Text

Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS
	ML20198J254
Person / Time
Site:	Comanche Peak
Issue date:	12/18/1998
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20198J241	List: ML20198J234; ML20198J254;
References
	NUDOCS 9812300122
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CHANGE NUMBER NSRC 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 ES-2A Table 1.2 of the current TS would become Table 1.11 in the improved TS. The following changes would be made to confoh.I 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 l 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 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 required al.1 reactor vessel head closure bolts are fully tensioned, and a new note c replaces the note 0 1.14 l applied to Mode 6. The new note c states that the required one or morefreactor vessel head closure bolts are less than fully tensioned. E] 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;in natures, except for the acw notc; b and c. added per TSTT SO and addrc;;cd in NS!!C ES 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 A_NQ and DB 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 l understanding completion times. Section 1.4 deals with the l proper use and interpretation of surveillance frequencies.

l 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 chanaev. incorporating travcicr; WOC 74 crG 0 1.4-1 c h .!ti T lf 270 3nd TSTI,2S7 _

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9812300122 981218 5 12/15/98 l PDR ADOCK 05000445 l P PDR

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l INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 l

l l TRAVELER # STATUS DIFFERENCE COMMENTS l l

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CPSESMark-up ofNUREG-IU1ITS-1.0 1e4-6 12/1588

l l JUSTIFICATIONS FOR DIFFERENCES FROM NUREG 1431 l

i Section 1.0 L 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 l numbers are referenced directly from the NUREG 1431 mark-ups. For enclosures 3A, 38, l 4, 6A and 6B, text in brackets "[ ]" indicates the information is plant specific and

! is not common to all the Joint Licensing Subcommittee (JLS) plants. Empty brackets indicate that other JLS plants may have plant specific information in that location.

l l CHANGE NUMBER JUSTIFICATION 1.1 1 The NUREG-1431 Rev.1 definitions of Channel CalibrationLChannel !

Operational 2 Test and1 Trip; Actuating Device 10perationaljTest use language;to describelthex scopefof testingLsimilar3tol states. "The 0-1.1 2 ,

ClTf!! L CALIBRATION shall encapss "the entire channel, including ;

the required sensor, alarm, interlock, display, and trip functions". The word " required"lislambiguouslandl subject?tola_1s_ interpretation asjto

( whetheritheilistLisiinclusive;or,representativeGThis change clarifies i what components;are included by!specify1ng "all.1.deviceslinLthe, channel requiredfor: channel3 0PERABILITY"EA;similariclarificationlis;provided j for;the Actuation Logi_c; Test.Z encepsscs the catirc channel by i

rewording the definition to state, "The ClTf!::L CALIBRATION shall l encavass those c_ycacats, such as sensors, alarms, displays, and trip functions, required to perfora the specified safety function (s)." The Channel Operational Test and Trip Actuating Sevice Operational Tcst definitions are similarly revised. This change is consistent with TSTF-205E64-1.1 2 Not used.

1.1-3 dnew exa;;;ple to ITS 1.4 to clarify meaning of SR notes of the type "Only required to be performed in tiODE..." This change is 0m consistent l l "ith traveler "00 74, Rcv 1 KTr;270. Not;used 1.1-4 Not used.

I.

l 1.1-5 The definitions for ESF Response Time and RTS Response Time are wetM l be revised to substitute the word " verified" in lieu of "reasured" 1

consistent with thc requirc; cats of NUREC 1431 SR 3.3.1.15 and SR 3.3.2.2. This changc ;;u?d casur: :asist:G:y bctucca th:

definiticas for Rcspca;c Ti;c and the requirc; cats to periodically

verify Rcspcasc Ti;c is within li;;;its. This changc is consistent with

TSTF-111.-Rev The?additionLofithe' statement that^responseLtimes for i selected components 1may.be; verified by other;means; approved by NRC11s

administrativelin; nature 3since[it; allows;no_ response time testing change l Unless NRC ~ approval; has; beenj fi rstiobtained 5This statement 11s consistent with;Section;5.3;4lof;IEEEl338fl977 6travelerfTSTF-111, and

approved; topical [ reports: onLresponse, time; testing verification methodologyi f

, CPSES Differencesfrenar u UREG-1D1 - ITS 1.0 1 12/15/98

--. - - --- - m - - -- - . - -

CHANGE NVMBER JUSTfFICATION the requirements contained in the PTLR. Referenced methodologies for l 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

[LTOP] setpoints. This change is consistent with Traveler WOC 57, Ree4;TSTF233. In additionathe PTLR: definition; includes;the.PORY lift. settingsiconsistent;with the traveler's;changel.to?ITS Section:5.5.6.

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

1.1-8 Not ; appl i cabl e l to; CPSESN See_ Conversion (Compari son LTabl e (enclosure 68); The reactor vcs el had closure bcit requirc;;ats 0 1.14 for "00ES 4. S and 5 arc clarified. The proposed chang; reviscs footnotc b for MODES 4 and S to refer to " Required reactor vessel had closure bcits fully tensioned" and notc c for "00E 5 is revised to rced

" Required reactor vessel had closure bcits icss than fully tensicacd."

l The transition point betu cn "00ES S and 5 would also b^ clarified-es i occurring when the required reactor vcssel head closure bcits arc less than fully tensioned. The rcquired number of closure bolts, which may L_ &_& 1 mm 1,___ & L. . .._ A L. m. _...L_ J L,..

J... _ m.

_ & .L. f. J. ..L. m_ mm . .1..,._J..

m. . ..m., . . . . &.L. &.

l dc;;nstretc3 adequate 0-ring comprcssica to prevcat icekage and ensures that AStiE Section !!! stress limits for affected ccaper. cats arc not

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I 1.1 9 Consistent with TSTF 205 30 Rev. 2, the definitions of Channel Operational Test (C0T),[ Master. Relay Test,1 Slave. Relay Test,- [] 0 1.1 1

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

j Performance of these tests in a series of sequential, overlapping, or i total channel steps provides the necessary assurance of appropriate j operation of the entee channel, relay or_ device,irespectively . This

! change also makes the COT. Haster; Relay Test,7 Slave;RelayiTest 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 6B).

1.1 11 Adm 6 cTd5p15'tc ITS Section l l ic~ciarU y su bcilla$ce '

frcqucacies that are contingcat on both a spccified frcquency and 0 1.4 1 plant conditions. The ITS contains many Survcilience Frcqucacies that are contingcat on both a "specified frequency" and plent conditions.

For cxampic, "Within 7 days prior to the initiation of Physics Tests."

! and " Prior to catering "00E 4 frca tiODE 5 if not perforacd within the previcus 02 days." Thesc Frequencies do not fall cicarly undcr any of the cxisting Sectica 1.4 cxampics. The proposed exampic is r.=dcd to ake cicar that 1) the SR 3.0.2 cxtension of 1.25 times the specified frequcacy app?ics tc the spccified Frequency. and 2' that the interva?

clicwcd to perform a missed Survcillance by SR 3.0.3 applics.-

SR 3.0.2 is cicar that the 1.25 extension may bc applied tc "the 4nterval specified in the Ircquacy". 30 the proposed change docs not changc the intent of the Specifications. SR 3.0.2 applics if a CPSES Differencesfrom NUREG-JD1 -ITS 1.0 2 12/1S/98 t

1 l CHANGE NUMBER JUSTIFICATION Surveillancc is not perforacd within the "specified ficqucacy". Agaier the example does act change the intent of the Specificaticas but caly j makcs clear the applicatica of SR 3.0.2 and 3.0.3 to Survcillances with

! frequencies ticd to plant conditions. This change will climinate l

confusion and misapplicatica of the ITS and will casure ccasistent application of SR 3.0.2 and 3.0.3 to thcsc types of Survcilienee frequcacics. This changc is consistent with travalcr "00 00.

