcuries/ gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131, I 132. I-133,1-134, and I 135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Tab]e3IIIrofiTIDf148H) 133 AECT1962 E"Cah:ul ationiofj Distarplactors ;.f.or;.PowerZand Test 1teactot Sites',por;thoseHistedtin TablelE;770f Regulatory;Guidell';l1092 Rey;E1,1NRCE1977s

,.~,.

SUPPL---A.t;7;Et 1,~?P;9;1192i212,3ebl;1 tit];d,J~. itted 0;;;J4;iV;loniliEl;Esot.?E9;EE;Oj;;;G;Got3;i;I MIEb^-$51I$2 (continued)

CPSESMark-up ofNUREG-131ITS-1.0 1.1-2 72 9/98 l

Definitions 1.1 1.1 Definitions (continued) b.

In MODES 1 and 2, the fuel and moderator temperatures are changed to the r,c;;;ir.cl zcrc

B}P"S9]

.;cr dc-igr. i=1 hot;z to;powerftemperatures!

^~

e g

SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each requiredjslave relay and verifying the 1.1 9 OPERABILITY of each requjred slave relay. The 0 1.1 1 SLAVE RELAY TEST shall includc. ; a r.ir.ir.,u;;; a continuity check of associated testable actuation devices. The SLAVE:RELAYiTEST~may;be performedlby means:ofiany,serj esiof_sequentialgoverlapping.or total; steps:

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist cf the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or otner designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TRIP ACTUATING DEVICE A TADOT shall consist of operating t trip OPERATIONAL TEST actuating device and verifying t-he OPERABILITYjgEaRdevices2 nJne_ channel 1.1 1 1

119 u mm ;triplactuating;deyice' 0PERABILITY; r

g(TADOT) of required 1.c'_,Mi_g;;;U3, ygg..;Afg 0111 0-1.1 2 u_-_u_

_.._e m __

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I!'s?"'MY I?r"2"I'_"R l'_'2',IT21__

m-i

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". ~

m N 5 5 55"'. n n ~"'(. a u.u~h d 5 N s $ N d 5 5 N b b,__

25ES hE 5 mu-vv.m u

~.v. n ~m-m m am ehenne'JJ ;tcit-d.: The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the nec,essary requircd accuracy. TheHADOTimay; be: performed; byiseans ofJgylseries;o,fisequentialgoverlappjpgipritatal, changelgtepst l

CPSESMark-up ofNUREG-1431ITS-1.0 1.1-6 72 9/98

JUSTIFICATIONS FOR DIFFERENCES FROM NUREG 1431 Section 1.0 This enclosure contains a brief discussion / 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 /NRC generic change process. The change

)

numbers are referenced directly from the NUREG 1431 mark ups. For enclosures 3A, 3B, I

4, 6A and 68, text in brackets "[ ]" indicates the information is plant specific and l

4 1s 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, l

CHANGE NUMBER JUSTIFICATION 1.1-1 NUREG-1431 Rev. I definitions of Channel Calibration?

ChanneE0perationa]i[est and1 Trip; Actuating,Devjce10perational 0 1.1 2 Test use;1anguage~tojdescribe;theiscope;of,testingisjmilat: toy

tetes. "The C".'"!!CL CAL

0 RATIO" shell ;ncap;s "the entire channel, including the required sensor, alarm, interlock, display, and trip functions". TheLword

" required"Jis;ambjguous~and;subjectito misinterpretation:as;to)hethet thelistiisiinchsivelo_r; representative; JThis change clarifies what compone_ntsiareijncludedfbyispecifying "allldevicesiinithe; channel required 1forichanne1 OPERABILITY"Msimil aric]arification 3siptovided forJhe:ActuatjonitogiciTestgj encap::c; the intira chenrel by rewording the definition t; stete. "The C".'?:!!CL CAL:0 RAT!0" ; hell enc q ;;; th;;c c + rent;, ;uch ;; ;ca;;rs, ler;;. di; ploys. nd trip furetiens. required te prfer; the spcified safety furetien(s)." The Ch;naci Og retienel Test ;nd Trip Actu; ting OcVic; Og retienel Tc:t definition; ;rc similarly rcvi:cd. This change is consistent with 205E64-1.1 2 Not used.

1.13 Adds new example to ITS 1.4 to clarify meaning of SR notes of the type "Only required to be performed in MODE..."

This O'l 4'l change is consistent with traveler "00 74. Scv i ISTFI270..

l 1.1-4 Not used.

1.1-5 The definitions for ESF Response Time and RTS Response Time would be revised to substitute the word " verified" in lieu of " measured" consistent with the requirements of NUREG 1431 SR 3.3.1.16 and SR 3.3.2.10. This change would ensure consistency between the definitions for Response Time and the requirements to periodically verify Response Time is within limits. This change is consistent with TSTF-ill, Rev 1.

a 1.1-6 The definition of the Pressure and Temperature Limits Report would be revised to include the maximum allowable PORV lift settings and arming temperature associated with the [ Low Temperature Overpressurization i

Protection (LTOP)] System, and to be consistent with the COLR de'inition. Improved Technical Specification 3.4.12 states that the CPSES Diferencesfrom NUREG-1431 -ITS 1.0 1

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ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-3 APPLICABILITY: CA, CP, WC REQUEST:

CTS 1.9, Core Alteration DOC 1-06-LS The DOC does not provide adequate technical justification to support this change.

Comment: The associated NSHC for this change appears to provide the necessary justification. Revise the DOC by incorporating the information contained in the associated NSHC.

FLOG Response: Additional information supporting this DOC is in NSHC LS-1 in Enclosure 4.

DOC 1-06-LS-1 is revised to include the following information:

"The proposed revision more explicitly defines those operations that have a potential for adding positive reactivity to the core and excluding from the definition the use of "non-core" components (such as cameras, lights, etc.) that would not significantly alter core reactivity.

This would allow movement of other components within the reactor vessel (with fuel in the vessel) that would have no effect on core reactivity. The proposed change would continue to maintain the required level of safety while eliminating unnecessary restrictions on the movement of items such as cameras, etc. The proposed change would continue to allow the l

application of appropriate limits to the movement of components that could affect core reactivity."

For WCGS, Amendment No.109 dated September 18,1997 revised the CTS CORE ALTERATION definition (1.9) to the wording in NUREG-1431, Rev.1. Therefore, DOC 1 LS-1 and DOC 1-33-A are no longer applicable to WCGS.

f l

ATTACHED PAGES:

l I

Encl.3A 2

I I

)

)

{

lL

i CHANGE NUMBER HSliC DESCRIPTION 1 06 LS 1 The current TS definition for Core Alterations would be modified consistent with NUREG 1431, to qualify a core alteration as movement of fuel, sources, or other reactivity control components. This I.roposed change is less restrictive since the current TS definition defines the movement of any component within the reac vessel with fuel in the vessel as a ente Alteratio. The 0113

. _ sedlevision_ pre; explicit]yicennesjthose operatiops2thatihayeja;potentialifocaddjngAsitiye rea,gtiyj ty2tq:thelcorelandlexcludingif_ rom;the;;defj nition the;us_e;offnonicore"icomponents1(such'as camerasE]jghts; etc;)1thatiwould,,notisj gni ficant]yia]tericoreZreagtivity0 This;woul d :all owinovementfof;other; components' with.in:the reactor;yessel3with_fue1Jn thelvesse]1thatlwouldihave:no effect;onicoreleactivity.;;Thefproposed; change:would continueito maintain 3he, required 21 eve]ioffsafetyyhile eliminatingiunnecessaryfestrictjon.slonithe;movementrof items ^suchias_,camerasZetc.2The;proposedlchangeyould continue,to3110w theiapplicationloCappropriateI]jeits' a

the moyementioficomponentsithaticould affect

• ara me proposed definition would r.eactivity? hc[c@ ions to those manipulations that could c

core alterat affect core reactivity, the proposed change is acceptable from the standpoint of the health and safety of the public.

1 07 A

Not applicable to CPSES. See Corversion Comparison Table (enclosure 38).

1 08 A

The current TS definitions for Engineered Safety Features Response Time and Reactor Trip System Response Time would be modified to be consistent with NUREG 1431. In addition, the term " measured" would be replaced by

• verified" to be consistent with the requirements of improved TS SR 3.3.1.16 and SR 3.3.2.10 to verify response time is within limits. The addition of the statement that i

response time may be verified by means of any series of l

sequential, overlapping, or total steps so that the entire l

response time is verified, is administrative in nature.

This is consistent with the methodology presently described i

in the current TS Bases for demonstrating total channel response time.

1 09 A

The current TS definition for Frequency Notation (and Table 1.1, Frequency Notation) would be deleted to be consistent with NUREG-1431. The acronyms defined in Table 1.1, Frequency Notation, are no longer used in NUREG 1431.

Surveillance frequencies are spelled out in NUREG-1431,

)

thereby obviating the definition. This is a non technical change made to conform to NUREG 1431.

l CPSES Description of Changes to CTS 1.0 7/29/98 i

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-4 APPLICABILITY: CA, CP, DC, WC REQUEST:

CTS 1.13, Engineered Safety Features Response Time [Diablo Canyon, Wolf Creek, and Callaway]

CTS 1.14, Engineered Safety Features Response Time [ Comanche Peak]

CTS 1.27, Reactor Trip System Response Time [ Wolf Creek and Callaway)

CTS 1.29, Reactor Trip System Response Time [Diablo Canyon and Comanche Peak)

DOC 1-08-A ITS 1.1, Engineered Safety Feature (ESF) Response Time ITS 1.1, Reactor Trip Syctem (RTS) Response Time JFD 1.1-5 The definitions for ESF Response Time and RTS Response Time are proposed to be revised to substitute the word " verified" in lieu of " measured." The JFD states that this change is made to be consistent with STS SR 3.3.1.6, SR 3.3.2.10, and TSTF-111, Rev.1. However, the DOC does not refer to TSTF-111 applicability for this change.

Comment: If NRC has not approved TSTF-111 by the time the draft safety evaluation is prepared, then this change should be withdrawn from the conversion submittal at that time.

This change will not be reviewed on a plant-specific basis. Also, revise the DOC to include TSTF-111 applicability.

FLOG RESPONSE: The response to Comment Number 1.1-4 will be provided separately after the August 17,1998 NRC letter to NEl on TSTF-111 has been fully evaluated.

ATTACHED PAGES:

None l

l l

l c___________________.________..____

m

I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-5 APPLICABILITY: CA, CP, DC, WC REQUEST:

DOC 1-17-A l

ITS 1.1, Pressure and Temperature Limits Report (PTLR)

JFD 1.1-6 The definition of Pressure and Temperature Limits Report (PTLR) is added to be consistent with STS. While this is acceptable, the changes to both CTS and ITS to include the maximum allowable PORV lift settings, arming temperature associated with the cold overpressure mitigation system (COMS) [for Callaway only), and arming temperature associated with low temperature overpressurization protection (LTOP)[for Comanche Peak and Wolf Creek] are generic and are beyond the scope of the conversion review. JFD 1.1-6 states that these changes are consistent with traveler WOG-67, Rev.1.

Comment: Provide the current status of WOG-67. If WOG-67 is not approved by the TSTF, then this change should be withdrawn from the conversion submittal at the time of the TSTF rejection. If WOG-67 has not been acted upon by TSTF, or has been approved by the TSTF, but not been approved by the NRC at the time the draft safety evaluation is prepared, then this change should be withdrawn from the conversion submittal. This change will not be reviewed on a plant-specific basis.

FLOG Response: WOG-67, Rev.1 has been designated TSTF-233 and was issued to the NRC by NEl on March 10,1998. The latest status report from the TSTF industry database, dated July 27,1998, indicates that the NRC has approved TSTF-233. The proposed wording in TSTF-233 was modified from WOG-67 and these modifications have been incorporated into the ITS. In addition, the PTLR definition includes the PORV lift settings consistent with the traveler's change to ITS Section 5.5.6. The FLOG continues to pursue the changes proposed by this traveler.

ATTACHED PAGES:

Encl 2 1-7 l

Enci 3A 3

l EnclSA Traveler Page and 1.1-5 Encl 6A 2

W

I l

i l

(

l liOI USE( M APPLICATION E4 DEFINITI0tG M

1.25 The ""0 CESS C0l,""0L ""00.J." ("C") sbil sat;in the current ferales.

..m n;pling, := lyses, tests. and iter;inetiens t; k =i t; asurc that preussing a 146-LG d ad pechging of 3; lid radi;;ctive westas ksed en i;;nstretcd ;recaning ;f actu;T cr si uietad wet sciid unta will M cue piiskd in suci ; w;y n t; nsure s pli = x with 10 Cr", 20, 51, ad 71. St;te rcgul;tions, kriel ground requir;xats. =d ;thcr rcquircants governing the disp;s;l of solid r;dioxtive wester PURGE--PURGING 1.25

"=0 er "=0!l0 abli k my cerfr:11cd precess ;f discharging air er 9: 3 fre; ; confin;n at t; =intain to. gr;ture, pressurc. humidity, cacentrati;n er

/1-15-A. S '

ethcr opc ; ting conditien, in such ; = nacr th;t rcpi x emcat ;ir er g;s is required t; purify thc confix x at.

(NEW)1PRESSEE_AND_TEMPERABEE_LIlflILBEE(EE (PILR)

TheJTLR;isithe:unitispecific; document 2that provides;the; reactor;vesseEpressureland temperAturetljaitsMncluding:hea

~

Jcooldown; rat.es Lthe:powerloperat.edi relief VaMtPORVTilift? settings [a.

_ p ina temperature;associatedlw1_th Low l.

Temperature 10verpressur_izationiProtection;(LT3OPy m,7f " the currentireactot l

VespeMRuence periodRTheselpressurelanditemperaturellimitsis a _

determined 1for'eachfuenceiperioddn accordance:isith the Administrative ContrrasTsection? 2Un t' operation w thin 4hese~ecerating;11mitrisladdrossedli _.

1 17.g f ud.dZhMei U;;I' ei.e 100 c3)b U Uipfressure ;and Jesperature; (PO o.1.1 5 L1NR$1*d,and1 col 3 ~.612 Glow 1TemperatureMerpryssure_ Protection [(LTOP)

%83Wir l

OUADRANT POWER TILT RATIO 1-27 QUADRANT' POWER TILT RATIO shall be the ratio of the maximum upper half excore.... M IN

(

detector calibrated output to the average of the upper half excore detector calibrated outputs, or the ratio of the maximum lower half excore detector j

calibrated output to the average of the lower half excore detector calibrated outputs, whichever is greater. With one excore detector inoperable and power s 75% of RTP. the remaining three detectors shall be used for computing the average, j

t

!~

With onetexcore detector inoperable and power above 75% RTP or:WithimotettharCone

!ieuMi I

I f

iltdperablemre detectot, the movable incore detectors shall be used to determine quadrant power and average power based on the relationship between incore and excore power using the most recent flux maps.

4 CPSESMark-up ofCTS-1.0 1-7 7/29/98 L

3

CHANGE

{

NUMBER EiliG DESCRIPTION which leakage is accounted for and treated from present practice. The definition of unidentified leakage has been expanded to include "except RCP seal water [ injection or]

leakoff". to be consistent with NUREG-1431.

1 12 A

The current TS definition for Member of the Public, would be deleted to be consistent with NUREG 1431. This definition would be deleted on the basis that it is defined in 10 CFR 20.1003 and 40 CFR 190.

1 13 A

The current TS definition of the Offsite Dose Calculation Manual (0DCM) [ ] would be [ ] incorporated into the Administrative Controls section of the ITS. This change is non technical because the definition of the ODCH [ ] will be [ ] moved to another section of the improved TS.

1 14 A

The current TS definition for Operational Mode would be revised to " Mode" and the wording would be revised to be consistent with NUREG 1431. The changes are nontechnical since they will not affect current practice.