.r.ewr-

.. y ,.;Not used or,--

0 1.4 1 1;1312 The definitiontof DWmtLJALIBRATIONjis; s revised:to move details of RTDLand thermoccuple calibrationito the;TS 3.3 Bases associated with:the: components] consistent withiTSTF-19.? m 1.0 006 l'.1113 deletes the definition of Traveler.:TSTF52,~draftRcvi;ica1,lAppendixJandlITS;Section

~

Lt. - Since. L :is defined _in;10CFR50 0 3.6.1 6

5. 5 16,1 Containment: Leakage . Rate, Testing Program,iit i s j redundant to include,Lgl.asfa definition.JAs; described in NUMARC193 03;

" Writers,. Guide for.ithe. Restructured Technical.DSpecifications',1 SpecificationL1,:111s::a: list of defined; terms and: corresponding 1 definitions used throughout.the. Technical Specifications. fL/11s not i used throughout. the;Technicaljspecifications andt is' defined'in.Section 5.5 16..

CPSES Differencesfrom NUREG-1431 -ITS 1.0 3 12/15/98

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG 1431 - SECTION 1.0 Page 1 of 2 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 1.1 1 This change would clarify t;;t :ncc.4;:;;c; thc a*tre Yes Yes Yes Yes channcl by rc ;;-ding the definitions of tMtatc. "Thc CHANNEL CALIBRATION.00Tf and TADOT ehe11 c..cm.s;;; by replacing the existing'ambiguousYJrdingLwith *all devices'in the channel' required for channel 0-1.1-2 l OPERABILITY. ,,.m . -rm _ . . . m. m ., ~ . . . .

sion;;;. display;. an? :-ip functions, ccquircd to i pcifon;; thc ;pccificd ;;fcty functionM8 The Actuation Logic; Test' COT :nd S DOT definitions-eee is similarly revised.

1.1-2 Not used NA NA NA NA 1.1-3 6 nc.; cxa plc to ITS 1.4 to cl;r'fy ac;ning of T VesNA VesM VesNA Veh _-

notc; cf thc typc "0-13 ; cquircd to bc pcrfor;;.cd in g 0-1.4-1

" -00[.

~~ - "."atased ~

1.1-4 Not used N/A N/A N/A N/A 1.1-5 The definitions for ESF Response Time and PTS Response Yes Yes Yes Yes

. ,,,.mm

.. [,2*

,,,,m

m. ..m m . s u !5_ f '((^N..e.

mmm.., ..m_

um l 0-1.1-4 l

cqui, m.~ct; cf N""EC l'31 5" 3.3.1.10: nd Sa 3.3.2.10.

1.1-6 The definition of the Pressure and Temperature Limits Yes Yes Yes Yes !

Report would be revised to include the 53ximum allowable PORV lift settings and the arming temperature associated with the system, and to be ,

consistent with the COLR definition, 1.1-7 The definition of Channel Functional Test in the Yes No - Not part No - Not part No - Not part current TS will be retained in the improved TS. This of current TS. of current TS. of current definition is not in NUREG-1431 Rev 1. TS.

CPSES Conversion Contparison Table - ITS1.0 12/158 8

CONVERSION COMPARISON TABLE FOR NUREG-1431 DIFFERENCES SECTION 1 Page 2 of 2 NUMBER DESCRIPTION DIABLO CANYON COMANCH PEAK WOLF CREEK CALLAWAY 1.1-8 In a Callawayt specific' change.lNote b is revised to VesNo YesNo VesNo Yes refer to the " Required reactor vessel head closure bolts fully tensioned" and note c is revised to read

" Required reactor vessel head closure bolts less than lQ.1.19 l fully tensioned."

1.1-9 The definitions of Channel Operational Test (C0T). Yes Yes Yes Yes Master Relay Test.~ Slave Relay Test; [ ] and Trip Actuating Devica Operational Test (TADOT) are expanded to include the details of acceptable performance 0-1.1-1 methodology. Performance of these tests in a series of sequential, overlapping. or total channci steps provides the necessary assurance of appropriate operation of the entire channel. relay orLdevice; respectively.

1.1-10 This change is based on the current TS definition of No - Not part No - Not part No - Yes CONTROLLED LEAKAGE. This change is a clarification of CTS. of CTS. Maintaining only and does not affect the way RCS water inventory ISTS wording.

balances are performed.

5]S_ E.m_ ((!) _!I,. I. I.w._m).

_M_5III. wm 0-1.4-1

< _t-h-

. . m . . . m mm ..m ..m mm. m_. .~

j Q f.c yc.cy and plant condition;. Not used 1.1-12 The , defi ni tion ' o f CHANNELL CALIBRATION ..is ' revi sed ' to Yes Yes Yes Yes move details'of'RTD and thermocouple calibration to TR-1.0-006 l the TS 3.3 Bases associated with the components consistent with TSTF-192 1.1-13 Traveler TSTF-52;1 draft Pcvi;ica 1. deletes the Yes Yes Yes Yes definition'of L(. Since L is defined;1n;10CFR50' 0-3.6.1-6 Appendix'J and ITS Section 5.5-16._ Containment Leakage Rate Testing Progras;"it is redundant to include Lfas a definition; CPSES Conversion Comparison Table - ITS 1.0 12/15198

ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: O 3.1-25 APPLICABILITY: CA, CP, DC, WC l

REQUEST: ITS 3.1.4 Rod Group Alignment Limits (All FLOG Plants)

JFD 3.1-16 l Comment: Inclusion of SR 3.2.1.2 to Required Action B.2.4 is approved; ensure OG submit WOG-105 as a TSTF change request.

FLOG Response (original): At the June 23-24,1998 meeting of the Westinghouse Owners Group MERITS Mini-Group, traveler WOG-105 was discussed. The remaining action on this traveler was assigned to Westinghouse to expand this change to also apply to ISTS 3.2.1 A, "Fo l (Z) (F,y Methodology)." However, this additional work has no impact on the manner in which the FLOG has incorporated this traveler's additional restriction. The TSTF will be submitted to NRC expeditiously.

FLOG Response (supplemental): WOG-105 has not become an NRC approved traveler in time to be incorporated into the license amendments for the FLOG. In lieu of incorporating this traveler, the STS markup and ITS is being justified based on the CTS. In the CTS, the associated action requires that the Heat Flux Hot Channel Factor be verified without specifying

! whether the steady state value (FoC) or the transient value Fo* or both are the correct values to be verified. The CTS has been understood to require the verification of both values and the ITS is hereby revised to match this understanding of the CTS.

ATTACHED PAGES:

Attachment 7, CTS 3/4.1 - ITS 3.1, Reactivity Control Systems )

i EnctSA Traveler Status Sheet (second page)

Enci 6A 3 Encl 6B 2 !

Attachment 8, CTS 3/4.2 - ITS 3.2, Power distribution Limits EnclSA Traveler Status Sheet Enci 6A 4 l

1 i

i e

i l

l l

TSTF-142 Net-Incorporated 3.1122;NA NRC; approved;J; Traveler l isouwu u 4..._2 . c. _ - . . . e i sm w u ,.vif TR 3.1 003 i

t e avu ,.,s,,.--

n _..

Tr"Pr ' ene a

...uu yv uowu W. CI' 3*1 002 M *' ! '. 69 :- . :~ ~. ~.: .: - '

mi i

n, .14 vvwnne 0 3.1 20 1

A !

> 1 l

tu nvu a v .,

ne v________._;

.iivviyu.uwuu g -

-- 0 3.1-25 j

i l

I l

l l

i 1

1 l

I i

I l

a l

l i

CHANGE NUMBER JUSTIFICATION 3.1-11 Not Used.

3.1 12 The Required Actions for inoperable DRPI in ITS 3.1.7 are revised per the current licensing basis to note that the use of movable incore detectors for rod position verification is an indirect assessment at best. The position of some rods can not be ascertained by this method.

3.1-13 This change adds an LC0 requirement and SR to MODE 2 Physics Tests Exceptions 3.1.8 to verify that thermal power is less than or equal to 5 percent RTP. The LC0 requirement and SR were added to verify that THERMAL POWER is within the defined power level for MODE 2 during the performance of Physics Tests, since there is an !

Action that addresses THERMAL POWER not within limit yet there was no corresponding LC0 or surveillance requirement. The Surveillance Frequency of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is retained from the i current TS. This change is based on TSTF-14, Revisicr 3. m.3.1 005 3.1-14 Not used.

i l 3.1 15 Consistent with TSTF 12 Revision 1. ISTS LCOs 3.1.9 and 3.1.11 are l l

deleted. The physics tests contained in LC0 3.1.9 were only I j contained in some initial plant startup testing programs. The physic test exception can be deleted since these physics tests are never performed during post refueling outages. The physics test that LC0 3.1.11 required was the Rod Worth Measurement in the N 1 condition. The use of other rod worth measurement techniques will maintain the shutdown margin during the entire measurement process i

and still provide the necessary physics data verification. Since l the N-1 measurement technique is no longer used, the SDM test l exception can be deleted. This change and traveler TSTF-136 renumbers ISTS 3.1.10 to ITS 3.1.8.

3.1-16 This change adds the requirement to perform SR 3.2.1.2 in addition to SR 3.2.1.1 during performance of ITS 3.1.4 Required Action

! B.2.4. The intent of Required Action B.2.4 is to verify that Fa(Z)

is within its limit. Fo(Z) is approximated by Fj(Z) (which is i obtained via SR 3.2.1.1) and F#(Z) (which is obtained via SR

3.2.1.2). Thus, both Fj(Z) and F#(Z) must be established to verify j Fa(Z) . This change is consistent with @ CTS.jttavcicr "00 10 Q 0 3.1-25 3.1 17 Consistent with current TS LC0 3.1.3.2. ITS 3.1.7 Condition C is clarified to state that the inoperable position indicators are inoperable DRPIs.

3.1-18 A MODE change restriction has been added to ITS 3.1.1. in the LC0 applicability, per the matrix discussed in CN 1-02-LS 1 of the 3.0 package. LC0;3.0.4 has!been: revised so that changes 0 3.1 27 in_H0 DES;orio_therispecified: conditions;in the, Applicability CPSESDifferencesfrom NUREG-1431 -ITS3.1 3 12/15/98

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.1 Page 2 of 3 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.1-10 Several surveillances (e.g., rod position deviation monitor and rod Yes Yes Yes Yes insertion limit monitor in this section) contain actions in the form of increased surveillance frequency to be performed in the event of inoperable alarms. These actions are moved from the TS to licensee controlled documents. This is consistent with traveler TSTF-110-Rev-1 l 3.1-00L l 3.1-11 Not used. N/A N/A N/A N/A 3.1-12 The Required Actions for inoperable DRPI are revised per the current Yes Yes Yes Yes licensing basis to note that the use of movable incore detectors for rod position verification is an indirect assessment at best. The position of some rods can not be ascertained by this method.

3.1-13 In accordarce with traveler TSTF-14. Rev-3r the LCO and Surveillance Yes Yes Yes Yes Requirements are modified to verify that thermal power s St RTP. This provides an LCO requirement to correspond to CONDITION 8 which requires THERMAL POWER to be within limit.

l TR-3.1-0N5 l 3.1 14 Not used. N/A N/A N/A N/A 3.1 15 In accordance with traveler TSTF-12. "c; 1. this change would delete ISTS Yes Yes Yes Yes LCOs 3.1.9 and 3.1.11. This change and TSTF-136 renumbers ISTS 3.1.10 to ITS 3.1.8.

l TR-3.1-l'06 l 3.1-15 This change adds the requirement to perform SR 3.2.1.2 in addition to Yes Yes Yes SR 3.2.1.1with durin

= ~ nf TT9 1 1 4 Required Action B.2.4, y gl 0-3.1-2! l consistent c ig-Icr U00 '05

. the CTS 7

- 2 1 3.1-17 Consistent with current TS LCO 3.1.3.2. ITS 3.1.7 Condition C is clarified Yes Yes Yes Yes to state that the inoperable position indicators are inoperable DRPIs.

3.1-18 A MODE change restriction has been added to ITS 3.1.1, in the LCO Yes Yes Yes Yes Applicability, per the matrix discussed in CN 1-02-LS-1 of the 3.0 package.

3.1-19 Not used. N/A N/A N/A N/A CPSES Conversion Comparison Table - ITS3.1 12/15198

l t

I l

l INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.2 TRAVELER # STATUS DJFFERENCE # _ COMMENTS l TSTF-24 Not Incorporated NA Not NRC approved as of l traveler cut off date.

i TSTF 95 Incorporated 3.2-06 Approved by NRC l

l TSTF 97 Incorporated 3.2 07 Approved by NRC l

I TSTF 98, Rev. S1 Incorporated 3.2 03 TSTF 99 Incorporated 3.2-08 Approved by NRC l TSTF 109 Incorporated 3.2 15 Approved by NRC l

TSTF-110 Rev. 2;) Incorporated 3.2 10 Approved-by;NRC n: .2 0M ,

l TSTF-112, Rev. 1 Net Incorporated NA"3.2!20

~

Not NRC approvcd 0-3 21 i es of travelee cut off date.

Approved;by NRC;3 Applicable /;to CAOC plants;d(CPSES only) l TSTF-136 Incorporated NA Approvedjby.NRC n: .2-0M l

TSTF 164 Incorporated 3.2-11 Applicable to CAOC only. (CPSES)

'400 05, proposed Incorporated 3.2 05 Modified as 0 3,2-6 Rcv. 2 TSTF 241 3.2-169 agreed;upon l Rev;73.

3.2 21 during:12/17/98 l

meeting.between1TSTF

,_ and NRC l (N W96--105 Ir.ccrporated WN n.3. 1 25 i

\ --

5

CFIANGE NUMBER JUSTIFICATION 3.2 15 This change incorporates industry traveler TSTF-109. Action A.2 would require the QPTR be determined rather than performing a l specific surveillance because more than one surveillance can be l used to determine QPTR. SR 3.2.4.1 was revised to retain i allowance that SR 3.2.4.2 may be performed in lieu of SR l 3.2.4.1. The;_ note and: Frequency forJSRi3.2.;4.2(are1 revised 0 3.2 10 to be consistent 1with1 typical;; presentation;formatsithat j provide,fona per.i.od of; time laftertestablishing conditions.

l The note for SR 3.2.4.2 is changed to rcquirc performance if one

v. ,,~,e y, in ...ro m u, m ,,~rs,om.m. These changes are acceptable l

because they clarify the ISTS regarding frequency and use of incore flux monitoring for OPTR measurement. The changes reflect that incore detectors provide an acceptable OPTR determination l during all plant conditions.