1 15 A

The current TS definitions of HVAC.' processes systc;;;s 0 1.1 7 and functions would be deleted to be consistent with NUREG 1431. [ ] " Purge - Purging" and " Venting". where used. do not require special definitions. These 0 1.1-6 definitionslar_eldeleted;sincelthe CTS! referring 1to,;the definitions;nollonge.ricontain ;thei r.. use. dor;noj onger areiretainedinitheRS^.71 Discussion;oRtheltechnical aspectstof2 thi s" change:areladdressed;inie.agh1TS;whereithey appM 1 16 LG The current TS definition of the Process Controls Program (PCP) would be moved outside of the TS along with the Administrative Controls description of this program to be consistent with NUREG 1431. The PCP definition and program description from Administrative Controls are moved into the FSAR. The PCP implements regulatory requirements and need not be restated in the TS. The requirement to comply with applicable Federal and State regulations for the processing of radioactive waste provides sufficient control of future changes to the PCP.

i 1-17 A

The definition of a Pressure Temperature Limits Report (PTLRpnnu ha added to be_ Consistent with MIRFG 1431 0 1.1 5 a

-57. ",c; 1 TSTE233; In~ addition &the"PJLR deffq1tjon]ncludeGthe:PORVHiftisettingsconsistent "theTtraveler M ehangelto IISlSeption;5._S;6.

ie definition will support tne un of a "TLR ing the n

definition is purely administrative in nature.

CPSES Description of Changes to CTS 1.0.

3 7/29/98

l

)

INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 TRAVELER #

STATUS DIFFERENCE COMMENTS NRCrpp:rbvedel_

TSTF 19. Rev 1 Net Incorporated NAlfI 12 a

o r ~_ _ _==r

.a nww vyys v v wu u of trGVCler cut-TR 1.0 00(

off date.

TSTr-20. Rcv 1 Incorporated 1.1 9 TSTFi205 lgf1 0 1.1 1 TSTr 54 In:crporated M -1 Ml 0-1.1 2 TSTr SS Incorporated 1-8 l01.19 TSTF-52, Rev 1 Incorporated 1.1-13 Incorporated 0 3'6'1 6 Draft Rev.1 per Q3.6.1-6 TSTF 111. Rev 1 Incorporated 1.1-5 f40-57. Rev 1 Incorporated 1.16 ] NRC approved.,

([IE233 0 1.1 s 2

TS

'4C 74. Rev i Incorporated 1.1 3 0141 E 2?0

'4C 00. Rev 1 Incorporated 1.1 11 0 1.4 1 l

lbitj26Z

?

Definitions L1 1.1 Definitions (continued)

PRESSURE AND The PTLR is the unit specific document that TEMPERAlljRE LIMITS provides the reactor vessel pressure and REPORT (PTLR) temperature limits, including heatup and cooldown rates. 3helpDwer_aperatedgelleggMMXIgN);4j ft

[1 $ g e

settings;andglie.5.t argiggiteppstatgrplipgsogjated with;the! Low n _._ureloverpr!Ls_surtz gion; Protection (LIOPZ)ystem, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6.

Plant operation within thoco _7_r: ting limits is addressed inqLTLetvidu@

E = ;171;;".107.;.1 00 3.4.3, ""CS "r:3_

Teagre:gr ir/:) Li;it3," and LC0 3.4.12. " Low t-1-6 T;;gr;tu Scrr, ::urc "retection (LT0'"

0 1.1 5 Su-t

"'.00;3.4J3,3"RCS, Pressure;and;Temperat.ure P/T)Rimits;"fand:LC0;3.4;12 M Low; Temperature Overpressure frotection (LT_0P);Sys. tem;"

QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper RATIO (QPTR) excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the 1

ratio of the maximum lower excore detector calibrated I

output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of-2893 3411 MWt.

LBfPSM REACTOR TRIP The RTS RESPONSE TIME shall be that time interval SYSTEM (RTS) RESPONSE from when the monitored parameter exceeds its RTS TIME trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be ;;;sur d verjfled by means of any series of sequential, overlapping, or total steps so that the e171g5j entireresponsetimeis;;;suredigiff;j.

SHUTDOWN MARGIN (SDM)

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a.

All rod cluster control assemblies (RCCAs) are i

fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDH: and 1

b.

In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal Icre lB-PSM Fw r design icyc1 hotizerolpoweritemperato_res]

J 1

CPSESMark-up ofNUREG-131ITS-1.0 1.1-5 7/19/98

CHANGE NUMBER JUSTIFICATION l

th quirements contained in the PTLR. Referenced methodologies for e PTLR would contain the methodology used to develop the heatup and cooldown figures, as well.as the methodology for developing the l

o.1,i.5

[LTOP] setpoints. This change is consistent with Traveler WOC 57, RewtTSIE233. IXadditjongtheLPILRideflattlo[1pludesithe: PORV 4

11fMsettings' consistent TwitKtheitravelerj sichangelto2ITS!Section~5W 1.1 7 Not applicable to CPSES. See Conversion Comparison Table (enclosure 6B).

1.1 8 Not; applicable;tolCPSES.ESee; Conversion;ComparisoniTable 0 1.1 9 (enclosure:6B)] The reactor vessci head closurc belt rcquirsats for M00ES 4. 5 and 5 arc clarified. The proposed changc reviscs footacte b for M00CS 4 and 5 to refer to " Required reactor vessel hcad closure bcits fully tensioned" and note c for M00: 5 is revised to read

" Required reactor vessel head closurc bcits less than fully tensioned."

The transition point batuna MODES 5 and 5 would also be clarified as occurring when the required rcactor vcssci head closure bcits arc less than fully tcasioncd. The required number of closure bcits, which may bc less than the total number, is established by analysis that d = castrate:

';quate 0 ring cocprcssion tc picvcat icakag; =d casures that ASME Section III stress limits for affected componcats orc not excccded. This ch agc is ccasistent with TSTF 08.

1.1 9 Consistent with TSTF 205'00 Rcv.1, the definitions of Channel Operational Test (C0T),[AasterLRelay:TestESlayelRelay: Test,' []

0'l l'1 and Trip Actuating Device Operational Test (TADOT) are expanded to include the details of acceptable performance methodology.

Performance of these tests in a series of sequential, overlapping, or total channci steps provides the necessary assurance of appropriate operation of the enMre channel, relay:or'de? ice;" respectively. This change also makes the COT, MasterJ_e]ayJestn11aveiBelay3est and TAD 0T definitions consistent with the definition of channel calibration which already contains similar wording.

1.1-10 Not applicable to CPSES. See conversion comparison table (enclosure 68).

1.1 11 Adds new example to ITS Section 1.4 to clarify surveillance frequencies that are contingent on both a specified frequency and plant conditions.

i I

The ITS contains many Surveillance Frequencies that are contingent on both a "specified Frequency" and plant conditions. For example, "Within 7 days prior to the initiation of Physics Tests," and " Prior to entering MODE 4 from H0DE 5 if not performed within the previous 92 days." These Frequencies do not fall clearly under any of the existing Section 1.4 examples. The proposed example is needed to make clear that 1) the SR 3.0.2 extension of 1.25 times the specified frequency applies to the specified Frequency, and 2) that the interval allowed to perform a missed Surveillance by SR 3.0.3 applies.

SR 3.0.2 is clear that the 1.25 extension may be applied to "the interval specified in the Frequency", so the proposed change does not CPSESDifferencesfrom NUREG-1431 -1TS1.0 2

7/29/98 i

__j

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-6 APPLICABILITY: CA, CP, DC, WC REQUEST:

CTS 1.24, Purge - Purging [Callaway and Wolf Creek]

CTS 1.26, Purge - Purging [Diablo Canyon and Comanche Peak]

CTS 1.38, Ventilation Exhaust Treatment System [ Wolf Creek)

CTS 1.39, Ventilation Exhaust Treatment System [Callaway]

CTS 1.39, Venting [ Wolf Creek]

l CTS 1.40, Venting CTS 1.40, Waste Gas Holdup System [ Wolf Creek]

CTS 1.41, Waste Gas Holdup System [Callaway)

CTS 1.41, Ventilation Exhaust Treatment System [Diablo Canyon]

CTS 1.42, Venting [Diablo Canyon]

DOC 1-15-A The DOC states that the definitions of HVAC systems and functions are deleted to be consistent with STS. While this is acceptable, the DOC does not provide sufficient justifications as to why this change is considered to be administrative.

Comment: Revise DOC by providing additional justification for this administrative change.

FLOG Response: DOC 1-15-A has been revised to provide additional justification that the deletion of the subject definitions are administrative in nature. The deletion of the subject definitions is consistent with NUREG-1431. These definitions are deleted since the CTS l

referring to the definitions no longer contain their use, or no longer are retained in the ITS.

Discussion of the technical aspects of this change are addressed in each TS where they apply.

Thus, the removal of the definition is considered administrative, with no impact of its own.

ATTACHED PAGES:

Enci3A 3

1 1

l

l CHANGE hUMBER ESE DESCRIPTION which leakage is accounted for and treated from present practice. The definition of unidentified leakage has been l

expanded to include "except RCP seal water [ injection or]

I leakoff". to be consistent with NUREG-1431.

1 12 A

The current TS definition for Member of the Public, would be deleted to be consistent with NUREG 1431. This definition would be deleted on the basis that it is defined in 10 CFR 20.1003 and 40 CFR 190.

1 13 A

The current TS definition of the Offsite Dose Calculation Manual (0DCM) [ ] would be [ ] incorporated into the Administrative Controls section of the ITS. This change is i

non technical because the definition of the ODCM [ ] will

)

be [ ] moved to another section of the improved TS.

j 1-14 A

The current TS definition for Operational Mode would be revised to " Mode" and the wording would be revised to be consistent with NUREG-1431. The changes are nontechnical since they will not affect current practice.

1 15 A

The current TS definitions of HVAC processes systcas 0 1.1 7 and functions would be deleted to be consistent with NUREG 1431. [ ] " Purge - Purging" and "Ventina". where used, do not reauire snacial definition [ These 0 1.14

. Jr!1tionslareldeletedJincelthelCTSirefeding ',tolthe definitionsino; longer;containdthei r31se gognoj onger ateiretained JDithe3IS EDi scossion;ofithe lecha1 cal I

aspects!oOhls"changelarela.ddressedlin]eac.h1TS;where;they (applW 1 16 LG The current TS definition of the Process Controls Program (PCP) would be moved outside of the TS along with the Administrative Controls description of this program to be consistent with NUREG 1431. The PCP definition and program description from Administrative Controls are moved into the FSAR. The PCP implements regulatory requirements and need not be restated in the TS. The requirement to comply with applicable Federal and State regulations for the processing of radioactive waste provides sufficient control of future changes to the PCP.

1 17 A

The definition of a Pressure Temperature Limits Report (PTLR) would be added to be consistent with NUREG 1431 0414 and WOC 57, ncy i ISTfj233l Inladditio n the PTLB defJJ11tionlinc]udesithe20RV.l;11ftisettingslconsistent with:theltr_ayeLer s!changelto,31SiSectjonl52516. The i

definition will support the use of a PTLR. Adding the definition is purely administrative in nature..

1 CPSES Description of Changes to CTS 1.0 3

7/29/98 e

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-7 APPLICABILITY: DC, CA, CP, WC REQUEST:

CTS 1.40, Waste Gas Holdup System (Wolf Creek]

CTS 1.41, Waste Gas Holdup System [Callaway and Comanche Peak)

DOC 1-15-A DOC 1-31-A For Callaway and Wolf Creek, the DOC in reference to the subject CTS is DOC 1-15-A.

However, the subject CTS refers to DOC 1-31-A for Comanche Peak.

Comment: Clarify this deviation and,if appropriate, revise the CTS markup with the correct DOC for the particular plant.

FLOG Response: DOC 1-15-A was intended to describe the deletion of definitions for HVAC processes which are in the CTS, Section 1.0. DOC 1-31-A describes the deletion of definitions for specific plant systems which are defined by the plant design and which are in the CTS, Section 1.0.

DOC 1-15-A will be revised to insert the word " processes" after "HVAC" and delete the words

" systems and functions" which led to this confusion. The bracketed systems will also be deleted from DOC 1-15-A.

The " Waste Gas Holdup System"(for all FLOG plants except DCPP) and " Ventilation Exhaust Treatment System"(for all FLOG plants except CPSES) are not HVAC processes. The correct DOC for the deletion of the definitions of these systems is DOC 1-31-A. The Callaway, Diablo Canyon, and Wolf Creek references in their respective CTS markups will be changed to DOC 1-31-A.

ATTACHED PAGES:

Enc!3A 3

Enci38 2

i 9

1

. CHANGE NUMBER HSE DESCRIPTION which leakage is accounted for and treated from present practice. The definition of unidentified leakage has been expanded to include "except RCP seal water [ injection or]

leakoff", to be consistent with NUREG 1431.

1 12 A

The current TS definition for Member of the Public, would be deleted to be consistent with NUREG 1431. This definition would be deleted on the basis that it is defined in 10 CFR 20.1003 and 40 CFR 190.

J 1 13 A

The current TS definition of the Offsite Dose Calculation Manual (00CM) [ ] would be [ ] incorporated into the Administrative Controls section of the ITS. This change is non technical because the definition of the ODCM [ ] will be [ ] moved to another section of the improved TS.

l 1-14 A

The current TS definition for Operational Mode would be l

revised to " Mode" and the wording would be revised to be j

consistent with NUREG 1431. The changes are nontechnical since they will not affect current practice.

~

1 15 A

T a merent TS definitions of HVAC rocesses syst as 0 1.1 7

-,d fu-di=s ld be deleted to

..ti stet NUREG-1431 []

Purge Purging" and " Venting", where used, do no uire special definitions. These 0 1.1 6 definition _s3reldel etedis.inceithe ;CTSiteferring Ltoithe defjnftions' no~ 1ongericontain;theiriuse;1orinoll onget areitetalDedliLthe1I_TS Z2Di scession3fithe2 technical aspects 3 [ this changelareladdtessed;1 [eachiTS h rejthey applyj 1 16 LG The current TS definition of the Process Controls Program (PCP) would be moved outside of the TS along with the Administrative Controls description of this program to be consistent with NUREG 1431. The PCP definition and program description from Administrative Controls are moved into the l

FSAR. The PCP implements regulatory requirements and need not be restated in the TS. The requirement to comply with applicable Federal and State regulations for the processing i

of radioactive waste provides sufficient control of future changes to the PCP.

1-17 A

The definition of a Pressure Temperature Limits Report (PTLR) would be added to be consistent with NUREG 1431 0 1.1-5 and WOC 57. kv i TSIE-233] Irt" addition &the PTL8 definitioCincludesithelPORV111ftIsettjngsTconsistent yjthitheittavelerigchange;_tolIISlSectiojn 5.15;). The definition will support the use of a PTLR. Adding the definition is purely administrative in nature.

i i

CPSES Description of Changes to CTS 1.0 3

7/29/98 l

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1A 1A 1A 1A 1A 1A 1A 1L 1A 1A l1l1I llll lj l-l' m

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-8 APPLICABILITY: CA, CP, WC REQUEST:

CTS 1.25, Quadrant Power Tilt Ratio (Wolf Creek and Callaway)

CTS 1.27, Quadrant Power Tilt Ratio [ Comanche Peak)

DOC 1-18-A ITS 1.1, Quadrant Power Tilt Ratio (QPTR)

The DOC states that the portion of the QPTR definition dealing with an inoperable excore detector is addressed in the Conditions and Surveillance Requirements of ITS 3.2.4. The CTS markup does not reflect this statement since it still contains the definition portion dealing with an inoperable excore detector.

Comment: Revise CTS markup to reflect associated DOC and ITS.

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. In general if the requirement was relocated to a specification in the improved TS which does not correspond with the specification in which that requirement is located in the current TS, a DOC number was generated but the current TS text was not struck through.

DOC 1-18-A is revised to include the following: "The CTS definition of Quadrant Power Tilt Ratio requires with one excore detector inoperable, the remaining three detectors shall be used.

ITS SR 3.2.4.1 Note 1 incorporates the CTS definition requirement such that with input from one Power Range Neutron Flux Channel inoperable, the remaining three Power Range

- Channel inputs can be used for calculating QPTR. In addition, for Callaway and Wolf Creek, I

see DOC 4-09-A in Section 3.2 (Attachment No.8) which reflects that portion of the OPTR l

i~

definition dealing with an inoperable excore detector and Note 1 to ITS SR 3.2.4.1." The CTS i

markup is consistent with the methodology discussed in the Back of Enclosure 2.

ATTACHED PAGES:

Encl.3A 3a 1

I

CHANGE NUMBER fiSBC DESCRIPTION 1 18 A

The portion of the QPTR definition dealing with an inoperable excore detector is addressed in the O'I'I'8

' Conditions and Surveillance Requirements of improved TS 3.2.4. TheICTSIdeffditioriW3Niedrant:foWeFHilt Ragoireqdidts31th'otteieWoMitt6ttcGinopeggleR,1the rega_fnirBiMtuttoirlishalEbenlisjRJ2DJdx3X4. I Note ~;1'j rit.vGvGtt~sitifeWWYinftfonIreqdifeuent?suct) that ~with nDDJtKo1neLPoweYlRa~rige3!ntCFl_ugChannel i

ir! operable 73he2emainjgjtthrf6'Pdiferif[ar!ge Channeljinputs c.e[beNMiforsilcu]iting ERGilnladditf. pKfqt Callagay3!id]gt f_ Creegg_s_ee; DOC 141091Alin_Section:3.2 l

(Attachment.W86Whichirefle~ t.sithat' portion of..theLQPTR c

def.initiorEdeaTing' wit.h..an~inoperableTexcore detector and Note I to ITS SR 3.2.4.1.-

CPSES Description of Changes to CTS 1.0 3a 7/19/98 I

]

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.1-9 APPLICABILITY: CA, CP, DC, WC REQUEST:

CTS Table 1.2, Operational Modes, added footnotes (b) and (c)

DOC 1-25-LS ITS Table 1.1-1, Modes, footnotes (b) and (c)

JFD 1.1-8 New footnotes (b) and (c) are proposed to be added per traveler TSTF-88. This is a change to both the CTS and the STS and is considered a generic change. Therefore, it is beyond the scope of the conversion review.

Comment: If NRC has not approved TSTF-88 by the time the draft safety evaluation is prepared, then this change should be withdrawn from the conversion submittal at that time.

This change will not be reviewed on a plant-specific basis.

FLOG Response: TSTF-88 has been withdrawn by the TSTF. Comanche Peak, Diablo Canyon, and Wolf Creek have deleted the changes discussed in TSTF-88 and have adopted the STS footnotes. Callaway intends to pursue these changes as an out of scope item given the plant-specific NRC safety evaluation cited in new DOC 1-34-LS-2. DOC 1-25-LS-2 has been reworded and revised to be DOC 1-25-A (see attached), applicable to all FLOG plants. New DOC 1-34-LS-2 is only applicable to Callaway.

ATTACHED PAGES:

Enc! 2 1-12 Enci 3A 5 and 7 Enci 38 3 and 5 Enci 4 1,17 and 18 Enci5A Traveler Sheet and 1.1-7 Encl 6A 2

Enci 6B 2

j l

r l

J f

lu-_-_--------_---_-----___-_-___---------------_---_--_----__-_-__---_---

liO~.KUSEj#E~APfLICA_TI_0N E

IIll E I.N M ONS N

i TABLE he lil-1 125 b5Al GP N MODES 0 1.1 9 AVERAGE REACTOR REACTIVITY

• RATED COOLANT HQDE CONDITION. K.,,

THEPJML POWER **' TEMPERATURE PF) 1

\\

1.

POWER OPERATION 2 0.99

> 5%

E. 350'F NA

)

1 2.

STARTUP 2 0.99 5 5%

t-3504 NA 3.

HOT STANDBY

< 0.99 0 NA 2 3504 4.

HOT SHUTDOWNS 8

< 0.99 0 NA 3504 > T.,,

> 2004 5.

COLD SHUTDOWNS'

< 0.99 0 NA 5 2004 1

6.

REFUELING ***)

$-G-95 NA 0 NA 2 140'F NA

)

l

• - (al Excluding decay heat.

Fuci in th; rc;ctor ves:ci with th; vc;;ci head cic urc bolt; less than fully ten;icacd or with the head rc= vcd.

I (bl All;i'M@3 reactot. jess _e]Jhead"cipsure',boltslullylterisjoned.!

)

0 1.1 9 l

A pagtorles~ elihead closure 1 bolts;]ess.than_;fu1]y s

h (c]

M_~~=are";ky te[slor1e.d; J

l 1

. CPSES Mark-up ofCTS-1.0 1-12 7/29/98 I

CHANGE NUMBER NSjiG DESCRIPTION 1 24 A

The current TS definitions of Site Boundary and Unrestricted Area are deleted to be consistent with NUREG-1431. These definitions are deleted on the basis that they are defined in 10 CFR 20.1003.

1 25 T

e 1.2 of the current TS would become Table 1.11 in he improved TS. The following changes would be made t conform to NUREG 1431. In ITS table 1.11, the notation "NA" would replace ~0" under

• Rated Thermal Power for Modes 3. 4. 5. and 6. This is a nontechnical change since j

with K,,, less than 0.99, thermal power would be zero anyway. For Mode 6. the temperature has been replaced with NA since there is no safety analysis basis for the value of 140'F specified in the current TS. Also for Mode

.6. the reactivity condition has been designated NA since the value of 0.95 is specified in the Bases for improved TS 3.9.1.

The temperatures for Modes 1 and 2 are j

designated as NA on the basis that temperature for these

{

Modes is dictated by the minimum temperature for criticality and the operating program for reactor coolant

)

system Tavg. A new note b has been added to Modes 4 and 5 stating that the requir d all reactor vessel head closure bolts are fully tensioned, and a new note c l'1 replaces the note applied to Mode 6. The new note c states that the rcquired one or:more' reactor vessel head closure bolts are less than fully tensioned. [-] The new note c no longer specifies that fuel is in the vessel because the condition of fuel in the vessel is addressed by the definition of the term Mode. This definition I

stipulates that fuel be in the vessel in order to be in a

" MODE." These changes are administrative;ini,naturg h iiS55!dS' !.$.,I,M.

~.~

1 26 A

New sections 1.2. 1.3, and 1.4 would be incorporated into j

the improved TS to be consistent with NUREG 1431. Section 1

1.2 provides specific examples of the use of the logical connectors MQ and QB and the numbering sequence associated with their use in the improved TS. Section 1.3 deals with the proper use and interpretation of completion times, and specific examples are given that will aid the user in understanding completion times. Section 1.4 deals I

with the proper use and interpretation of surveillance frequencies. Specific examples are given that will aid the user in understanding surveillance frequencies as they will appear in the improved TS. The proposed changes are administrative in nature and by themselves are not technical changes, incorporating travelers "00 74 cr.d 0141 WOG-90 TSTF-270IandML267.!

CPSES Description of Changes to CTS 1.0 S

7/29/98 L_____________________________._____

CHANGE NUMBER NSHC DESCRIPTION N

m 1.-34 LS-2 Not3pplicablelto'CPSES? 5Ses1ConversioniC.c!!padMD l o.l.la TabRetic155tr@338p

)

1135' A

CTS!IHia31STilforUlfiblo_Cargehspecines u"A 0 3.6.3 1 all3EnetrAttifrwinersiirsditolbeMcKed3Ratthg asc;isl6~ticdhditidrisNr63ititfigunEEpikejpg cjosed: by_ Tan'0PERABEldirttittellftt)Jpep$st1CJsolatforj valvelsistjeciralusreirbycnancanravsab1fr ditlange.sIot i

dea'ctiv8tgdlietonatic tyglRs15fCfg9Mff9GQeirlclused p6siftoris7Ecoirsistfent MthmMI?2tnistruguirement froCtheidsfinft1onTofiCONTAllelENUINTEGRITTjeuld_be includedifrCtJile Ba~s~e~sTof)ITS'3 63Lar@MLuld_bela.ddiressed by:,theIcombjnation of;sfurye.1]lanceZrequirements'ITS;SR 3.6.31;[SR 3;6;3 23notiapplicable.Mo3PSES);l.SR 3.6.3.3, 3

SRX6. 3.4;andR 3.6.3;8; IThisfchange;would be classifiedias", Administrative; (A);because_theTrequirements of_CES' l.2. a(1;8[aiwoul d_be. retaj nedlinl_theicombined f

surveil] anc.ef,teguj rements 'of..ITS;3 ;6;3, ?Contai nment Isolation'ValveC" 1 36 A

CTS 1.'7.'cyl.~8.c/for Diablo Canyon);speciffe,s that 0 3.6.2 1 theTair;Tocksishall be in~compjiance~with the r_ requirements'oCCTSi3i6,.:1;g.7This requirement,from i

theldefinition~of_CMAJ! MENT 2INTEGRIICyo0Td_be; included iltheiBasesTofjITS :3.76;1]F_T_ heTdetajled; surveillance tes. ting 3equjn sientslor:the "a~1rgocks;arelfurther specifj.edjin: CTS"4:6l1.3?Jetause1 meeting 3;pntginnent. air Locklbghirenehts3dob1d:beMtitrisdiasYdifecticondition ofic[nta(nesht31ri1NOPER,$BJEUYLthfoughj!aprived TS SRl3 6;2;1TaTid';SR'3?6.212]ithis'chirigelieuTd'beTclassified aLAdmin~1strativEi(A)]

1i32 A

CTST7;G1Ee3for;Ca17 s9ay~a1WolfiCreekYand 1;8Kf,orjDiabTo7Catiypn)ls[iec,fiflisit_ hat",goqtaj_nme_nj; 0 3.6.1 3 le6.ga,yelr_dtyf,3 CPSES Description of Changes to CTS 1.0 7

7/29/98

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N0 SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC)

CONTENTS I.

Organization........................................ 2 II.

Description of NSHC Evaluations......................

3 III.

Generic No Significant Hazards Considerations "A" - Administrative Changes.........................

5 "R"

Relocated Technical Specifications............. 7 "LG" Less Restrictive (Moving Information Out of the Technical Speci fications)................. 10 "M"

More Restrictive Requirements................. 12 IV.

Specific No Significant Hazards Considerations "LS" LS 1...................................

............ 15 0119 LS 2.................................... Not _ a ppl i cabl e 47 LS 3..................................

............. 1719 CPSESNo Significaist Ha:ards Consideration - 1.0 1

7D9/98

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CPSES No Significant He:ards Consideration - 1.0 18 7/29/98

INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 TRAVELER #

STATUS DIFFERENCE COMMENTS TSTF 19. Rev 1 Not Incorporated NA1El,12 NRCjjppfoire~dd Ndt approvcd as of travelcr cyt-TR 1.0 00f off date.

ETF-30. Rev 1 Incorporated 1.1 9 15 13205 L.1 1 l01.11 TSTr-54 Incorporated 1.1-1 0 1.1 2 X

TSTr-SS Inccrperated 1-1~6 01.19 w-TSTF_52.1;Rev;1 Incorporated 1.1-13 Incorporated 0 3.6.1 6 Draft Rev.1 per Q3.6.1 6 i

TSTF 111, Rev 1 Incorporated 1.1 5 WOC 57. Rev 1 Incorporated 1.1 6 NRC.apptoved.,

0 1.1 s RTE 233 WOC-74, Rcv 1 Incorporated 1.1 3 0141 TSTE270 WOC-00, Rev 1 Incorporated 1.1 11 0 1.4 1 j

idIt2Z67, 1

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1 Table 1.11 (page 1 of 1)

MODES

• RATED AVERAGE REACTIVITY THER REACTOR COOLANT MODE TITLE CONDITION POWER a TEMPERATURE (k,,,)

(*F) 1 Power Operation 2 0.99

>5 NA 2

Startup 2 0.99 s5 NA 3

Hot Standby

< 0.99 NA 2 350' B

4 Hot Shutdown (b)

< 0.99 NA 350 > T,,, > 200 B

5 Cold Shutdown (b)

< 0.99 NA s 200 B

6 Refueling (c)

NA NA NA m

(a)

Excluding decay heat.

(b)

AL'1Mrcd ]All reactor vessel head closure bolts fully tensioned.

M-e (c)

Or.cor.T.ord-C'edOne"orno eactor vessel head closure bolts less 0-1.1 9 than fully tensioned.

CPSESMark-up ofNUREG-1431ITS-1.0 1.1-7 7/19/98 I

-4

CHANGE 1

l NUMBER JUSTIFICATION i

the requirements contained in the PTLR. Referenced methodologies for i

the PTLR would contain the methodology used to develop the heatup and cooldown figures, as well as the methodology for developing the o.1,1 5 4

[LTOP] setpoints. This change is consistent with Traveler "00 57, I

Rev4JSE23L InladditfonEtheiPTLRideffnitioLincludes1he20Ry liftise.ttlegszconsfstentMth;theittaveletnhangeito3TSiSectfonXs4 1.1-7 Not applicable to CPSES. See Conversion Comparison Table (enclosure 6B).

1 1.1 8 NotlappHeab]eltoCPSESKSee; Conversion;Comparj sonlable 0 1.14 (enclosur(68)] Thc reactor vessel hcad cic urc bolt rcquirc; cats for liOOCS 4. 5 and S are clarified. Thc proposed chang; r viscs footacte b for liOOES 4 and 5 to refer to " Required reactor vcssci hcad cic,ure bcits fully tensioned" and note ; for."00E S is revised to read

" Required reactor vessel hcad closure bolts less than fully tensicned."

l The transitica point betw;;n tiODES 5 and S would also be clarified as occurring uhcn the required reactor vessci head closure bcits arc less than fully tensi ncd. The rcquired numbcr of cic urc bcits, which ;;y bc icss than the total numbcr. is established by analysis that dc; castrates adcquate 0 ring compression to prcycat icekagc a p -

that AS"E Section III stress limits for affccted cca-nc "

.m not xcccded. This change is consistent wi 9 T T 1.1 9 Consistent with TSTF 205'30 Rev 1, the definitions of Channel 0 1.1-1 Operational Test (C0T) Haster Re_layTestr Slave;RelayjTest; []

c and Trip Actuating Device Operational Test (TAD 0T) are expanded to include the details of acceptable performance methodology.

Performance of these tests in a series of sequential, overlapping, or total chanaci steps provides the necessary assurance of appropriate operation of the entee channel, relay orldenceZrespectively. This change also makes the COT, MastedPelay; Test? Slav.e RelayJest and TADOT definitions consistent with the definition of channel calibration which already contains similar wording.

1.1 10 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

1.1 11 Adds new example to ITS Section 1.4 to clarify surveillance frequencies that are contingent on both a specified frequency and plant conditions.

The ITS contains many Surveillance Frequencies that are contingent on both a "specified Frequency" and plant conditions. For example, "Within 7 days prior to the initiation of Physics Tests," and "Prit-to entering H0DE 4 from MODE 5 if not performed within the previous 92 days." These Frequencies do not fall clearly under any of the existing Section 1.4 examples. The proposed example is needed to make clear that 1) the SR 3.0.2 extension of 1.25 times the specified frequency applies to the specified Frequency, and 2) that the interval allowed to perform a missed Surveillance by SR 3.0.3 applies.

SR 3.0.2 is clear that the 1.25 extension may be applied to "the interval specified in the Frequency", so the proposed change does not CPSES Differencesfrom NUREG-131 -ITS 1.0 2

7/29/98

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ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 1.4-1 APPLICABILITY: CA, CP, DC, WC REQUEST:

DOC 1-26-A ITS Example 1.4-4 ITS Example 1.4-5 JFD 1.1-3 JFD 1.1-11 Additional examples, Example 1.4-4 and 1.4-5, are proposed to be included in ITS. The DOC and the JFDs state that these ITS changes are to incorporate travelers WOG-74 and WOG-90.

Comment: Provide the current status of WOG-74 and WOG-90. If WOG-74 and WOG-90 are not approved by the TSTF, then these changes shou d be withdrawn from the conversion submittal at the time of the TSTF rajection. If WOG-74 and WOG-90 have not been acted upon by TSTF, or have been approved by the TSTF, but not approved by the NRC at the time the draft safety evaluation is prepared, then these changes should be withdrawn from the conversion submittal. These changes will not be reviewed on a plant-specific basis.

FLOG Response: WOG-74 and WOG-90 have been approved by the TSTF and are designated as TSTF-270 and TSTF-267, respectively. Both of these travelers have been submitted to the NRC and are under review. The proposed wording in TSTF-270 was modified from WOG-74, Rev. 2, and these modifications have been incorporated into the ITS. The FLOG continues to pursue the changes proposed by these travelers.

ATTACHED PAGES:

Enci 3A 5

Enc!SA Traveler Sheet,1.4-5 and 1.4-6 Enci 6A 1 and 3 I

~

1 1

l J

CHANGE NUMBER N2iG DESCRIPTION 1 24 A

The current TS definitions of Site Boundary and Unrestricted Area are deleted to be consistent with NUREG-1431. These definitions are deleted on the basis that they are defined in 10 CFR 20.1003.

1 25 E-2A Table 1.2 of the current TS would become Table 1.11 in the improved TS. The following changes would be made to conform to NUREG 1431. In ITS table 1.11, the notation "NA" would replace "0" under

• Rated Thermal Power for Modes 3. 4, 5, and 6. This is a nontechnical change since with K.n less than 0.99, thermal power would be zero anyway. For Mode 6. the temperature has been replaced with NA since there is no safety analysis basis for the value of 140'F specified in the current TS. Also for Mode 6. the reactivity condition has been designated NA since the value of 0.95 is specified in the Bases for improved TS 3.9.1.