3.2 16 This change would require that both transient and static Fa measurements be determined when performed for Required Actions 3.2.4 A.3 and 3.2.4 A.6. The intent of the Required Actions is to verify that Fa(Z) is within its limit. Fa(Z) is approximated by Fj(Z) (which is obtained via SR 3.2.1.1) and Fs(Z) (which is obtained via SR 3.2.1.2). Thus, both Fj(Z) and Fg(Z) must 0 3.1 25 be established to verify Fa(Z). This change is consistent j withQtravelerWOCly /

3.2 17 Not used, applicable to CPSES. Scc conversion comparison 0 3.2 3 tabic (cnclosure SS).

3.2-18 Not applWole to CPSES. See conversion comparison table l (enclosure 6B).

l 3.2 19 Not applicable to CPSES. See conversion comparison table l (enclosure 6B).

t 3.2 20 This change l incorporates TSTFl112 (1l.e.1 deletes'the Note. in 0 3.2 1 l Condition D which required that' required action.D.1'be completed wheneverLCondition D.is entered). ! Deleting the Note permits exiting the. required' action when. power is_ reduced below 50%fRTP. ; Exiting.the required actionLis' appropriate-because i

operation below 50%'RTP:is not constrained with respect to.AFD:

3:2 21 LC0 3.2.111s revised to clarify the Completion Times 0 3.2 6 consistent'with TSTF-241CThe: proposed change will . require Actions?A;1TLA2;and;A;3;to:be repeated after'each subsequent Fa'(z) determination if [a*(z) is'notLWithin limit. LThis will ensure that' Actions.are; continued until the; parameter 11siwithin 'its limit.

f l

CPSES Differencesfrom NUREG-1431 - ITS 3.2 4 12/1S/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.2-6 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.2.4 Quadrant Power Tilt Ratio CTS 3/4.2.4 Quadrant Power Tilt Ratio (All FLOG Plants)

DOC 04-01-A JFD 3.2-05 ITS Required Action A.5 Comment: The ITS proposes to change the STS wording for Required Action A.5 from

" Calibrate excore detectors to show zero QPTR," to " Normalize excore detectors to eliminate tiit," based upon WOG-95 (and rejected TSTF-25). A preferred wording would be that proposed in the Comanche Peak CTS mark-up, " Calibrate excore detectors to show zero Quadrant s Power Tilt." What is status of WOG-957 FLOG Response (original): Traveler WOG-95 was transmitted to the NRC in February 1998 as TSTF-241. The FLOG is incorporating TSTF-241 including the latest revisions discussed at the June 1998 WOG MERITS Mini-Group meeting. These revisions corrected errors made during the development of TSTF-241.

Additionally, Wolf Creek submitted a License Amendment Request to CTS 3/4.2.4, Quadrant Power Tilt Ratio, on February 4,1998 which was approved on April 27,1998 in Amendment No.

116. This amendment incorporated the changes proposed in TSTF-241.

The FLOG believes that it is appropriate to incorporate the proposed TSTF-241 changes based on the NRC approval of the Wolf Creek amendment request.

FLOG Response (supplement): The NRC and the Technical Specification Task Force have agreed upon the acceptable changes to be included in this traveler. Most of these changes were incorporated into the FLOG submittals in the initial RAI response as noted above. The final set of needed modifications have been incorporated as noted in the attached pages.

ATTACHED PAGES:

Attachment 8, CTS 3/4.2 - ITS 3.2, Power Distribution Limits Encl. 5A Traveler Status Sheet and 3.2-1 Encl. 5B B 3.2-5 and B 3.2-Sa Encl. 6A 4 Encl.6B 3

l INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.2 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-24 Not Incorporated NA Not NRC approved as of traveler cut off date.

TSTF 95 Incorporated 3.2-06 Approved by NRC TSTF 97 Incorporated 3.2 07 Approved by NRC TSTF 98, Rev. El Incorporated 3.2-03 TSTF 99 Incorporated 3.2-08 Approved by NRC TSTF-109 Incorporated 3.2 15 Approved by NRC TSTF 110 Rev. 2 3 Incorporated 3.2-10 Approvediby..NRC 3. .2 004 TSTF 112. Rev. 1 Net Incorporated NA?3.2i20 N^t NRC ;PPTOVEd 0 3.21 as of trcycler cut-off date.

Approved'by,NRC.!

Applicable;to;CAOC plantsR(CPSES only)

TSTF 136 Incorporated NA Approved 1by;NRC m: .2-004 TSTF 164 Incorporated 3.2 11 Applicable to CA0C only. (CPSES)

'400 05. proposed Incorporated 3.2-05 / Mod _1fied as 0 3.26 Rev. 2 TSTF-241

.Reyih _

489 [ agreed upon during~12/17/98

( 312f2 meeting'between.,TSTF g.NRC h % 105 Ir.corporated 3-B-46 0 3. 1 25

_- _ _ - ~ _

Fo(Z) (Fa Methodology) 3.2.1 l

l 3.2 POWER DISTRIBUTION LIMITS i

.3.2.1 Heat Flux Hot Channel Factor (Fa(Z)) (Fa Methodology)

LC0 3.2.1 Fo(Z), as approximated by Fj(Z) and Fj(Z), shall be within the ;

limits specified in the COLR. i APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I

'A. Fj(Z) not within limit. A.1 Reduce THERMAL POWER 15 minutes a 1% RTP for each 1% Fj(Z) gerjeach 3.2-21 exceeds limit. 0-3.2-6 Fa'_(Z)

{

determinati A.2 Reduce Power Range Neutron Flux-High trip setpoints 8 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months /s h -3.2-06 '

~

> 1% for each 1% Fj(Z) 4fiIch Fa*(Z) exceeds limit. ( determination

%~

^

@ l A.3 Reduce Overpower erT N 16 trip setpoints 2 1% for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months fter s 3.2-01' each 1% Fj(Z) exceeds limit. %ch.F*(Z) a

{ determination M Y A.4 Perform SR 3.2.1.1. Prior to increasing THERMAL POWER above the limit of Required Action A.1 l

t (continued) l CPSESMark-up of NUREG-1431-ITS3.2 3.2-1 12/1588

l Fo(Z) (Fo Methodology)

B 3.2.1 BASES (continued) l' ACTIONS M I

Reducing THERMAL POWER by 21% RTP for each it by which Fj(Z) l exceeds its limit, maintains an acceptable absolute power

! density. Fj(Z) is Fi(Z) multiplied by e factors 1that account 4eg for manufacturing tolerances and measurement uncertainties.

F#(Z) is the measured value of Fo(Z). The Completion Time of j 15 minutes provides an acceptable time to reduce power in an l l orderly manner and without allowing the plant to remain in an unacceptable condition for an extended period of times _ .. o.3.2 6 fal10wablel power:1.evel2initia]lymaetemined;byJequired ActionIA;11may;belaffectedlby; subsequent 1determi_nationstof f/.(ZE and; wou;direquires powett roductionsiwithinJ15:minutesto.f t thef/(ZXdetermination;iaif.necessarycto comply!withithe decreasedinaximunj allowable: power [ level f 3 Decreases tig F/(Z) wouldfallowjincreasing;thelmaximum allowable ~powerilevelland 1 increasingipowerfup;tosthisyevised;11mit?