The temperatures for Modes 1 and 2 are designated as NA on the basis that temperature for these Modes is dictated by the minimum temperature for criticality and the operating program for reactor coolant system Tavg. A new note b has beenaddedtoModes4and5statingthatthercquiredall reactor vessel head closure bolts are fully tensioned, and a new note e replaces the note 0 1. M applied to Mode 6. The new note c states that the rcquired one;or,more; reactor vessel head closure bolts are less than fully tensioned. [2] The new note c no longer specifies that fuel is in the vessel because the condition of fuel in the vessel is addressed by the definition of the term Mode. This definition stipulates that fuel be in the vessel in order to be in a " MODE."

These changes are administrative 2tginaturej. cxccpt for the r,cw notc; b cad c. c.ddcd per TSTF SS cad cddic;;;d in "SlC B 1 26 A

New sections 1.2.1.3. and 1.4 would be incorporated into the improved TS to be consistent with NUREG 1431. Section 1,2 provides specific examples of the use of the logical connectors ANQ and 08 and the numbering sequence associated with their use in the improved TS. Section 1.3 deals with the proper use and interpretation of completion times, and specific examples are given that will aid the user in understanding completion times. Section 1.4 deals with the proper use and interpretation of surveillance frequencies.

Specific examples are given that will aid the user in understanding surveillance frequencies as they will appear in the improved TS. The proposed changes are administrative in nature and by themselves are not technical changes. incorocrating travelers (.?SS 4 c.n' TSTFj2Z0LandHSTEf26]l l0101

.2 CPSES Description of Changes to CTS 1.0 5

7/29/98

INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 TRAVELER #

STATUS DIFFERENCE COMMENTS e

TSTF 19. Rev 1 Net Incorporated NAl~.1-12 NRC@pp=oVed.]

u c... =m nuw uyys vvv u ua of traveler cut-TR 1.0 00f eff date.

l TSTr-20. Rcv 1 Incorporated 1.1 9 TSTFf2_05 1.1-1 0 1.1 1

)

TSTr-54 Incorporated 1-1-4 0 1.1 2 TSTr-SS Incorporated 1 8 Q 1.1 9 TSTF-52 'Rev:1 Incorporated 1.1-13 Incorporated 0 3*6'1 6 Draft Rev.1 per Q3.6.1 6 TSTF 111. Rev 1 Incorporated 1.1 5 E S7. Rev 1 Incorporated 1.1 6 NRC approved.

0-1 1 5 I M 233 Rev 1 Incorporated 1.1 3

' E 74.

0141 M 270 WOC-00. Rev 1 Incorporated 1.1-11 0 1.4 1 B g g67 y

l l

l-

i l

Frequency 1.4 1 14 Frjit[ Gen [3 nemywyynxnygerngsumwgm77;w.y~;gxy nwpcmvw ~

EXARLES EXiBFHFI?474 X @ tinued).

SERVEILLANCEfREQUIREMENIS 1

TdRWiMMSURVEILEANCQ E DIEquENCY

.~=:g._ e====:N.0.T_E_=_ v. n_=._c.. =.~

1.1-3 m

OnJyJMksigditolbelperformediin ; M00Eil;

,=,=.,g=..=.=..,=__===m_==_=:.=

=

==

m, i

PerforaTcdeplet_eicycle;of.thelval ve.~

7Jdays i

ThelinterVa1Icontinues/:whetherjor. not' the unit; operation is in MODEa1Rjiorl31the: assumed Applicability'ofithe associated LCO) be.tetg']Lirformancesj As;thelote!s.odiffeMthelrequired performance ~ofathe; Surveillance, theiNote]isjconstrued_tolbe,partLof;thefspecified Frequencyi".

Should!$he71daylinteryal,.belexceeded while: operation;isinot in M00EXRhi$1rjotelallows'entryfinto;andfope; ration;inLMODES:2 land 3 l

to pect@lthelSurve111ance.3lJhe Surve111ancejlsist111; considered toibeJLillgorisedJfthinithelispecified..Frequen~ y'sif@omple_ted c

pr,forMng:!IODEll;5;gherefore.Hif the;Survjtillance^)ere;not A

peEfoD!hLighMthe?Jlday:1plu.s;thelextensfoKallopfdiby; 5R 3LO12E![RtiftaljIbutloperation:WasinotjinMODElli"jitLWlo~ld not u

constMlalfailurefof.tthe^SR;orifai]ureitoiseetithe,LCO.2A1so, noMcDt%2CDfRA014 0ccurs]vhenichanging$0DESKeyen'withithe 72dgygsgu]igfM,]qe_tfjprovfdedjppe,rltion; doe.sM. ire ~sult. in eH1011gEMIDE32 j

Oncf thirhitZtgiches't100E21?Hthe;retpittementifot[ths;S,utveillance to:blGRBONid31MirWtsispecified;F.te.qdaricylaMie~ sendMld s

61ajgelhayelbeenjpe:rfo,tged?ilfst.he SM3lL*3ietfolged;Klorito710DE*1?BhereM1dithen ben 13tieflDincGithEth0Mc3ff' NM ~- n.1.4 1

---

===__...,....-....w I

~ ll' I CPSESMark-up ofNUREG.1431ITS-1.0 1.4-5 7/29/98

Frequency 1.4 l 3. --.?. : g,qy,y,3y y - r-,- -. m. = c -rm 7. ~. 3 EXAMPLES EXAMPLE:U 4:5 l:li-. Idh- 0

l-tchneed) l SIRVEILEANCEIREQUIREMENTS I B MJI E GSURVEILLAN_QE iTfjiFREQUENCY VdrifyTachyntaipmenti'isblati.on manual Ptiorito valye;1Cclose;y entering MODE _4 fr6m'H00E15l1f riotiperformed within~the previous 92 day { "' - c.1.4 1 In. Example /1.4-5, the $specified Frequency" is measured. from when the

SurvejlJance_wasllast. performed. ;Shouldlthef.interyal. be exc'eeded,3the:Surveillarice.is not required to:be performed until certain:c6nditions'are, met. :The _Surye111anceLis allowed to be delayed.,untilptiot;tolentering;H00E;41from H00E_5;if the,92. day "specjliedJreqGenefiha.sinxpf red.?The:9.2,.daylinterval.may be extendedloI251 times"the3tatedlintsriaiXsiilloWedibf SR 3.0.2 forloperatlogajglextbflity.ETherefor;e;Mf t.he Surysf11ance were 2 Z notMrJpoirsp8DvithinJth_e192l day 3plus7the' extension allowed by;SR 2

r 3.0.;_2Ei!LterjaMb0tlope~ ration Wasinotltransiti.oning ;from_ H0DE 5 to LH00EE4? lit].iioQlf.nbtic.o. nstitutefalailure.~.bf_the SRiori;.a failuteltgneetj.the_LC0FHhe~next time:theidnitEptcceeds'from H00EXtgM0E3,$thelsury,e111 ancel.iwolJ1A.be ~redjf.edito ~ be pe rforniRCpr,for5to'5the.lttalisttiori.1 ~ ThfmeaiD;rjesientibCthis31nterva15continueslatjaRiti.m.esZeven when theJSR_1sInotXeq01tydito]helmetiperiSRKO..li[sdchias3henithe s e9'JJpeGIIIsMooWesbIma24tiable:istsidels ycf.fiedjJjnits: p ofithejl![11tXslootXdelthq@]fgabf}itfofit_h3e CO)3Hfithe f co_nditimi$11oitM7ciRoreticyiare'aetJfg;thaelntesaJ12spicifier bi SRIEU'2MeiexceededMthoTitMM;J.urleillancewayinyltteg periotistenditterfdriethcs:ofithe3urvet1Ritcu'Jsinotibt.hsrwise modif.ifdKf"bferito*EMapTs714Q)2thBnTSRT0;3 be'cbees app 1_ic4blel er;wrmmm:- ~v :umm,newgun;.myr.wvex wm,~~ m.,~m CPSES Afark-up ofNUREG-H31ITS-1.0 1..t-6 72 9/98

JUSTIFICATIONS FOR DIFFERENCES FROM NUREG 1431 Section 1.0 This enclosure contains a brief discussion / 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 /NRC generic change process. The change numbers are referenced directly from the NUREG 1431 mark ups. For enclosures 3A, 3B, 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 l indicate that other JLS plants may have plant specific information in that location. l l CHANGE i NUMBER JUSTIFICATION j 1.1 1 The NUREG 1431 Rev.1 definitions of Channel Calibration! Channe1 L0perationahTestj and; Trip: Actuating EDevice: Operational 0 1.1 2 Test use'languagesto; describe t.helscopetof testing:similar'to; stetcs, "The C".'f0!CL CALI""'TIO'? shall cacm..ps3 "the entire channel, including the required sensor, alarm, interlock, display, and l trip functions". The: word "requireCis:: ambiguous;andisubject;to misinterpretationiasitoiwhether i theilistlisinclusive or.; representative'.TIThis change clarifies what i l componentsfareiincluded by;specifyingfallidevicesMnitheichannel required;forighannel 0PERABILITY"gAjsimilar1 clarification.iis;provided forithelActuation;LogiglestE cne.apsses the antir; ch;naci by rewordi g the dcfinition to state. "The C".'f0!CL CALI""ATI0" shall i l enc a ps3 thosc capacats, such :s sensors, cler;;;s, displays, and trip functions. rcquired to perfor;;; the specified safety function (s)." He j Channci Operational Test and Trip Actuating Ocvice Opcration:1 Test definitions era si;;;ilarly revised. This change is consistent with TSTF-i 205E64- ] 1.1 2 Not used. 1.1 3-Adds new example to ITS 1,4 to clarify meaning of SR notes of the type "Only required to be performed in Mnnt

• This 0*l 61 change is consistent with travele@ 74, "cv 1 15IE-j2 1.1-4 Not used.

1.1-5 The definitions for ESF Response Time and RTS Response Time would be revised to substitute the word " verified" in lieu of " measured" consistent with the requirements of NUREG 1431 SR 3.3.1.16 and SR 3.3.2.10. This change would ensure consistency between the definitions for Response Time and the requirements to periodically verify Response Time is within limits. This change is consistent with TSTF 111, Rev 1. 1.1 6 The definition of the Pressure and Temperature Limits Report would be revised to include the maximum allowable PORV lift settings and arming temperature associated with the [ Low Temperature Overpressurization Protection (LTOP)] System, and to be consistent with the COLR definition. Improved Technical Specification 3.4.12 states that the CPSES Diferencesfrore NUREG-1431 -ITS 1.0 1 7/2988

CHANGE NUMBER JUSTIFICATION Surveillance is not performed within the "specified Frequency". Again, the example does not change the intent of the Specifications but only makes clear the application of SR 3.0.2 and 3.0.3 to Surve111ances with Frequencies tied to plant conditions. This change will eliminate confusion and misapplication of the ITS and will ensure consistent application of SR 3.0.2 and 3.0.3 to these types of Surv nce Frannoncies. This change is consistent with traveler E 00. ~0 1.4 1 pg q / 1.1512 The:defitttiofoLCHANNEL CALIBRATION;is.~reyi,s_edito: move details"0LRl]Fdnd; thermocouple:c~ l.ibration;tolthegY 3.3; Bases a m-1.0 006 associaturwith~theicientsfgonsistent WithJSTFl19; 1.1-13 Traveler]JSTES2.2draftiRevision'1;; dele _tes;the;d finition_.of e 0 3'6'1 6 L,. ;Sinceit,lisidefined;,if;10.CFR5_0,~ Appendix lJ and ITS Section 5.5-167_ Containment Leakage 1 Rate Testing ~ Program, lit;is redundantitolinclude L,~as;a' definition.~ Asl described in NUHARC 93 03, TritersAide;forathe_ Restructured. Technical. _Speci figatj ons," Specific 8 tion %1l:is;a;11st of; defined terms.and corresponding definitiorjs(us6d; throughoutithe; Technical _ Specifications ; L, 'is not used;_throughoutlthel Technical specifications and is_ defined in Section 5.5-16;] l ? CPSES Differencesfrom NUREG-1431 -ITS 1.0 3 7/2988 l -____ _ ______ - __ A

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR 1.0-006 APPLICABILITY: CA, CP, DC, WC REQUEST: Incorporate NRC-approved traveler TSTF-19 Revision 1 to move the details of the RTD and thermocouple calibration process from the CHANNEL CALIBRATION definition to the appropriate Section 3.3 Bases. Section 3.3 Bases mark-ups are tracked under No. TR 3.3-004. ATTACHED PAGES:, CTS 1.0 - ITS 1.0 Enci2 1-1 Enci 3A 1 EnciSA Traveler Sheet and 1.1-1 Enci 6A 3 Encl 68 2, CTS 3/4.3 - ITS 3.3 (See changes labo!cd TR 3.3-004) l EnctSA Traveler Sheet Enci5B B 3.3-56, B 3.3-120, B 3.3-140 an.1 S '.3-151 5 i l l 1

U0feUXSANDlAPPJ.ICAT_I0N 1.01 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. __ t-el-6_,Y_ ACTION M' ACTIONS, shall be that part of a Tcdnical Specification wh4eh.that prescribes 1-01-A rc;cdial ac;su.c3 rcquired Required Actionsito_beltaken under designated reconditions within1helspecif,ied;..Completign Times. ACTUATION LOGIC TEST M An ACTUATION LOGIC TEST shall be the application of various simulated or 1-01-A f actual input combinations in conjunction with each possible interlock logic state required for OPERABILITY 'of a logic circuit and verification of the ~ required logic output. The ACTUATION LOGIC TEST shall,-as a minimum, include a 1 32.A continuity check, s ; ainimum-of output devices. 0 1.1 2 ANAh0G CHANNEL OPERATIONAL TEST (C0T) { 4-3 An.^f:^100 C".'f!EL OPERATIO!!AL TEST A1 COT shall be the injection of a i i 1-EA / simulated ocactual. signal into the channel as close to the sensor as practicable to verify 0PERABILITY of all' devices;in'the channel required for t channe_1 0PERABILITY; j,.cludipsJ.ll14-.-ycnint;_ f.r. ti.;_;'.g.aci,7;uph_;s;;1erm

• 130 A 2

interleds, displays, and/;r trip functions required to"pctfor;;thc::pc-ified 1-32 A sofctyjunction(s). The COTsmay be: performed by.means;of;anyf series of a.1.1 1 sequential,2 overlapping or total channel. steps scith:t;thc;catir;;hqanci is o.1.1 2 testedJ The 'J!^100 C".'J:!IL OPERATIO!!AL TEST COT ~shall include adjustments, as necissary, of the required alarm, interlock and/or Trip Setpoints required for channe10PERABILITYjsuch that the setpoints are within the rcquired n.ecessary range and accuracy. AXIAL FLUX DIFFERENCE CAFD)] 4-4 AXIAL FL"X OIFr:ROiCE AFD shall be the difference in normalized flux signals Wi-A M between the top and bottom halves of e four scctica an excore neutron detector. CHANNEL CALIBRATION M A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the i channeljip03Es0.ch such g that it responds within the tjetl:essary rcquired a.1.1g2 1 32 range and accuracy to known yaLUeCofithgefumJe etithat1thelchannelimonitots; values of input. The CHANNEL CALIBRATION shall encompass ajDevicesJinithe chattrMTir,equitedlfor'ichennieliOPERABILIJD thr;Qt;[,t;;the cr.tirc chenaci, including the required us.';;s~3cnscid, cler;, interled, display, and trip functicas;;riquiicd;tEp--fir;2CpicifiqCpgic_t11fC.ctierZsD Calibration oflips_tr_unegt;,, channel _s[wi_th~resistagc_e;tgperatute ;de_tecto.rJRTDJioC 1 03 M thegKouplelsensoCS)y ]C9nsisEof,ian]npMcelqualitatijgeiasses_sment[ofjsensor TR 1.0 006 belgUotyand wreaucalibrattoh?ofithe2@salDirig~'ad.iustablerdevices "i rrthe _ ~~ d = 6 i;,i. a siiFi E - m.w r s_s i n E ls n i s G jisi.E2JE.I L 4 15 s. M.C E $ 0.lE.E - E i~. 2. S N EIS EC M i.!, w;^I O T-tic i,tI5 C.i-i^in1 2 G G ;r C._ = -, .---a.- cuun . ~.. - nuraum.s-.-~ww~re w".~.v wr.~m.mnu uum w=n CPSES Mark-up of CTS - 1.0 1-1 7/29/98