M A reduction of the Power Range Neutron Flux-High trip setpoints by 2 1% for each it by which Fj(Z) exceeds its limit is a conservative action for protection against the consequences of i severe transients with unanalyzed power distributions. The ;

Completion Time of 8 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is sufficient considering the small likelihood of a severe transient in this time period and the preceding prompt reduction in THERMAL POWER in accordance with . _ . _

Required Action A.1/ Thelmaximum allowaDie foWer sRange Neutron] - 0 3.2 6 digh: trip 2 setpointslinitiallyidetermined; by;Requi red "

ActionW31may,beiaffacted;bylsubsequentideterminations[of F/(Z) land,woul.d.requireiPower; Range Neutron (Fluxf;EHighitrip setpoi_nt; reductions; withing 2' hours:.of the F/(Z)ideterni. nation l ifinecessaryito* comply lwith;theidecreased maximum 1 allowable Powet Range NeutronfluxBHip% trip 3etpoints5Decreasesdr; F/(Z) would allowlincreasingithe;maximunfal.lowablejPower Range; 2 Neutron FluMHighitrip;setpoints' O

l Reduction in the Overpower eTNi16 trip setpoints by a 1* for each it by which Fj(Z) exceeds its limit, is a conservative action for protection against the consequences of severe transients with L

unanalyzed power distributions. The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months t

I (continued)

CPSESMark-up of NUREG-1431 Bases-ITS3.2 B 3.2-5 12/15/98

Fa(Z) (Fo Methodology)

B 3.2.1 i BASES (continued) l l

is sufficient considering the small likelihood of a severe l transient in this time period, and the preceding prompt reduction in THERMAL POWER in accordance with Required Actinn A.L#ffie. maximum'allowabl,e. Overpower, N 16: trip ,0 3.2 6 setpointslinitially, determined. by Required: ActionJA.~4;may:be affectediby; subsequent;deterninations;of F/(Z.);;andyould require20verpower;Ni16' trip setpoint reductionsiwithin';721 hours0.00834 days 0.2 hours 0.00119 weeks 2.743405e-4 months ofithe F/(Z):determinati_onaif;necessaryLtoicomply.with;the decreased maximusjallowable;0verpower!.N 16: trip:setpointsT2 l

Decreases..in F/(Z);would: allow increasing.the; maximum:0verpower N 16l trip;setpoints!

Ad i Verification that Q(Z) has been restored to within its limit, by performing SR 3.2.1.1 prior to increasing THERMAL POWER above the limit imposed by Required Action A.1, ensures that core conditions during operation at higher power levels are consistent (continued) i CPSESMark-up of NUREG-1431 Bases-ITS3.2 B 3.2-Sa 12/15/98 l

l

1 CHANGE NUMBER JUSTIFICATION 3.2 15 This change incorporates industry traveler TSTF-109. Action A.2 would require the QPTR be determined rather than performirq a specific surveillance because more than one surveillance can be used to determine QPTR. SR 3.2.4.1 was revised to retain allowance that SR 3.2.4.2 may be performed in lieu of SR 3.2.4.1. Thernotef and Frequencyifor SR.L3:2.4;2iar.e3evi_ sed

_ 0 3.2 10 to;be consistent,withLtypical. presentation 1 formats titat Prov1delforfa period,ofitime::after estab1_1shing; conditions; The note for SR 3.2.4.2 is changed to require performance if one "cr morc" OPTR inputs arc inoperable. These changes are acceptable because they clarify the ISTS regarding frequency ani! use of incore flux monitoring for QPTR measurement. The changes reflect that incore detectors provide an acceptable QPTR determination durin.g all plant conditions.

3.2-16 This change would require that both transient and static Fa measurements be determined when performed for Required Actions 3.2.4 A.3 and 3.2.4 A,6. The intent of the Required Actions is to verify that Fa(Z) is within its limit. Fa(Z) is approximated by

Fj(Z) (which is obtained via SR 3.2.1.1) and F#(Z) (which is obtained via SR 3 2.1.2). Thus, both Fj(Z) and F#(Z) must be established to verify Fa(Z). This change is consistent witn traveler WOG 105.

3.2-17 Not used, applicabic to CPSES. Sec conver; ion comparvse" 0 3.2-3 tabic 'enclosurc SS).

3.2 18 Not applicable to CPSES. See conversion comparison tible

. (enclosure 68).

3.2 19 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

4 3.2:20 This;changeiincorporates;TSTF-112;(i.et, , deletes lthe hote in o.3.2 1 Condition D,which. required thqt(required, action D.1 be completed whenevericondition:Diisientered);j.Deletingjthe Note permitsfexiting the. required action when: power is[ reduced below 50% RTPJn Exiting-;the' required; action is appropr,1 ate ~because operation;below 50% RTPfisLnot' constrained with. respect to AFDi r %

(3:2-21 LCOl3.21 is. revised to; clarify.the: Completion Times 0 3.2 6 4

i consistent 1with1TSTF 241,1The proposed change wil1;requi ActionsLA.1, A2 Land-A'.3 to be fepeated after_each subsequent Fa*(z);determinationL1_f Fa*(z)fis.not within: limit.~ This will ensure that Actions are continued until.the-parameter is within its limiti J-CPSES Differencesfrom NUREG-1431 - ITS 3.2 4 12'15/98

CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.2 Page 3 of 3 NUMBER DESCRIPTION Diablo Canyon Comanche Peak Wolf Creek Callaway 3.2-15 This change partially incorporates the industry traveler TSTF-109. Action A.2 now requires the OPTR Yes Yes Yes Yes 3*2 4 l be c'etermined rather thar performing a specific surveillance because more than one surveillance can be used to determine OPTP..! The notc for S" 3.2.4.2 i; chcagcd to .cquirc r..vi ~.~m if cac "cr crc" O'""

input; crc inopcrchic.

3.2-16 Requires both transient and static Fa measurements Yes Yes Yes Yes when performed for Required Actions 3.2.4 A.3 and A.6.

3.2-17 TN tre ; cncy requir = nt fer perfer-ing F, N; Scc CN 3.2-12 No Scc CN 3.2 12 Ves-MA Yes-NA 7.co;u, m..~..t; Sc; tcc . rcview ~m.... m . . ~ m. NA NA l 0-3.2-3 R:

which did r.ct ;pccify c Oc siction Ticc. Not'used 3.2-18 This change modifies the OPTR requirements in NUREG- No No Yes No 1431. Rev.1. for Wolf Creek to retain some the l 0-3.2-6 l current TS requirements and to 'acc.,~.ctc rcvision; tc "cquircd Action; i 4c;;d by trcicicr t.'0C 05.

approved in Amendment'No:~116:

3.2-19 The Wolf Creek specific change modifies SR 3.2.3.1 to No No Yes No resolve a literal compliance issue concern regarding the use of the LCO Note to modify the SR.

3.2-20 This CPSES specific change,(CAOC plants only) No Yes No No incorporates TSTF-112 ;(1.e.T deletes' the Note:1n l 0-3.2-1 l Condition D which required that. required ~ action D;l be f ---Mad hver Condition D11s entered)J

. -21 LCO 3.2.1 is. revised to. clarify tne Sorp;eu on n aes ~ Yes Yes Yes Yes --

consistent'with TSTF341. 0-3.2-6 l CPSES Conversion Comparison Table -IIS3.2 12/15/98

l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR 3.3-007 APPLICABILITY: DC, CP, WC, CA l

REQUEST: Incorporate traveler TSTF-311 as indicated on the attached pages.