DESCRIPTION OF CHANGES TO CURRENT TS SECTION 1.0 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, 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 NUMBER L2iG DESCRIPTION 1 01 A These definitions would be reworded to be consistent with NUREG-1431. The proposed rewording included in this category does not involve any changes of a technical nature. 1 02 A The definitions for Analog Channel Operational Test and Digital Channel Operational Test would be combined into a single definition of Channel Operational Test (C0T) to be consistent with NUREG 1431. Separate definitions would no longer be required for the improved STS. The combined definition allows use of actual as well as simulated signals. The proposed rewording does not involve changes of a technical nature. ~ 1 03 M The definition of channel calibration is reworded g j to be consistent with NUREG 1431 a_simodifjediby TSTi 19. The revised wording provides additional detail concerning calibration of instrument channels with RTD's or thermocouple. 1 \\ 1 04 ALG Thi; d;finition would n; leng;r k uxd ad th;

pcific;ti;n; in ITS S;;ti= 0.0 ad M;;ir.istrative cer,trols Occticr, would be rcvised exerdingly. T k ;;rrent 5 i finiti c for Cent; irs at kt;grity W;uld M 21;t;d t; k ;;n;i; tat with ".'"CC J

101. Thi; ifinition i; cff;;tiv;1y ireerper;t;d int; th; "'J"CC 1431 k;;; for th; ac.; Centei,- st Luiting Cendition f;r Op;r; tion (ITS 0.0.1) nd tk Aiini;tr;tive j Centrol; 0;; tion for the Catsi. st Lak;;; T;; ting "regra [ 3. TtleIdefinit16nInfiCONTAlleiElg3NTEGEjs j deletedKthelbasis3hatMtTdodijhotiapp~gENUREGi e 1431HItihais' beenDL@tth;the Wrequiregn_tf of ImptoL6dEEE1MoAFinmetgit_oX0PEJ,A_BJ@ll)e detai] sTef1this"defirgittopescribehdtitonstitutesian OPERABLEliit:entamjgMfytfulfggilc6cpgfit.ed 10tolthe;8agsyoHLaptoie_d;TSR316113JidJre3' inflected CPSES Description of Changes to CTS 1.0 1 7/29/95

l l INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 1 1 TRAVELER # STATUS DIFFERENCE COMMENTS e ~ TSTF 19. Rev 1 'Not Incorporated NAl'1_-;12 NRClappro'ved.] Not ;pproved..as of traveler cut-TR 1.0 00f off date. TSTI 30. Rcv 1 Incorp h 1.14 TSTF-205 1.19 { 0-1.1 1 ) l TSTr 54 Incorporated M 0-1.1 2 TSTr 88 Incorporated M-B 0 1.1 9 TSTF-52. Rev,1 Incorporated 1.1-13 Incorporated 0 3.6.1 6 Draft Rev.1 per 03.6.1 6 TSTF 111. Rev 1 Incorporated 1.1 5 WOC-57. Rev 1 Incorporated 1.1 6 NRC approved. 0115 E 233 WOC 74. Rev 1 Incorporated 1.1-3 0-1.4 1 E E0 WOC-00. Rev 1 Incorporated 1.1 11 0 1.4 1 TSE26Z

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions ..................................... NOTE------------- The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. Ig.ag Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in 1.1 1 conjunction with each possible interlock logic state 0-1,1 2 I l required foriOPERABILITY:of a logic; circuit and the l verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices. I AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux B-PS. (AFD) signals between the top and bottom; halves of e tw;sectionanexcor_eineutronfdetector. CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel se output }uc;1 that it 111 0 1.1-2 responds within the neces.sary require.d range and accuracy to known valdestof;theghgameterJhat?.the channehmonitoCLs; input. The CHANNEL CALIBRATION shall encompass allideylceslin1h_e3:hanne1} required,for chanr!610_PERABILITY2 th;;C;,, L%..t;~thc cr.tira ch;nncl. including the rcquired ;;;;MjGsca;;rg : lor;4 interlock, display;. :nd trip functier.sfT,%.;;d l G il,.elthe ] Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the ramaining adjustable devices in the 1,1,12 cySacar ;, casing cl. cat i:.at rcquired C".".'?.' L CALI"",'TIO" ; hell includ; =q, TR-1.0-006 )

repunc, inplus cross c:libration that ca pcrcs the othcr j

cnsing cicnnts with the resnth 'n: tolled ; casing I ' nnt ' The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping 1,1,1 calibrations or total channel steps so that the atira 0 1.1 2 chanci is calibrated. l (continued) i I CPSESMark-up ofNUREG-1D1ITS-1.0 1.1-1 7/29/98 o_______=___________ j

CHANGE NUMBER JUSTIFICATION Surveillance is not performed within the "specified Frequency". Again, the example does not change the intent of the Specifications but only makes clear the application of SR 3.0.2 and 3.0.3 to Surveillance with Frequencies tied to plant conditions. This change will eliminate confusion and misapplication of the ITS and will ensure consistent application of SR 3.0.2 and 3.0.3 to these types of Surveillance Frequencies. This change is consistent with traveler "^C 00. 0 1.4 1 TSTE2@ Theldef. n,ition;gf plANNELICA_LlBRATIOLis_ levi sed. to; nove i 1.1f12 det. ail s :of..;RTDJand _thermoc_oep1Epalj bration ~, tpithefTSJ3.3, Bases m 1.0 006 associated;withithfcoMs",~ consistent,with JSTFi19., x 1.1V13 TravelermiF.-5_22 draft; Revision 1," deletes ;theJefinition of 0 3.6.1 6 La[Mncesi.s;definedin10C85'0;[ Api >endix ~Jiand ITS.Section 5.5)16)i?ontainment,. Leakage;RateLTestingProgram;21 tis c redundant l;to inglu_de;L, asia'; definition.7JAs _ described in NUMARC 93 03, " Writers; Guide;forJheJe_str0ctured. Technical. Specifications." Specification'1.1.isia list of_ defined. terms and corresponding definitions used throughout..th,e.' Technical Specifications. L,'is not used throughout the Technical, specifications an_d.is defined in Section 5.5-16._~ I I l 4 l CPSES Differencesfrom NUREG-H31 -ITS 1.0 3 7/29/98

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i INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 ) i TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-19. Rev. 1 d Incorporated NA _... _. s{d as of t'ot ti;C cv g-( by lhe M._;. Bases ~eo M*.. x m=.M=:.v A i TSTF-36, Rev. 32 Incorporated 3.3-34 yg 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. TSTI 01 l4ct Incorporated NA [ ] A11cuabic Valucs l TR 3 3 005 for loss of voltage and dcgraded vc Magc will rcasin 4n the TS. TSTF-111, Rev. 1 Incorporated NA TSTF 135 Partially 3.3 41 Travcicr is toc broad 7g.3.a 006 Incorporated 3.3 90! scope in naturc, 313-917 should have bcen 3.3-93, several separate travelcrs. 3.3 95, Porticas of the travelcr that 3.3 122 significantly clarify operability requirc; cats have bcca incorporated. TSTF 161 Incorporated 3.3 79 TSTF-168 Incorporated 3.3-43 TSTF 169 Incorporated 3.3 42 ApprgvedibKthelNRCJ TR-3.1-003 '400-1052TJUE242 Incorporated 3.3 49 l TR 3 3 005 TSIE246'.fropcsed Incorporated 3.3 107 '400 tiini Orcup Actica 7g.3,3.got treveler Item #145. l L__

l RTS Instrumentation B 3.3.1 BASES This SR is modified by a Note that excludes verification of setpoints from the TADOT. Since this SR applies to RCP undervoltage and underfrequency relays, setpoint verification requires elaborate bench calibration and is accomplished during the CHANNEL CALIBRATION. SR 3.3.1.10 A CHANNEL CALIBRATION is performed every BB} 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. dThis;SR;is modified by a Note _ stating (that,N;16_ detectors.arel excluded from the; CHANNEL CALIBRATION;LThi.s.' Starve 111ancefis' not;for, entrylinto. MODE 2 orfl,~because the unit.aust _be;in.at leastf M00Eilfor the. N 16 detector _s;g CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit specific setpoint methodology. -The differens betwan th: current ";s found" alx; =d the picvicus test "= left" alues ;;;u:t bc ;;nsistat with the drift ellow== u;cd in the setp; int ;;;cthedclogy. The Frequency of 18 months is based on the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint methodology. SR 3.3.1.10 is modified by a Note stating that this test shall include verification that the time constants are adjusted to the Tji,IdoesWitncJdde prescribed values where applicable. ver.ifiglicifontime delayM1_ays;$11tThiscertwrtfiedNfa rw =-mmmSn;s;r.no.,,,r .cantamo TR-3.3 004 GulE li-i M N7, b l4 2. M M ldd CtNNEtBEEEEME'5f4hs'BTDs11 sis %MIBtdM14] L gMgsgEggam19hithaerr---- p-A siMpements WNh166stal16dWielseitt! SR 3.3.1.11 SR 3.3.1.11'is the performance of a CHANNEL CALIBRATION. as described in SR 3.3.1.10, every 98318 months. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The C"."ZEL CALIS"ATI^" for thc p;cr ren;; n;;tre,. detGters cen;ist: ;f ; ne niiz: tion of the detecters bued en : p;;r ;;l;ri.;.;tric ad ; =p perferad eben 15t."". !EorAtheJintepediate2gnd;paggrltange3_hannel s j ~ det_ectof;pl ateao; curves tarezobtainedayaluatedatnd; competed 3o CPSES Markup ofNUREG-H31 Bases -ITS 3.3 B 3.3-56 7aM8 C__

ESFAS Instrumentation B 3.3.2 j l BASES l l l f SR 3.3.2.8 ) i SR 3.3.2.8 is the performance of a TAD 0T. This test is a check of the Manual Actuation Functions and AFW pump start on trip of all MFW pumps. It is performed every 18 months. Exh ",;nual Actu; tion function is tasted up to and including. th; = ster relay ccils. In ;c;; instanccs. the tcst includcs xtuation of the cad dcvice 'i.c., pump starts, valvc cycics, 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 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 measured parameter within the necessary range and accuracy. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit specific setpoint methodology.--The diffc.cxe betuxn the current ";s found" values :nd the prcvicus test ~;3 left" values aust bc ccasistcat with the drift 11cwance ttscd in the ;stpcint cethodcicgy. The Frequency of 18 months is based on the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint methodology. This SR is modified by a Note stating that this test should inc.ude verification that the time constants are adiosted to the orescribed values where applica4neganb_,_ Et; TR 3.3-004 ,sjyplElRQt!gpj!p_tfpnti6 Y(l(3);4thC@extJMitlyediCHANN cat 1BBgIg![~0fXthe'RTqsis]iscomplis!Le(REinplac.e3tpss - es11bm1h8 tic?!sparis otherlsensgeleadhtsyith3he recentXanstalleolement.! SR 3.3.2.10 This SR verifies the required; individual channel ESF RESPONSE TIMES are less than or equal to the maximum values assumed in the (continued) CPSES Markup ofNUREG-1431 Bases -ITS 3.3 B 3.3120 7/29/98

PAM Instrumentation B 3.3.3 BASES during normal operational use of the displays associated with the LCO required channels. SR 73.-3:3.2 f0E ;_thgMtogenimogj tors, ca., CHANNEL 1 CALIBRATION;1s; performed _every 92;daMCHANNEECALIBRATIONT,1.sla complete ~ check [ofithe;jnstrument l#P711geludingithe;segsofgThe fest derffles.~,thatithe l channellrespondsito; measured parameter;withithe:necessary CP 3.3-001 range;andi, ccuracy2Thelc. alibration; sequence 3sesisample a gas.in;accordan:ceyjth the' man 0facturerls; recommendations and verifies that"the' current ~ calibration ~ constants are~ contained in.the;mjeroproces_soridatabasel.3ThisiSR.isimodified by a. Note i.ndicating ;that;this;SRL.is lonly;applicableitoltheihydrogen monitors.NTheJrequency is1 based on' manufacturers recommendations. SR 3.3.3.23 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 measured parameter with the necessary range and accuracy. This SR is modified by a Note that excludes acutron detect;rs.3thelhydtggeniponitorsXwhichia.re addre_ssedlin SR13j323i2. The calibr: tion ;;thed for neutron detectors is specified in the Seses of LCO 0.3.1 "Rescter Trip Syste;;; (RTO Instru;catetion." This75R.:islaiso'modif,jed byla, se_ conOote!thatidiscusseslan219@ied;methodologflotical.ibrating th919tsinne!)t1RadiatfonTele1JHigh EangeJiFujc_tiog; The { calibration method for neutron detectors is specified in the Bases of LC0 3.3.L " Reactor Trio System (RTS) InstrumentationSmsplated4niuncuoD 7 h ]i orsmnetemmercazBNLEKEMAM31 tg,R_TDJ sD3s3MBBhilDD2IREEhDIBIN. competHRMrEH52RrgeantsIMtitBheMMtBWIrnstaned elemeBatLWevyi2GUrteRit2he teRnTpTeTrplacTd in?FdnctiorD4, r theJWkt TeqQfff!r2_ANIELTCALIJBl!LTI_0!CdGtMLegrelexit j-CH the_@l_isJfMcTcjtplifs@d by~an2n.iplaM^ cross 3alib_ tat 1on~thay cgapa s t_h,e~b_th_er)sensind~ela-mts'ltith'thelecegt]y31nstalW yl senNelement37:ne Frequency is based on vperaung experience and consistency with the typical industry refueling cycle. CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3145 7M988 J

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 LC0 required channels. l SR 3.3.4.2 l SR 3.3.4.2 verifies each required Remote Shutdown System powegland control circuit and transfer switch performs the~ intended function. This verification is performed from the remote shutdown panel and locally, as appropriate. Operation of the 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 inaccessible, the unit can be placed and maintained in MODE 3 from the remote shutdown panel and the local control stations. The 18 month Frequency is based on the need to perform this 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 during a unit outage.) Operating experience demonstrates that remote shutdown control channels usually pass the Surveillance test when performed at the 18 month Frequency. 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 measured narameter within the nacaccarv rance and accur [a .. Elaisensinglelemegislteplacedsthelgentlegired R 3.3 m CHANNEtCALIBR_AIIONiofjthelresistanceiteeperatureldetectorA @TDEsensgs21sIaccpaplishedibKarGinIplaM3 Mss @likation thaticomparesithelother msensing' elements"WithitheP76 m t Z ;w sensing;elemen AtPrequency of 18 months is based upon operating eyei ieme aiia consistency with the typical industry refueling cycle. SR 3.3.4.4 SR 3.3.4.4 i: the grformacc of a TA00T cycry 18 naths. This test should verify the OPER'SILI"I of the reactor trip br:2cr; (RE cpen and cicscd indicatica on the re;;;cte shutdown p;ncl. by actu; ting the RTSs. The frequcacy is b;;cd upon operating expcricacc cad con;istency with the twical industry refueling cutagc. (continued) CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3-151 7/19/98

i ' to TXX-98195 Page 1 of 4 l l l l JLS CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS CTS 2.0 - SAFETY LJMITS AND LIMITING SAFETY SYSTEMS SETTINGS ITS 2.0 - SAFETY LIMITS 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION AND LICENSEE INITIATED f ADDITIONAL CHANGES { t ) i j l l ( l i ~ ~~-

---

n

l-1 to TXX-90195 Page 2 of 4 INDEX OF ADDITIONAL INFORMATION ADDITIONAL INFORMATION APPLICABILITY ENCLOSED NUMBER 2.0.G-1 CA, CP, DC, WC YES 2.0-1 CA NA 2.0-2 CA, CP, DC, WC YES 2-.0-3 CA, CP, DC, WC YES 2.0-4 DC NA 2.0-5 DC NA 2.0-6 WC NA CP-2.0-001 CP YES DC 2.0-001 DC NA DC-ALL-002 (2.0 changes only) DC NA DC-ALL-003 (2.0 changes only) DC-NA O.

. to TXX-98195 ) Page 3 of 4 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR { PROVIDING ADDITIONALINFORMATION The following methodology is followed for submitting additional information:

1. Each licensee is submitting a separate response for each section.

2. If an RAI does not apply to a licensee (i.e., does not actually impact the information that defines the technical specification change for that licensee), "NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee.

3. If a licensee initiated change does not apply, "NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee.

4. The common portions of the " Additional information Cover Sheets" are identical, except for brackets, where applicable (using the same methodology used in enclosures 3A,3B, 4,6A and 6B of the conversion submittals). The list of attached pages will vary to match the licensee specific conversion submittals. A licensea's FLOG response may not address all applicable plants if there is insufficient similarity in the plant specific responses to justify their inclusion in each submittal. In those cases, the response will be prefaced with a heading such as " PLANT SPECIFIC RESPONSE......."

5. Changes are indicated using the redline / strikeout tool of Wordperfect or by using a hand markup that indicates insertions ar.d deletions. If the area being revised is not clear, the affected portion of the page is circled. The markup techniques vary as necessary, based on the specifics of the area being changed and the complexity of the changes, to provide the clearest possible indication of the changes.

6. A marginal note (the Additional Information Number from the index) is added in the right margin of each page being changed, adjacent to the area being changed, to identify the source of each change.

7. Some changes are not applicable to one licensee but still require changes to the Tables I

provided in Enclosures 3A,38,4,6A, and 6B of the original license amendment request to reflect the changes being made by one or more of the other licensees. These changes are not included in the additional information for the licensee to which the change does not apply, as the changes are only for consistency, do not technically affect the request for that licensee, and are being provided in the additional information j being provided by the licensees for which the change is applicable. The complete set of j changes for the license amendment request will be provided in a licensing amendment request supplement to be provided later. L

. to TXX-98195 Page 4 of 4 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION (continued)

8. The item numbers are formatted as follows:

[ Source][ITS Section]-[nnn] Source = Q - NRC Question CA-AmerenUE DC-PG&E WC-WCNOC CP - TU Electric TR - Traveler ITS Section = The ITS section associated with the item (e.g.,3.3), if all sections are potentially impacted by a broad change or set of changes, "ALL"is used for the section number. nnn = a three digit sequential number or ED (ED indicates editorial correction with no impact on meaning) I r I L J

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 2.0.G-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 2.0.x Bases General There have been a number of instances that the specific changes to the STS Bases are not properly identified with redline or strikeout marks. l Comment: Perform an audit of all STS Bases markups and identify instances where additions and/or deletions of Bases were not properiy identified in the original submittal. ) FLOG response: The submitted ITS Bases markups for Section 2.0 have been compared to the STS Bases. Some differences that were identified were in accordance with the markup methodologies (e.g., deletion of brackets and reviewer's notes). Most of the differences were editorial in nature and would not have affected the review. Examples of editorial changes are: i 1) Capitalizing a letter with only a " redline" but not striking out the lower case letter that it replaced. 2) Changing a verb from singular to plural by adding an "s" without " redlining" the "s". 3) Deleting instead of striking-out the A, B, C,.. etc. following a specification title (e.g., SR3.6.6A.7). 4) Changing a bracketed reference (in the reference section) with only a " redline" for the new reference but failing to include the strike-out of the old reference. 5) In some instances the brackets were retained (and struck-out) but the unchanged text within the brackets was not redlined. 6) Not redlining a title of a bracketed section. The methodology calls for the section title to be redlined when an entire section was bracketed. 7) Additional text not contained in the STS Bases was added to the ITS Bases by the lead FLOG member during the development of the submittal. Once it was determined to not be applicable, the text was then struck-out and remains in the ITS Bases mark-up. Differences of the above editorial nature will not be provided as attachments to this response. The pages requiring changes that are more than editorial and are not consistent with the markup methodology are attached. ATTACHED PAGES: None l

l \\ l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 2.0-2 APPLICABILITY: CP, DC, DC, WC REQUEST: NUREG-1431 Bases (markup) B 2.1.1 Reactor Core SLs (Callaway and Comanche Peak [pages 2.0-3]) Comment: The SAFETY LIMITS refer to Figure B 1.1.1-1. This figure was not included in the B 2.1.1 markup of NUREG-1431. Provide Figure B 1.1.1-1. FLOG Response: The FLOG has carefully examined the use of examples and typical information in the Bases of i the ITS. The intent of these examples and typicalinformation is to clarify the meaning of the Bases and thus the meaning of the ITS. In some cases, the examples and typicalinformation may create a human factors problem. If an example or typical information is not identical to the ITS, the operator may become confused and inadvertently use the infc.mation in the Bases. l Although this scenario should be unlikely, the value of the clarification provided must be weighed against the possibility and consequences if an operator error is induced. For the subject figure, it was the best judgement of the licensees that the typical information j provided in the STS Bases figure should not be included in the ITS Bases and the figure is being intentionally deleted. Callaway and Comanche Peak removed the figure in their initial submittals. Diablo Canyon and Wolf Creek have revised the ITS Bases to reflect deletion of this figure from the ITS Bases. l l I ATTACHED PAGES: None. ~ I i 9 J

l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 2.0-3 APPLICABILITY: CA, CP, DC, WC REQUEST: NUREG-1431 Bases (markup) i B 2.1.2 RCS Pressure SL (All FLOG Plants [Callaway and Diablo Canyon [page B 2.0-8], Comanche Peak [page B 2.0-7), and Wolf Creek (page B 2.0-9]) Comment: The APPLICABLE SAFETY ANALYSES has been revised to include,"..The transient that establishes the required relief capacity, and hence valve size requirements and lift settings, is a comp lct; less of cxicinal lced turbine. trip without a direct reactor trip. Cases with and without pressurizer spray andf0RVs:are ana_lyzed; Our n;; the tran;; cat, no contr;l actlons arc assurned, cxcept that the Safety valves on the secondary plant side are assumed to open when the steam pressure reaches the secondary plant safety valve settings, en+nemtnel Main feedwater supply is maintained. lost at the time of turbine trip;. Justify the revised STS Bases 2.1.2 changes. FLOG Response: These mark-ups directly reflect plant-specific accident analyses discussed in FSAR Chapter 15. Plant Soecific Discussion FSAR Section 15.2.2 states the following: "A loss of extemal load event results in a Nuclear Steam Supply System transient that is less severe than a turbine trip event (see Section 15.2.3). Therefore, a detailed transient analysis is not presented for the loss of external load event." As such, the ITS Bases were revised to reflect the turbine trip analyses. FSAR Section 15.2.3.2 specifically states that main feedwater flow is terminated at the time of turbine trip and that cases with and without pressurizer spray and PORVs are analyzed. Copies of pertinent FSAR pages are attached for information. ATTACHED PAGES: CPSES FSAR pages 15.2-4 through 15.2-9 l [

CPSES/FSAR The steam generator safety valve capacity is sized to remove the steam flow at the engineered safety features rating (105 percent of steam flow at rated power) from the steam generator without exceeding 110 percent of the steam system design pressure. The pressurizer safety valve capacity is sized based on a complete loss of heat sink with the plant initially operating at the maximum calculated turbine load along with operation of the steam generator safety valves. The pressurizer safety valves are then able to relieve sufficient steam to maintain the RCS pressure within 110 percent of the RCS design pressure. Q212.127 80 A more complete discussion of overpressure protect!an can be found in Reference [1], which also provides the bases for establishing the capacities of-.the steam generator and pressurizer safety valves. A loss of external load is classified as an ANS Condition II event, fault of moderate frequency..See Section 15.0.1 for a discussion of Condition II events. A loss of external load event results in a Nuclear Steam Supply Sys: transient that is less severe than a turbine trip event (see Section 15.2.3). Therefore, a detailed transient analysis is not presented fo the loss of external load. The primary side transient is caused by a decrease in heat transfer capability from primary to secondary due to a rapid termination of steam flow to the turbine, accompanied by an automatic reduction of feedwater flow (should feed flow not be reduced, a larger heat sink would be available and the transient would be less severe). Termination of steam flow to the turbine following a loss of external load occurs due to automatic fast closure of the turbine control valves in approximately 0.3 seconds. Following a turbine trip event, termination of steam flow occurs via turbine stop valve closure, which occurs in approximately 0.1 seconds. Therefore, the transient in primary pressure, temperature, and water volume will be less severe for the loss of external load than for j the turbine trip due to a slightly slower loss of heat transfer capability. 15.2-4 August 31, 1994 L_-_______

CPSES/FSAR The protection available to mitigate.the consequences of a loss of external load is the same as that for a turbine trip, as listed in Table 15.0-6. 15.2.2.2-Analysis of Effects and Consequences Refer to Section 15.2.3.2 for the method used to analyze the limiting . transient (turbine trip) in this grouping of events. The results of the turbine trip event analysis are more severe than those expected for the loss of external load, as discussed in Section 15.2.2.1. Normal reactor control systems and engineered safety systems are not required to function. The Auxiliary Feedwater System may, however, be automatically actuated fo*10 wing a loss of main feedwater; this will further mitigate the effects of the transient. Q212.65 The Reactor Protection System may be required to function following a - complete loss of external load to terminate core heat input and prevent departure from nucleate boiling (DNB).. Depending on the magnitude of the load 10ss, pressurizer' safety valves and/or steam generator safety valves may be required to open to maintain system pressure below allowable limits. No single active failure will prev.ent operation of any system required to function. Refer to Reference [2] for a discussion of anticipated transients without trip (ATWT) considerations. 15.2.2.3 Conclusions Based on results obtained for the turbine trip event (Section 15.2.3) and considerations d6 scribed in Section 15.2.2.1, the applicable acceptance criteria for a loss of external load event are met. l l 15.2-5 August 31, 1994

CPSES/FSAR 15.2.3 TUR8INE TRIP 15.2.3.1 Identification of Causes and Accident Descriotien 77 For a turbine trip event, the reactor would be tripped directly (unless below approximately 50 p;rcent power) from a signal derived from the turbine stop emergency trip fluid pressurt and turbine stop valves. The turbine stop valves close rapidly (typically 0.1 seconds) on loss of trip fluid pressure actuated by one of a number of possible turbine trip signals. Turbine trip initiation signals include:

1. Generator trip.

2. Low condenser vacuum.

3. Loss of lubricating oil.

4. Turbine thrust bearing failure.

5. Turbine overspeed.

6. Main steam reheat high level.

7. Manual trip.

Upon initiation of stop valve closure, steam flow to the turbine stops 77 abruptly. Sensors on the stop valves detect the turbine trip and initiate steam dump and, if above 50 percent power, a reactor trip. The loss of steam flow results in an almost immediate rise in secondary system temperature and pressure with a resultant primary system transient as described in Section 15.2.2.1 for the loss of external load event. A slightly more severe transient occurs for the turbine trip event due to the more rapid loss of steam flow caused by the more rapid valve closure. The automatic steam dump system would normally accommodate the excess steam generation. Reactor coolant temperatures and pressure do not significantly increase if the steam dump system and pressurizer pressure control system are functioning properly. If the turbine condenser were not available, the excess steam generation would be dumped to the I I i 15.2-6 i August 31, 1994 i

CPSES/FSAR atmosphere and main feedwater flow would be lost. For this situation feedwater flow would be maintained by the Auxiliary Feedwater System to ensure adequate residual and decay heat removal capability. Should the steam dump system fail to operate, the steam generator safety valves may lift to provide pressure control. See Section 15.2.2.1 for a further discussion of the transient. A turbine trip is classified as an ANS Condition II event, fault of moderate frequency. See Section 15.0.1 for a discussion of Condition II events. A turbine trip event is more limiting than loss of external lcad, loss of condenser vacuum, and other turbine trip events. As such, this event has been analyzed in detail. Results and discussion of the analysis are presented in Section 15.2.3.2. The plant systems and equipment available to mitigate the consequences of a turbine trip are discussed in Section 15.0.8 and listed in Table 15.0-6. I 15.2.3.2 Analysis of Effects and Ccnsecuences j i i Method of Analysis 1 In this analysis, the behavior of the unit is evaluated for a complete 84 loss of steam load from full power without direct reactor trip. This is done primarily to show the adequacy of the pressure relieving devices j and also to demonstrate core protection margins; that is, the turbine is assumed to trip without actuating all the sensors for reactor trip on the turbine stop valves. The assumption delays reactor trip until ctanditions in the RCS result in a trip due to other signals. Thus, the analysis assumes a worst transient. In addition, no credit is taken for steam dump. Main feedwater flow is terminated at the time 1 15.2-7 August 31, 1994 l l -

CPSES/FSAR of turbine trip, with no credit taken for auxiliary feedwater ) mitigate the consequences of the transient. { 92

The turbine trip transients are analyzed using the methodologies described in Appendices 4A and 48 for Units 1 and 2 respectively.

Major assumptions are summarized below: l

1. Initial operating conditions

) f 92 84 The initial reactor power and RCS temperatures are assumed at their maximum values consistent with steady state full power operation i including allowances for calibration and instrument errors. The initial RCS pressure is assumed at a minimum value consistent with steady state full. power operation including allowances for calibration and. instrument errors. This results in the maximum power difference for the load ' loss, and the minimum margin to core 84 protection limits at the initiation of the accident. For Unit 2, the initial reactor power, pressure, and RCS temperatures are assumed to be'at their nominal values consistent with steady state full power 92 operation. l Amendment 92 15.2-8 August 31, 1994

CPSES/FSAR

2. Moderator and Doppler coefficients of reactivity

. The turbine trip is analyzed with both maximum and minimum reactivity' 84 feedback. The maximum feedback (EOL) cases assume a large negative 92 i moderator temperature coefficient and the most' negative Doppler [ coefficient. The minimum feedback (BOL) cases' assume the most positive moderator temperature coefficient and the least negative Doppler coefficient.

3. Reactor control From the standpoint of the maximum pressures and minimum DNSRs 84 attained, it is conservative to assume that the reactor is in manual control. If the reactor were in automatic control, the c:ntrol rod banks :would move prior to trip and reduce the severity of the transient.

4. Steam release

.No credit is taken for the operation of the steam dump system or steam generator power operated relief valves. The steam generator pressure rises to the safety valve setpoint where steam release through safety valves limits secondary steam pressure at the setpoint value. . Pressurizer spray and power operated relief valves Two cases for both the minimum and maximu i reactivity feedback cases 84 are analyzed: Full credit is taken for the effect of pressurizer spray and a.. power operated relief valves in reducing or limiting the coolant pressure. Safety valves are also available. b. No credit is taken for the effect of pressurizer spray and power operated relief valves in reducing or limiting the coolant pressure. Safety valves are operable. Amendment 92 15 F 9 August 31, 1994 l l

[ t I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 2.0-001 APPLICABILITY: CP REQUEST: Corrects the plant specific hydrostatic test pressure for RCS components to be 3107 psig instead of 3110 psig in the Background section of Bases 2.1.2. ATTACHED PAGES: Enci 58 B 2.0-6

RCS Pressure SL B 2.1.2 B 2.0 SAFETY LIMITS (SLs) B 2.1.2 Reactor Coolant System (RCS) Pressure SL BASES BACKGROUND The SL on RCS pressure protects the integrity of the RCS against overpressurization. In the event of fuel cladding failure, fission products are released into the reactor coolant. The RCS then serves as the primary barrier in preventing the release of fission products into the atmosphere. By establishing an upper limit on RCS pressure, the continued integrity of the RCS is ensured. According to 10 CFR 50, Appendix A, GDC 14. " Reactor Coolant Pressure Boundary," and GDC 15. " Reactor Coolant System Design" (Ref. 1), the reactor pressure coolant boundary (RCPB) design conditions are not to be exceeded during normal operation and anticipated operational occurrences (A00s). Also, in accordance with GDC 28, " Reactivity Limits" (Ref.1), reactivity accidents, including rod ejection, do not result in damage to the RCPB greater than limited local yielding. The design pressure of the RCS is 2500 p;ia. 2485jpsjg; During ) normal operation and A00s, RCS pressure is limited from exceeding the design pressure by more than 10%, in accordance with Section III of the ASME Code (Ref. 2). To ensure system integrity, all RCS components are hydrostatically tested - m 2.0 ool at 125% @3103ps19), of design pressure, accoraing to the ASME coae requirements prior to initial operation when there is no fuel in the core. Following inception of unit operation, RCS components shall be pressure tested, in accordance with the requirements of ASME Code, Section XI (Ref. 3). Overpressurization of the RCS could result in a breach of the RCPB. If such a breach occurs in conjunction with a fuel cladding failure, fission products could enter the containment atmosphere, raising concerns relative to limits on radioactive releases specified in 10 CFR 100, " Reactor Site Criteria" (Ref. 4). ~ APPLICABLE The RCS pressurizer safety valves, the main steam safety valves SAFETY ANALYSES (MSSVs), and the reactor high pressure trip have settings established to ensure that the RCS pressure SL will not be exceeded. (continued) CPSES Mark-up ofNUREG-lul Bases -ITS 2.0 B 2.0-6 7/2988

7 l l l to TXX-98195 Page 1 of 4 JLS CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS CTS 3/4.0 - LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ITS 3.0 - LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY / SURVEILLANCE REQUIREMENT (SR) APPLICABILITY RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION AND LICENSEE INITIATED ADDITIONAL CHANGES i 9

_ _ _ _ _ ___ __ _ ____ _ __ _ _ _ - _ _ - _ _ to TXX-98195 Page 2 of 4 INDEX OF ADDITIONAL INFORMATION ADDITIONAL INFORMATION APPLICABILITY ENCLOSED NUMBER 3.0.G-1 DC, CP, WC, CA YES 3.0-1 DC, CP, WC, CA YES . 3.0-2 CP YES 3.0-3 DC, CP, WC, CA YES 3.0-4 DC, CP, WC, CA YES 3.0-5 DC, CP, WC, CA YES 3.0-6 DC, CP, WC, CA YES 3.0-7 DC NA DC 3.0-001 DC NA TR 3.0-001 DC, CP, WC, CA YES TR 3.0-002 DC, CP, WC, CA YES 4 4 l e e i l . j to TXX-98195 Page 3 of 4 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION The following methodology is followed for submitting additional information:

1. Each licensee is submitting a separate response for each section.

2. If an RAI does not apply to a licensee (i.e., does not actually impact the information that defines the technical specification change for that licensee), "NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee.