ATTACHED PAGES:

Attachment 9, CTS 3/4.3 - ITS 3.3, Instrumentation l Enci 2 3/4 3-12

- Enci 3A 14 Enci 38 10 EnctSA Traveler Status Sheet and 3.3-15 Enci5B B 3.3-58 and B 3.3-59 Enci 6A 14a Enci 6B 22 I

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS TRIP ANALOG ACTUATING MODES-FOR CHANNEL DEVICE WHIC-H CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEIL'aNCE 21-44-A-FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REOUIRED

14. Undervoltage--Reactor N.A. R N.A. Q(10) N.A. 48 Coolant Pumps

15. Underfrequency--Reactor N.A. R N.A. Q(10) N.A. 48 s1-16-L5 Coolant Pumps

16. Turbine Trip

a. Low Fluid N.A. R N.A. la.10) N.A. l' '1-24-LSa Oil Pressure

b. Turbine Stop Valve N.A. R N.A. SAJ# 1a.10) N.A. 4' Closure 11-24 LS ^

17. Safety Injection N.A. N.A. N.A. R.(10) N.A. 1. 2 Input from ESFAS 1-64-A Q 1-23

18. Reactor Trip System Interlocks

a. Intermediate Range N.A. R(4) R N.A. N.A. 26 Neutron Flux P-6

b. Low Power Reactor Trips Block P-7

1) Power Range N.A. R(4) R N.A. N.A. 1, 2 Neutron Flux P-10

2) Turbine First N.A. R R N.A. N.A. 4 Stage Pressure P-13

Prior.to; exceeding the P-9E. inter 1ock_wheneverjthe unit'has been'in' MODE -

-007 CPSES Markup ofCTS 3M.3 3M 3-12 12/158 8

CHANGE NUMBER liSE DISLRIPTION i

and ESFAS sensor response time testing to be performed per WCAP 13632 P A Revision 2. " Elimination of Pressure Sensor Response Time Testing Requirements," or other similar methodologies. This change is consistent with traveler l TSTF-111, which revises the Bases for ITS SR 3.3.1.16 and j SR 3.3.2.10 to allow the elimination of pressure sensor l response time testing.

CPSES has not yet provided a plant specific submittal describing the manner in WCAP 13632 P A or a similar methodology will be applied. Therefore, until a plant-specific submittal is approved by the NRC, CPSES will l continue to response time test all Reactor Trip System and i

ESFio sensors. The proposed changes to the wording in the l Technical Specifications remain applicable, regardless of l the implementation of the sensor response time elimination.

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

! 1 60 A ht u:;cd.The: TAD 0T: Frequency for Functional' Units 16'.aland[16.b[in CPSES; CTS;Tablel4:3IIIisf revised to l M belcons1 stent;with3thei" MODES 1ForiWhich 1 Surveillance}

l It Ra' Qed"Jcolumn; j l 1-61 M This change reflects a revision to CPSES current ACTION j Statement 6. If the requirements of current ACTION Statement 6 are not met, LC0 3.0.3 would be entered which would allow 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to exit the LC0 applicability by entering MODE 2. In accordance with the ISTS this isCTION Statement is revised to state that if the ACTION requirements are not met, the plant must be taken below the P 7 interlock setpoint (the LC0 applicability) within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Thus, this change is more restrictive, by l one hour, than the current TS.

[ Q 1 A GEN A11ireformattingCrenumberinggand; editorial.

1163 A reword 1_nglislin"accordance;with1thelWe:tinghouse Standard: Technical ~ Speci fications';1 NUREGi1431'.Z :.Durj ng; the developmenticertain; Wording'preferencestorEnglish l 1anguagelconventionsiwereladopted; i As:a results: the Technical [ Specifications (TS):should'be'mor,eireadily

readable Rand thereforetunderstandable,1by plant; operators i and;other; users; iDuring;the,reformattingitrenumberingl andirewording process;"no.techni. cal! changes 5(either actual orf, interpretational)]toithe TS;wereLaade: unless.they were identifjed;and[ justified!

CPSES Description of Changes to C153N.3 14 12/15/98 l - - -. - .

CONVERSION COMPARIS0N TABLE - CURRENT TS 3/4.3 Page 10 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY CANYON PEAK 1-55 Applicability Note [a] and ACTION Statements [5 and 9] for Functional Units [1. Yes Yes Yes Yes LS-39 6.a.2).19. and 20] of current TS Table 3.3-1 are modified to provide an alternative to opening the reactor trip breakers (RTBs) while still assuring that the function and intent of ope.ning the RTBs is set.

1-56 The DCPP CTS 3.3.1 Action 2.c requires that power be reduced to less than 75% or Yes No No No A that SR 4.2.4.2 be performed whenever power is 2 50%. This power level requirement should be a 751 since if power is decreased below 75% per the first part of Action 2.c. the required Action is complete and in addition, SR 4.2.4.2 is only required for power levels a 75* with one power range cetector inoperable.

1-57 Current TS Table 3.3-1 Functional Units [12.a and 12.b] are combined per TSTF- Yes Yes Yes Yes LG 169. The relationship between the Functional Units is moved to the Bases.

1-58 The proposed change would allow Reactor Trip System and ESFAS sensor response No - See CN 1- Yes No - See CN No - See CN 1- ,

A time testing to be performed per WCAP-13632-P-A Revision 2. " Elimination of 03-LS-1. 1-03-LS-1. 03-LS-1.

Pressure Sensor Response Time Testing Requirements." or other similar methodologies. This change is consistent with traveler TSTF-111, which revises the Bases for ITS SR 3.3.1.16 and SR 3.3.2.10 to allow the elimination of pressure sensor response time testing.

1-59 Not used. N/A N/A N/A N/A

~

r 1- ,

Not scd.The TADOT; Frequency.forJFunctional Units'16.a:and:16'.b;1n.CPSES: CTS N/ANo N/A Tes N/ANo Table 4.3-1;is revisedLto~be consistent withLtha70 DES ForJhich Surveillance No Is: Required

column,'

TR-3.3-007l 1-61 If the requirements of current CPSES ACTION Statement 6 are not met. LCO 3.0.3 No - See Yes No - See No - See H would be entered. In accordance with the ISTS, this ACTION Statement is revised CN 1-19-LS-8. CN 1-19-LS-8. CN 1-19-LS-8.

to state.that, if the ACTION reqJirements are not met, the plant must be taken below the P-7 interlock setpoint within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1-62 In a Callaway-specific change;; ACTION 7]in CT3; Table;3.3-1 is moved from Functional No N6 No yes A Units 13.a and-13.b to Functional Unit ~13.c CPSES Conversion Comparison Table - CTS 3N.3 12/1588

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 19. Rev. 1 Net Incorporated NA Not NRC approved a; cf l 7g;3 -004 cut off date. Approved i mmasse by;the NRC; Bases changessonly.

TSTF OS, Rev. 2 Incorporated 3-3-34 l o.3%

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.

TSTF 01 Not Incorporated NA [ ] Alicuabic "alues

~

for ics; cf volta;c and l TR 3 3 005 degraded voltage will recain in thc TS.

TSTF 111, Rev. 44 Incorporated NA 0 1. 4 TSTF 135',1Rev;i3 Partially 3.3 41 Travcler is too broad TR-3.^ 006 Incorporated 3;.3144 scopc in natura; 3:3i90] should have bcca 3.3 91? several ;eparate travelers.

3.3 93, Portion; cf the travcicr that 3.3 95, significantly clarify 3:3fl06l cperability requircccats have 3.3 122, beca incorporated.

3.3 142 TSTF 161 Rev.11 Incorporated 3.3-79 Approved by the:NRC o.3, 79 TSTF 168 Incorporated 3.3-43 Approved;byitheiNRC 0 3. 43 TSTF 169 Incorporated 3.3 42 Approved by theiNRC: 7g.3, . !.co3 WOC 10SiTSTFf242 Incorporated 3.3 49 0 3. . 49 TSTE246.1Propc;ed Incorporated 3.3 107 WOC tiini-Croup Action o.3,: 107 travcler Itco #145.

r

( JSTFj311 Incorporated 3,31143 '

TR 3 3 007

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.12 Not;used; 1,1AT. f"

,v m

-3.3 50 -

This Surveillance shall include verification of I!cactor Cociant System resistance tempcrature detector bypass loop ficw rate.

n t,v---. . f*f ......-m t A tikif*l /* A l TDMAT

.m, emmm.,n T m,Ak.t. in m . . - ..A.L...

SR 3.3.1.13 Perform COT. 18 months SR 3.3.1.14 - - -

-- NOTE - ------ - -

Verification of setpoint is not required.

Perform TAD 0T. 18 months :8, SR 3.3.1.15 - - - -

NOTE -- - ---- - -

NOTC Verification of setpoint is not required. [0nly rcquired i

...............................................j when not

{ performed within

\ prcvious 31 days

(

Perform TAD 0T. Prior to 3.3 143 pe ng.- t TR 3.3 007 (P 9 interlock Whenever;the unit'.has;been;in H0DE;3!21f.not performediin previous 31: days

( reactor startup SR 3.3.1.16 - - -

NOTE - -- - - 8 3.3 38 n Neutron and;N-16 detectors are excluded from response time testing.

C B

Verify required ",TS RESPONSE TIMES are 4s 18 months on within limits specified'in the TRM. - ' ~ - '- '

a STAGGERED 3.3 55 TEST BASIS 0-3.3 55 CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-15 12/15/98

. _ - .- ~ _ . .-

RTS Instrumentation B 3.3.1 BASES This test will verify thc rate las compcasation for ficw from the I core to the RTOs.

The frequcacy is justified by thc assumption of an 10 month calibration interval in the detcraination of the magnitude of equipacnt drift in the setpcint analysis.

SR 3.3.1.13 SR 3.3.1.13 is the performance of a C0T of RTS interlocks every 18 months. .

The Frequency is based on the known reliability of the interlocks I and the multichannel redundancy available, and has been shown to l

be acceptable through operating experience. '

1 SR 3.3.1.14 SR 3.3.1.14 is the performance of a TAD 0T of the Manual Reactor Trip. RCP Srccher Position, and the SI Input from ESFAS E and the l Reactor Trip; Bypass;Br.eakerLundervoltageitripl mechanisms. This TADOT is performed every ElB} 18; months.

The Manual" Reactor' Trip]ADOT test shall independently verify the OPERABILITY of the handswitchiundervoltage and i shunt trip contacts 1for_both; mechanisms for the fianuci Reactor Trip function fee the Reactor Trip Breakers and Reactor Trip l Bypass Breakers. The Reactor Trip Bypass Breaker test shall '

include testing of the automatic undervoltage trip mechanism.

The Frequency is based on the known reliability of the Functions and the multichannel redundancy available, and has been shown to be acceptable through operating experience.

The SR is modified by a Note that excludes verification of setpoints from the TAD 0T. The Functions affected have no setpoints associated with them.

SR 3.3.1.15 SR 3.3.1.15 is the performance of a TAD 0T of Turbine Trip TR 3.3 007 Functions. This TADOT is as described in SR 3.3.1.4. except that this test is performod nrinr to fxceeding the.P:9.

erlock.Whenever the unit hastbeen in M00E:3.' ?This reactor

" rt "- A Note states that thisi5urveiiionce is nuc required if it has been performed within the previous 31 days. Verification of the Trip Setpoint does not have to be performed for this CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3-58 12/1S/98 l

)

RTS Instrumentation l B 3.3.1 l BASES 1

Surveillance. Performance of this test will ensure that the '

turbine trip Function is OPERABLE prior toJ xceeding thelP;9 l

.mper!ocka t; Mag =c rcactor critica!. This test connet be ' 1 perfer.;.ed with the reactor at p;n r =d must thereforc bc j

- rfor;;;ed prior to racctor startup- l SR 3.3.1.16 i 1

SR 3.3.1.16 verifies that the required individual channel / train actuation response times are less than or equal to the maximum l values assumed in the accident analysis, Response time testing !

testing); 1'intj=Erequiredichannels?[and acceptance criteria i are included in Technical Requirements Manual. (RefE6)Q Individual component response times are not modeled in the analyses. The analyses model the overall or total elapsed time, from the point at which the parameter exceeds the trip setpoint ,

value at the sensor to the point at which the equip ;nt rcacha i the rcquired functicaci state (i.e., centrol ad shutdown rods i fully inxrted in the reactor core)until;l.oss_of_Jstatio. n. ary _

grippericoilivoltage. 0 1.1 4 '

For channels that include dynamic transfer Functions (e.g.,

lag, lead / lag, rate / lag, etc.), the response time test my bc l testimayjbeneti'intj;; js, performed with the transfer Function time 1 constants;xt to one, with the roulting =nur-d re pense ,

ti e cm. pored to thc appropriate ISA" resp;n a time-- !

Al-ternately, the respenn tin test c;n be perfor;;;ed with the tin contents ct to their no;;;inal values, provided the rcquired l j

respenx tin is analytically calculated assu;;ng the time !

comt;nts are set at their nominal values. The respenx time-mey i bc ;Gsured by a series of overlapping tcsts such that the satire l

__ _ ____..__s ,

_ _huyvi a . _ _ saw

__ _ uI s..b sa ar.w w a u s bu . )

l

"__Cp;;_ti; ny be?.,^,riE;..d by;EtZl Gr; Ziti; tens-4n

_ __,___,__ __ m_m_, _u____,

I l

..., p .av. s . m -~.....,, s ~ ..yv...,?. e -.., y.~.- w ,

measuremente-suelb._ . a_...m_..y________m...~__~...__,,,_1 . t..r . . .

m ., , , W .

Ihcl one;- ond^e tis 1;;t,be 3;.j'i;d p-i r. toipiring,the cr e .e..tiin 3pcrptic .;Dervice.,st re;5eE ' iicd 'clic.;ing______

mu_. __.._2..____2_ _ ,__. . _ _ _ _ _ _ _ m__- ,_

ma.intenen._

_,__ ,__,.____,. ... . ,,.__..m

,- ___ __ y .....

.,____m.________. . ..u,

.r m g ., ,,, m. . . . .

_ m_

W WW W 3 ' WW ! . . ' WfW ! !. 3,'N' ^ MW

,;I 'W W ,, m. _y_ . , _fy_w_Y .swww

. o _ 2 _...b

--- _,_ ___- _, - L u _ ' '_"fWW b d W 8 fw. _-aa.w

. . _ _ 2 m _ _c n._ _

-s.,.__ . . . , , . _

___s.._ ,p f*3, . ep.M .y y , I wyu y 1 ,,,yg .rW { ys N _ www , VI N d u_-._ ,,f __m_a p t U fu -,, T U . W e

_-_-,_m__________ m__ __.,2 ,_ .___,__,__ m_ l W9WMFIW u , s m ,.,w ( ,] W% ~W. . I . ,, f, W y 3 Mb I I ty , .5 N ? ., )

___ _ _ "_ _ _ '_ _u ,t W 8fW' 3..

_,.'*FV .,

j "_N ,, Wu {__-

-...m...,,,,..,y,_....