3. If a licensee initiated change does not apply,"NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee.

4. The common portions of the " Additional Information Cover Sheets" are identical, except for brackets, where applicable (using the same methodology used in enclosures 3A,3B, 4,6A and BB of the conversion submittals). The list of attached pages will vary to match the licensee specific conversion submittals A licensee's FLOG response may not address all applicable plants if there is insufficient similarity in the plant specific responses to justify their inclusion in each submittal. In those cases, the response wii!

be prefaced with a heading such as " PLANT SPECIFIC RESPONSE..... "

5. Changes are indicated using the redline / strikeout tool of Wordperfect or by using a hand markup that indicates insertions and deletions. If the area being revised is not clear, the affected portion of the page is circled. The markup techniques vary as necessary, based on the specifics of the area being changed and the complexity of the changes, to provide the clearest possible indication of the changes.

I

6. A marginal note (the Additional information Number from the index) is added in the right margin of each page being changed, adjscent to the area being changed, to identify the source of each change.

7. Some changes are not applicable to one licensee but still require changes to the Tables provided in Enclosures 3A,3B,4,6A, and 6B of the originallicense amendment request 1

to reflect the changes being made by one or more of the other licensees. These changes are not included in the additional information for the licensee to which the change does not apply, as the changes are only for consistency, do not technically l affect the request for that licensee, and are being provided in the additional information being provided by the licensees for which the change is applicable. The complete set of changes for the license amendment request will be, provided in a licensing amendment request supplement to be provided later. l 1 l lC____________.__________________

c l i to TXX-98195 Page 4 of 4 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR l FROVIDING ADDITIONALINFORMATION (continued)

8. The item numbers are formatted as follows:

(Source] (lTS Section]-{nnn) Source = 0 - NRC Question CA - AmerenUE DC-PG&E WC - WCNOC CP - TU Electric TR - Traveler ITS Section = The ITS section associated with the item (e.g.,3.3). If all sections are potentially impacted by a broad change or cet of changes, 'ALL" is used for the section number. nnn = a three digit sequential number or ED (ED indicates editorial correction with no impact on meaning) 1 l l l l L__________.__.__________________

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL IMORMATION NO: 3.0.G-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.0.x Bases General There have been a number of instances that the specific changes to the STS Bases are not properly identified with redline or strikeout marks. Comment: Perform an audit of all STS Bases markups and identify instances where additions and/or deletions of Bases were not properly identified in the original submittal. FLOG response: The submitted ITS Bases markups for Section 3.0 have been compared to the STS Bases. Some differences that were identified were in accordance with the markup methodologies (e.g., deletion of brackets and reviewer's notes). Most of the differences were editorial in nature and would not have affected the review. Examples of editorial changes are: 1) Capitalizing a letter with only a " redline" but not striking out the lower case letter that it replaced. 2) Changing a verb from singular to plural by adding an "s" without " reclining" the "s". 3) Deleting instead of striking-out the A, B, C,.. etc. following a specification title (e.g., SR3.6.6A.7). 4) Changing a bracketed reference (in the reference section) with only a " redline" for the new reference but failing to include the strike-out of the old reference. 5) In some instances the brackets were retained (and struck-out) but the unchanged text within the brackets was not redlined. 6) Not redlining a title of a bracketed section. The methodology calls for the section title to be redlined when an entire section was bracketed. 7) Additional text not contained in the STS Bases was added to the ITS Bases by the lead FLOG member during the development of the submittal. Once it was determined to not be applicable, the text was then struck-out and remains in the ITS Bases mark-up. Differences of the above editorial nature will not be provided as attachments to this response. The pages requiring changes that are more than editorial and are not consistent with the markup methodology are attached. ATTACHED PAGES: Enct 5B B 3.0-6 Portions of STS bracketed text should have been redlined but were not

LCO Applicability B 3.0 BASES LC0 3.0.4 shall not pn. vent changes in MODES or other specified conditions (continued) in the Applicability that result from any unit shutdown. Exceptions to LC0 3.0.4 are stated in the individual Specifications. The_stexception,slaRotentr.1EintQ10DESloriother specified ~condLtions1n.ItheZAppl1cabilit.Ohegithegassociated ACTIONS 1to,belegter. didojnotfprovfde;foMontinuedioperation : for e anunlimited.petlodottime; Exceptions may apply to all the ACTIONS or to a specific Required Action of a Specification. LC0 3.0.4 is only applicable when entering MODE 4 from MODE 5, I MODE 3 from MODE 4, MODE 2 from MODE 3, or MODE 1 from MODE 2. Furthermore LCO 3.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODES 1, 2, 3, or 4. The requirements of LCO 3.0.4 do not apply 1 in MODES 5 and 6, or in other specified conditions of the J Applicability (unless in MODES 1, 2, 3, or 4) because the ACTIONS of individual Specificatinne efficiently define the remedial measures to be taken. @some,casege.g., wheref a plant-specific.revie(has:conquum J,o specific restriction on MODE: changes should;benincluded1>tneseAyuntprovioe j o.3.o.a.1 _,e tnat stat.esj un ne2thjs.LC0;isinotisetEentryTinto a x MODE orlotherlspecjfi_edf, condition 1nithelAppljcability is not_ permitted!;unless2equired :to;complylwithiACTIONS.MThi Note;is a requirementLexplicitly' precluding ~ entry into a: MODE r o. ified conditionfof, the Applicability; 7 Surveillance do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, changing MODES or other specified conditions while in an ACTIONS Condition, in compliance with LCO 3.0.4 or where an exception to LCO 3.0.4 is stated, is not a violation of SR 3.0.1 or SR 3.0.4 for those Surveillance that do not have to be performed due to the associated inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO. LCO 3.0.5 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed ~ from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LC0 3.0.2 (e.g., to not comply with the applicable Required (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.0 B 3.0-6 7/29/98 L

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 3.0-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS SR 3.0.3 CTS SR 4.0.3 (All FLOG Plants) i-DOC 1-20-A Comment: The CTS Markups of CTS SR 4.0.3 for all FLOG plants do not accurately reflect - the ITS end product, SR 3.0.3 (ITS 3.0.3 is compatible with the STS and acceptable). Correct CTS Markup, or revise ITS Markup and provide justification. FLOG Response: The markups for CTS SR 4.0.3 and CTS SR 4.0.1 have been revised to be consistent with ITS SR 3.0.3 and ITS SR 3.0.1. The CTS markups have been revised to reflect moving CTS SR 4.0.3 phrases into CTS SR 4.0.1 and DOC 1-20-A revised to state: " Editorial changes to CTS SR 4.0.1 are made for consistency with NUREG-1431 SR 3.0.1. The CTS SR 4.0.3 phrase " Failure to perform a Surveillance Requirement... for a Limiting Condition of Operation." was moved to CTS SR 4.0.1 (ITS SR 3.0.1) to establish the relationship between Surveillance Requirements and meeting the requirements of the LCO. In addition, the words "except as provided in Specification 4.0.3" are added at the end of the moved sentence to retain the exception provided by the CTS markup of SR 4.0.3. The CTS SR 4.0.3 phrase " Surveillance Requirements do not have to be performed on inoperable equipment." was moved to CTS SR 4.0.1 (ITS SR 3.0.1) to establish the relationship between Surveillance requirements and meeting the requirements of the LCO. This phrase has also been modified to include variables not within limits since Specifications cover more than equipment (e.g., containment pressure)." CTS SR 4.0.3 is revised to specify required actions whenever the Surveillance Requirement l fails or whenever the delay period is exceeded. DOC 1-08-LS and NSHC LS-4 have been l modified to specifically address this change by adding the following words: "The CTS has been l revised to add the phrases "If the Surveillance is not performed within the delay period, the LCO l must immediately be declared not met, and the applicable Condition (s) must be entered." and "When the Surveillance is perforraed within the delay period and the Surveillance is not met, the l LCO must immediately be declared not met, and the applicable Condition (s) must be entered." to clarify the delay period." ATTACHED PAGES: Enct 2 3!4 0-3 Enci 3A 4 and 6 1 Enci 3B 3 Enci 4 47 l E-________-_.- ]

l l SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL H0 DES or other conditions specified for individual Limiting Conditions for Operation unless i otherwise stated in an individual Surveillance Requireme&/F,pj]urehperfqre l .i-mhawi2 - -melDE1pitht,3pMCtsggj y;5Gpt.e. fvaQdefined 120 A \\ l byiSpegffc.atjg, 2 fghal12coJMtj10tggglompltance TW1th3heLOPERRILITY a 3.0 1 l requirementsforia31stLWconditio[torloperation;exceptias;ptgvfdedlin I speciffcatjonsgEsurve111ance:geguiremets do~noEhate3ollEperfpraed;on inopetab1requipagg.tornattabits;outside;specified limits: l 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval. (NEW) For Frequencie,s specified as,"once,"sthe1above interval extension.does.not apply 2 un-u (NEW)3fia: Completion T.ime: requires. periodic; performance on:a ;"once'per ~.1.." bas.is;3the:above_Fre~ uengy extensionfappliesito.each performance,after the initial. q l. performance.' Exceptions to this requirement are stated in the individual specifications. .0.3 feilurc t; Frier; ; Survcilixx Requi ;nnt within th; elloucd 1 20 A surveillance intcrvel. dcfincd by Sgcification 4.0.2. ;h:11 ;;n;titut; e

• 0"E"#ILI"I ccquir;xnt; for : Li;iting Conditi;@3 0301 n;ncaplienz "raticfhe ti; li;1ts ;; :nc ra uun rcqu;r;xats ;rc ;pp;ica;c sc the ti;c ;; is idcatified th;t : Survcilience Rcquircxat h;; net bxn pcifer cd.

The ACTI0' requiri.nats xy bc del;ycd f;r up to 24 hours t; gr;it th; capletien of th; ;urveilixx unca th; ellcuable Outes; ti= li;;;its of the a' -"a AC'I0'! ccquirennt: ;re lxs then 24 h;;rs. QlEWDfJtgis3fiscovered that;a Suryelllance~yasspeggreedJtithinjits*spgcif;ted;F,tequency?$henicompliance Wittetheitequitengtiltg3laclate3hgLcolgot get; par b_eAlayed;*hom1the31me ofditscovery,1upitMB4'aWMdQD393bCMEltJpfd$hCspe,gifled1%lueg_cy? 1 20 A l WUIMNf3LD$$.$M1MkWIodMMtted las4MSperMWlof,Lt Q 3.0 1 l Surwa411ancagurve;;;;,_ ,y,,,. ,..,,3 ;; n,,; n;V; c; ;; gr;;cx; ;g;s, 6;xrd': r-icat f,- 2E -- _ ____2cc; =::pam l _._M18LcensilgggfegggggigllMg]gymppro!MgggCgs_t~d.maggia.te_ ~ i W--w yot2mmunigsthmaccRm82ammRIMon00MiettMd.1 1 08 LS 0 3.0 1 (h$t$$heWifle,}}}jER.7*N"'""" 'NJelayWe[gl@@d3bgMVlanc Cond 31 4.0.4 Entry into an OPE TIONAL H0DE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provirion shall not prevent passage through or to OPERATIONAL N00ES as required to comply with ACTION requirements drlth,at;are:part;oCa JMMd shutdoenlofithe70g11. Exceptions to these requirements are stated in the individual specifications. QlEH1SR 50Ed.s3!11y3pp11 cab],e.,forlentryMnto'a H0DErorrotherl.spegifi,_ed ryg ' ~ - conditioginithe gp}icabll,ityAMX!EEM2fM and,f t \\ l, CPSESMarkup ofCTS -3N.0 3M 0 3 7/29M8 O__-______-________________________

CHANGE NUMBER H$liC DESCRIPTION more consistent. The change still restricts performance of the surveillance to within 24 hours of discovery and is seen as acceptable, from the perspective of safety, as equipment is normally demonstrated OPERABLE. not inoperable via surveillance performance. ECTSihas beesastreDbNdOthe]phral$esRfit3LEurfitilanje]s 0 3.0 1 not3mtfaramrmtMoheJoelayant4cgshe3mwst Leggiat_e}y3gtylattd~riotTietzwrrd3Esppy_c= b]q a Cog (1gonsEbost Kentered.,"sppd LMthelSurve111ance ICPM9EmedTrf thin;theldela.t'psafodA!ditheJSuryijil ance isingimetHthelCQEenstfjamediatelyKdeclared,not metJ Q

a. dJhfapplicab.lel, Condition (s);mustL,beZentered."1to n

clarjfyjheldelay~per,1od. 1 09 LS 1 Surveillance Requirement 4.0.4 was previously applicable for entry into all MODES. The specification has been revised to not prevent unit shutdowns and will apply only to entry into MODES 1. 2. 3. and 4 from lower MODES. This change is less restrictive in that it will allow MODE changes from either direction into MODES 5 and 6 prior to the performance of Surveillance Requirements. As required in the " Reviewer's Note" of NUREG 1431 Rev.1. SR 3.0.4 a matrix is provided (see LS 1) which documents the plant-specific review of all specifications for determination of where specific restrictions on MODE changes or Required Actions should be included in individual LCOs. The change is acceptable for those specifications for which specific restrictions were not deemed warranted. 1-10 A Specification 4.0.5. the surveillance requirements for inservice testing, are moved to the Administrative i Controls Section 5.5.8 consistent with NUREG 1431. The reference to 10CFR50.55a is unnecessary and has been deleted. i 1 11 LG The portions of Specification 4.0.5 concerning Inservice Inspection are moved to the Inservice Inspection Program Plan. The requirements of 10CFR50.55a are adequate and j technical specifications are not necessary. l 1 12 A Consistent with NUREG 1431 Programs and Manuals section. ITS 5.5.8. the CTS is clarified to address the frequency (in days) for biennial requirements which was previously inferred but not explicitly stated in the CTS. j 1-13 A Adds applicability of 4.0.3 (SR 3.0.3 in improved TS) for Inservice Testing for consistency with the wording in NUREG-1431. In NUREG 1431. Inservice Testing is moved to l the Programs and Manuals section (ITS 5.5.8) and is no longer a surveillance requirement. Thus an explicit CPSES Description ofChanges - CTS 3M.0 4 7/29/98

CHANGE NUMBER NSHC DESCRIPTION 1 19 A Not applicable to CPSES. See Conversion Comparison Table '(Enclosure 38). 1 20 A o;nsister,t with "!RCO 1431. the phiese "er '3 "' variables cutsii :pcified limitr is ;did t; the stateur.; th;t survcill;nces i not hev; t; be prfered ;, ineprebic cquip.;r,t. This is net a technice; ch;n,c in thet "veriebies cutsin spcified limitt is as explicitly stated in the ITS whccees. in ths CTS. it w;s i;plicit in the ifinition of insprebic I

iF~nt.

Editot,al:changesito:CTSiSR:,4;0;1Lareloadelfor 1 consistencyMthiNUREGi1431;SRl3.0.1EJhelCTS: SR;4;0 ?3 phraseHfA110teLto:perfors a:Sutyeillance1Requjtementsl1 forlaELimiting;Condjtionlo(Opetationi"Zwasimoyedito1 CTS SR;440Ir.(IIESR10;1Ltolestablishitheitelationship betweenjSuryeilunce:Requirementslandseeting;the i j tequirementslofj the:LC0 Q In ' addition gthe;words5fexcept as;.;provided;jn:Specjficatjon3;0.3iare:;added atithe;end ofithe;movedisentenceito retajn:_the exceptjon:providedjby the:CTF sarkuplof ; SR14;0 ;3 lCThe; CTS;5R:4.0;3 phrase i "Surve11]anceRequirementsido p t;haveltolbe performed log i inoperable;equjpment t was: moved;to: CTS Sg:10;_11(IIS;SR 2 3.0g)ltolestab]1shithe;relattonshjp;between;Sutyeillance requirementDndiseetj ng' theitequire. mentsfof;the;LC0;g ThisIphCaseIhasiai so;been.:modittedjo;includelvatiable within 11 sits]sjnce2SpecificationsicoverCaoteithan equjpeent1(eig;*2co_ntainmentlpressureD li21 A Thelrequiltiment!thet:nponlfaildteltoimeet Lan L_C0] 0 3.0 5 - the: associated.;ACTLONiteqdirementsJhallibe' met? is:movediftselM:013IO711to;LC0J310,2;tolbe consistent]Mith'IthelSIS' organ,12atjon ofithe_se tequirementsj 1 l CPSESDescription ofChanges - CTS 3N.0 6 7/2988

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l l IV. SPECIFIC N0 SIGNIFICANT HAZARDS EVALUATIONS NSHC LS 4 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN T11E TECHNICAL SPECIFICATIONS This change is administrative in nature as the time allowed to perform a missed surveillance upon discovery is changed from up to 24 hours when the allowable outage time limits of the ACTION requirements are less than 24 hours. to the lesser of 24 l hours or the surveillance frequency interval. Additionally the equipment is not required to be declared inoperable at the time of discovery of a missed surveillance. This prevents unnecessary entry into Conditions based solely on equipment inoperabilities when the equipment is anticipated to be demonstrated OPERABLE by surveillance performance. The change is acceptable because it still restricts performance of the surveillance to within 24 hours of discovery and the equipment is normally demonstrated to be OPERABLE not inoperable by performance of the surveillance. The_ CTS has;,beenlevised.to. add the; phrases 7If the o.3,g.1 Surveillance _ejs not, performed within.;t. eidelay; period, the LCO must;immediately be h decl ared. notimet Cand_the appli cabl e1Condi tion ( s E must. be. entered. " ~ and.. "When the S_urvell. lance;'lis'. performed withinitheidelay,;periodiand the.Surysillance.is not met, the;LC0;sustjemediat. ly be; declared,not;metZand the applicab1_e: Condition (s) must e beientered."sto clarify;the_de.layLperiod/ j 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 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 frorn 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? Surveillance performance is nominally considered to demonstrate equipment operability. Therefore identifying that a surveillance has been missed l CPSESNo SignifwantHazards Consideration - CTS 3M.0 47 7/29/98 i u__________________._________

1 l ADDITIONAL INFORMATION COVER SHEET I ADDITIONAL INFORMATION NO: 3.0-2 APPLICABILITY: CP REQUEST: ITS SR 3.4.13.2 / Administrative Controls Section 5.5.9 CTS 4.0.6.4a (Comanche Peak) DOC 1-15-A Comment: The ITS revises the wording of CTS 4.0.6.4a.8. Is this also applicable to the other FLOG plants in which the location of this paragraph is CTS SR 3/4.4.5; is it generic? FLOG Response: The CTS change to 4.0.6.4a (Comanche Peak) is applicable to the other three plants (see DOC 5-03-A in ITS Section 3.4 for Callaway, Diablo Canyon, and Wolf Creek - CTS SR 4.4.5.4a.8)). In attachment 3 to their conversion submittals, Wolf Creek and Callaway correctly identified this change as a generic change not within the scope of a full conversion to the improved STS. Per a conference call with Jim Luehman on July 16,1998, an NRC review has already been initiated for this out-of-scope change. ATTACHED PAGES: None l t l ]

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 3.0-3 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS LCO 3.0.5 Bases (All FLOG Plants) Comment: The STS Bases has been revised to address "the performance of required testing" versus the " performance of SRs," to be consistent with the TS. Submit a TSTF to revise the STS. Suggest that the first instance this wording is to be revised to state,"the performance of required testing including applicable SRs," since testing to restore equipment to an operable state will frequently include the performance of SRs. l FLOG Response: The ITS LCO 3.0.5 Bases were revised consistent with traveler TSTF-165. l The latest status report from the TSTF industry database, dated July 27,1998, indicates that i the NRC has approved TSTF-165. The FLOG continues to pursue the changes approved in TSTF-165. ATTACHED PAGES: None l l l l l i l I i i e [.. l

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 3.0-4 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS SR 3.0.2 Bases (All FLOG Plants) Comment: Justify the revised STS SR 3.0.2 Bases. The STS provides an explanation for the inapplicability; the ITS does not. FLOG Response: The ITS SR 3.0.2 Bases were revised based on Traveler TSTF-52. Comment Number 3.6.1-6 for Section 3.6, " Containment Systems", concerned the revision of the submittal to conform to the 11/2/95 letter from C. Grimes (NRC) to D. Modeen (NEI) and TSTF-52 as modified by the NRC staff. In the FLOG response to Comment Number 3.6.1-6, it was identified that the iTS Bases were revised to incorporate proposed Revision 1 of TSTF-52. The FLOG response provided changes to the ITS SR 3.0.2 Bases based on incorporating proposed Revision 1 of TSTF-52. ATTACHED PAGES: None

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 3.0-5 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS LCO 3.0.1 & 3.0.2 ) CTS 3.0.1 & 3.0.2 (All FLOG Plants) { DOC 1-01-A Comment: The markup of CTS 3.0.1 and 3.0.2 do not agree with the markup of STS LCO 3.0.1 and LCO 3.0.2. The markup of STS LCO 3.0.1 and 3.0.2 are correct. Revise the CTS f markup. FLOG Response: { l The FLOG has re-examined the CTS markups for LCO 3.0.1 and 3.0.2. The ITS requirements are contained in the CTS markups but may not have been aligned with the same LCOs as in the ITS. Comanche Peak and Diablo Canyon have modified their CTS markups for LCOs 3.0.1 and 3.0.2 to line up the requirements with their corresponding ITS LCOs. DOC 1-21-A has been drawn to describe the modification. The CTS markups for Callaway and Wolf Creek are already lined up with the iTS and no additional modifications are required. ATTACHED PAGES: Enci2 3/4 0-1 and 3/4 0-2 Enci 3A 6 Enci 3B 3 f i 1 I - _ ~ - - - - - - _ _ _ - - - - - - - - - - - - -. - - - - - - - - _. - - - - - - - -

1 l 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l 3/4.0 APPLICABILITY l LIMITING CONDITION FOR OPERATION 3.0.1. Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required durina the OPERATIONAL MODES or other conditions <nacima thoroin g;cp; tt;t up;7, ;;;;;r; :; ;;;;;; ty; Li;;;it=; g ditions for Opcration. th; :s:ccieted ACTIO^l rcquir; x ats : hall bc c;t,3 IE E E l except.Js_fvnoen in LCD:3.u.quiu#ww.vg. 1 21.A 3 10ponj fai10re 'toTaeetitheysitjpg1ConditionsMor,0peration dthe 0 3.0 5 i ssociatedMIONTequirementstshaH_1bie tet 'onc plianc; with ; l

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i Condition for Operation is restored orlis no longeriapplic6ble prior to expiration of the specified time intervals. completion of the ACTION requirements is not required unle.sslotherwiselstated. 3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within i hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: a. At least HOT STANDBY within the next 6 hours, b. At least HOT SHUTDOWN within the following 6 hours, and c. At least COLD SHUTDOWN within the subsequent 24 hours. Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications. This specification is not applicable in MODE 5 or 6. 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements oc3h8tf5PeTpgr2NLgrgbytA3LnioGtheZGnit. Exceptions to IMtM3 these requirements are stated in the individual specifications. [NElHlLC03'.:0 ~42[sIgnh18pplis8bWomtrKintfCMXElotiptheQpecified g'aggyj CoDditj,oln ig;the~ApplicabilityjirCHODjSS,3,I3]Iand3) ~ CPSES Markup of CTS - 3N.0 3 M 0-1 7/29/98

LIMITING CONDITION FOR OPERATION 3.0.5 Li;iting C;ndition; f;r Ogration including the ;;seciated AC'!0" @~# requirc. cat; sh:11 opply to cxh unit indf sidually unics: other.;i;c indic;tcd as mi1m...

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CHANGE NUMBER ldE DESCRIPTION 1 19 A Not applicable to CPSES. See Conversion Comparison Table (Enclosure 38). 1 20 A 0;nsistent with E"tCC-1431. the phres; "er 0 3.04 verieblas outside spcified lirits" is added to th; stat;. cat th;t surveillenccs de not have to bc grferrcd ;7 inegr ble aquipcat. This i; not a technical chang in that "veriebles outside sgcified li;;;its" is new explicitly stated in th; ITS wherces, in the CTS. it was i;;;plicit in the definition of inegrebic equiFcat. Editotia11changesito1CTSiSRi4l0;1;areinadelfor consistencylWjth;NURE.Gi14311SR13:0 ;1GThelCTS;SR$.0.3, phrase 1Ifall q E perfpte_alSuryelllance~ Requirements m fotia: Limiting 1 condition::of;0peration:Das_moyed;to; CTS l SR X 0;1 XIISlSR13;0jl)1 tole. stab 11sh;the Relationship l between2Sutyejl]ance:Requitementsiand; meeting;the requirements [ofitheJCO.2Iniaddition 2the wrdsjexc.ept asJptoyidedliniSpecj fjcationl4;0J31:aretadded ;atitheiend ofithe;motedisegtenceyretain;the; exception prov.jded:by the;CTSimarkupZofiSRX0.31:iThelCTSiSR3 0.3~ phrase ISutveillance: Requirements do;notjhaveito;belperformed on inopetablezequjpment m as1 moved;to' CTS;SR310i1MITSiSR 31011)ltoiestab11shithelre]ationshjpibetweeg; Surveillance requirements"8ndineetjpg!,thelequirements;ofithe2LC03 This;phtaselhas31sohnodifieditolinglude; Variables;no I Within'1jaitsIsince SpecificationsIcovetimore than equjpment3eigi71contai.nmentfptessurep D m T. he.~re_q0. i. teme. _nt.i. t_ha_t.ruportf..a..i_l ur_.e t to__meetfan~ LC0;' 21 A ~ Q 3.0 5 l the3ssociated;AcrI00tequirementsis_ha111be met 2 js notedif_ rom;tc01310;11o?LC0i3r0:2:to'be consistentlmt;hltheLS]Sjorganizationlof;these reqotteeents; l CPSES Description ofChanges - CTS 3M.0 6 7/29/98

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ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: 3.0-6 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS LCO 3.0.4 CTS 3.0.4 (All FLOG Plants) DOC 1-02-LS1 Comment: The markup of CTS 3.0.4 does not agree with the markup of STS LCO 3.0.4. The markup of STS LCO 3.0.4 is correct. Revise the CTS markup. FLOG Response: The FLOG has re-examined the CTS markups for LCO 3.0.4. The actual markup vary slightly although the Comanche Peak markup is essentially identical to the Diablo Canyon markup, and the Wolf Creek markup is essentially identical to the Callaway markups. All four markup were found to mean the same and all four markups were found to be consistent with the ITS. The markup is slightly different but the meaning is identical. ATTACHED PAGES:

None, l

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR 3.0-001 APPLICABILITY: CA, CP, DC, WC REQUEST: Incorporate NRC-approved traveler TSTF-122 to climinate confusion in the ITS LCO 3.0.2 Bases that discuss inoperability of redundant equipment. ATTACHED PAGES: EnctSA Traveler page Enci5B B 3.0-2

INDUSTRYTRAVELERS APPLICABLE TO SECTION 3.0 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-06, Rev. 1 Incorporated 3.0 01 NRC approved. TSTF 08. Rev. 2 Incorporated NA l TSTF 12. Rev. 1 Incorporated 3.0 02 NRC approved. TSTF 52 Rev.;1 Incorporated Incorporated draft Rev 1.per 0 3.6.1 E Q 3.6.1-6 l TSTF-71 Rev.2 Not incorporated NA Will be addressed in SFDP TR-3.0 0C2 l l TSTr 100 Not i ncrporated NA PCrforE d 3.0.4 ";triX TR 3.0 0C2 l TSTF 104 Incorporated 3.0-03 NRC approved. T TSTF 122 Net-4 Incorporated NA Not NP,C Opprov;d :: Of TR 3.0 0C 1 l l travclcr cut-cif date. Approved.'byitl}eZNRC TSTF 136 Incorporated 3.0 02 Approvedgby-the aNRC m 3.0 0(2 i TSTF-165 Incorporated NA Appi%Ved3ylthle NRC TR 3.0-0(2 l TSTF-166 Incorporated 3.0 04 AppFdiFedibfitfidi?NRC TR 3.0-0C2 l 1

1 ) LCO Applicability B 3.0 l BASES LC0 3.0.2 ACTIONS.) The second type of Required Action specifies (continued) the remedial measures that permit continued operation of ?.he unit that is not further restricted by the Completion Time. In this case. compliance with the Required Actions provides an acceptable level of safety for continued operation. Completing the Required Actions is not required when an LCO is met or is no longer applicable, unless otherwise stated in the individual Specifications. The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Conditions no longer exist. The individual LC0's ACTIONS specify the Required Actions where this is the case. An example of this is in LC0 3.4.3, "RCS Pressure and Temperature (P/T) Limits." The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillance, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational c '"r9=9Alternati= thatAdd1tionat ivs1r intention 3h -===== j intn ~ ACTIONS @oulainetifresult in redirndant equipment m.3. j.ool inoperabl.7 native should be used instead. Doina so limits the time subsystems /tra a safety funct M.i are perable and limits the ti onditions exist whic esult in LC0 3.0.3 being entere. Individual Specificati ay specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed. When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another Specification becomes applicable. In this case, the Completion Times of the associated ~ Required Actions would apply from the point in time that the new Specification becomes applicable, and the ACTIONS Condition (s) are entered. i (continued) r l CPSES Mark-up ofNUREG-1431 Bases -ITS 3.0 B 3.0 2 7/2988 L i

ADDIT'ONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR 3.0-002 APPLICABILITY: CA, CP, DC, WC REQUEST: Revise Traveler Status page to reflect NRC approval and latest revision number of travelers TSTF-71 Rev. 2, TSTF-136, TSTF-165, and TSTF-166. Deleted TSTF-103 I from the Traveler Status pages as this traveler has been rejected by the NRC and accepted by the TSTF. There are no changes involved to any CTS mark-ups, ITS mark-ups, DOCS, or 1 JFDs. ATTACHED PAGES: Enc!SA Traveler page l I

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.0 1 1 TRAVELER # STATUS DIFFERENCE # COMMENTS l TSTF 06, Rev. 1 Incorporated 3.0 01 NRC approved. TSTF 'i8, tov. 2 Incorporated NA TSTF1N,Rev.1 Incorporated 3.0 02 NRC approved. TSTF 52 Revi 1 Incorporated Incorporated draft Rev 1.per 0 3.6.1-( Q 3.6.1 6 TSTF 7 Rev.2 Not incorporated NA Will be addressed in SFDP 'j!,m3.00C 2 ir103 t'ct ir,corporated NA Perforacd 3.0.4 tictrix m 3.0 oc2 h) TSTF 104 Incorporated 3.0 03 NRC approved. TSTF 122 Net-incorporated NA i;ct !;P,C approved a: of m 3.0 oci travckr cut off date. Approved.iby.,theiNRC I TSTF 136 Incorporated 3.0-02 MedEby'the].NRC m -3.0 0(2 %i TSTF-165 Incorporated NA AppgjgdbfithqNRC m 3.0 0(2 l i l TSTF 166 Incorporated 3.0 04 AppfoV4Lb?j;the'i' NRC m 3.0 0(2 J I L t _ _... _ _ _ _ _ _. _.. _ _ _ _ _ _ _ __ _ _ _.}}