__.....m.....

1 Respons?'ti.ne may;.be; verified byf actu_allresponse c time; tests;in o.1.1 4 l- any;seriesfoffsequential doverlapping:or; tot _a1l channel l measurementsg oriby;thefsummation offallocatedzsensornsignal processing'andfactuation(logic 1 response!timestwith actual responseitimentestsionsthel remainderfofl the1channelT f Allocations CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3,3-59 12/1S/98 I

CHANGE NUMBER JUSTIFICATION 3;3-141 Not.: appl i cabl e . to. CPSES . ; See ~; Conversi on . Compari son Tabl e a.3,3 002 (Enclosure ~ 68);

3.35142 Adds'for trains" .to ITS '3.3;1 Condition A. . consistent with ITS TR 3.3 006 3.3.2 and traveler 3TSTF 135; N.

3 33143 The: Frequency..of;ITS'.SR^3.3.1.15 is revisedLto_ reflect traveler TR 3.3 007 TSTF 311.JThe: Applicabil.ity_ off these Turbine: Trip; Functions beginsLin MODEWat;the P-9; Interlock!(500RTP);; Thel.STS Frequency C Priorito reactor;startup,":is; inconsistent.:withlthe Applicabil:!ty of:these Functions which can:be tested at; power with minimal perturbationst ofplant; t systems; These;TADOTslar.eL typically performed.prioq to.;1oading the. main turbine,;if not performed within the previons;S1; days.: Both Callawayland Wolf 1 Creek have filed LERs [,)

regarding.this issue. This change _was previously approved'for Vogtle.

N 3.3!144 Not' applicable.to CPSES. . See~ Conversion. Comparison , Table (Enclosure 68). 0-3 3 144 I

i CPSES Differencesfrom NUREG-1431 -ITS 3.3 14a 12/15/98 l

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUPEG-1431 SECTION 3.3 Page 22 cf 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3:33140 Changes to RTS'and ESFAS:DT Functionsfare made.to reflect No

~

No No Yes CallawayJL' Amendment!No.T125 dated:4/1396; CA-3.3-007 l 3.3 141 Change.5,to ESFAS Feedwater:l Isolation Functions are made;to No No No ,

reflect Callaway OL; Amendment ~.No;1125; dated 4/13/984 l CA-3.3-002 l 30i142 Adds for; train" to'ITS' Condition A~3 ' ." consistent with ITS

^

Yes Yes Yes

~

Yes 3;3.2andTSTFjl35) ^

lTR-3.3-00S l

-_ T 3:3~143 ReviseSR3.3;1:15 Frequency.per;travelerTSTF:311'.73 Tes Yes Yes Yes -

TR-3.3-007 I 3.3-144 SR 3.3 7;3:and 3.3.7;4.are, deleted forJDCPP2since therelare No Y_es No No 0-3.3-144 nol actuation)ogic.ormasterJrelaysassociatedwiththe CRVS1pressurizationSystem actuationyia'the CRVS atmosphere intake l radiation. monitors:

CPSES Conversion Comparison Table -ITS3.3 12/15/98

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CP 3.3-011 APPLICABILITY: CP i REQUEST: The CTS and the ISTS address the undervoltage and degraded voltage channels for the Loss of Power (LOP) Diesel Generator (DG) start instrumentation but do not address any Automatic Actuation Logic and Actuation Relays. The CPSES design included Automatic Actuation Logic and Actuation Relays as part of the LOP DG start instrumentation. ITS 3.3.5 has been revised to incorporate this function and the CTS has been marked up to be consistent with the ITS.

ATTACHED PAGES:

Attachment 9, CTS 3/4.3 - ITS 3.3, Instrumentation Encl. 2 3/4 3-24,3/4 3-30,3/4 3-36 and 3/4 3-44 Encl. 3A 19a Encl. 3B 16 Encl. 5A 3.3-53,3.3-55,3.3-56 and 3.3-56a Encl. 5B B 3.3-153a, B 3.3-155, B 3.3-157, B 3.3-158a, B 3.3-159 and B 3.3-159a Encl.6A 12 Encl.6B 18 l

l 1

I 1

TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRLNENTATION REQUIRED MIMMUM TOTAL !!0. C:??!!?ELS C".*?!!!ELS APPLICABLE "1-43-A*4 FUNCTIONAL UNIT OF CHANNELS TO TilI" 0"E"^ ELE N0 DES ACTION 1-04-LG N-

8. Loss of Power (6.9 kV & 480 V Safeguards System Undervoltage)

a. 6.9 kV Preferred Offsite Source Undervoltage 2/ bus 2/ bus 1/ bus l', 2'. 3', 4' 23a, 23b 11-A ^ <

b. 6.9 kV Alternate Offsite Source Undervoltage 2/ bus 2/ bus 1/ bus 1, 2, 3, 4 23a, 23c

c. 6.9 kV Bus Undervoltage 2/ bus 2/ bus 1/ bus 1, 2, 3, 4 23a, 23d

d. 6.9 kV Degraded Voltage 2/ bus 2/ bus 1/ bus 1,2,3,4 23a 23e

e. 480 V Degraded Voltage 2/ bus 2/ bus 1/ bus 1, 2, 3, 4 23a, 23e

f. 480 V Low Grid Undervoltage 2/ bus e/ bus 1/ bus 1, 2, 3, 4 33a, 23e utomatic Actuation Logic z 2. trains ,1, ; z ,

~~ '

.5, . 4 '"' 23D -

E nd: Actuation Relays CP-3.3-011 l2-59-H

9. Control Room Emergency Recirculation

a. Manual Initiation 2 1 2 AM 24 1;2,3,4,5,6 and /2-12-MM during: movement;of]

1rradiated_ fuel assemblies inew; AutomaticTActuation,.L_ogiciand 72 trains;ff; "l 7 ~ C 7_' , T ""; f1;2.3,4,5;6:and; 7 24 .2 47-M 4 ActuationLRe1ays during movement 1of irradiated.. fuel assemblies

b. Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

CPSES Markup ofCTS 3N.3 3/4 3-24 12/15/98

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

l l

l TABLE 3.3-2 (Continued)

ACTION STATEMENTS (Continued)

ACTION'23: ff With the number lof;0PERABLE motor; driven AFW:puso U(Continued) channels ~one;less; thanl the Required; Numberil place -the i . inoperable.channeltin: trip orarestore the: inoperable *2'10'M' e

channelf withinj6; hours orLbe;in MODE 131withinLthe next'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) l .ction;23; ; g.? Withthenumberof0PERABLE' s trains;lessthanAhe l Required Channels,Lrestore the11noperableLtrain(s)Lto 2 59 M OPERABLE within~1" hour..or; enter l actions;for'the CP 3.3 011 diesel generator;made;inoperablesby the Lossfof: Powe -

_ dieselj generatorJstart ,i nstrumentation.' j ACTION 24 - With the number of OPERABLE channels one less than the c 1 43 A <

Minimum Required; Channels OPEPX LE requir;;;nt, restore the inoperable channel to OPERABLE status within 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 7(days i2 16 LSS.4 or initiate and maintain operation of the affected! train!of the; Control Room Emergency Recirculation System.

With the' number;ofj0PERABLE channels twollessithan Required Channel s ,?.immedi ately. pl ace . one . trai n l ofc the Control Room Emergency Recirculation. System in operation'and enter the required actionsyforf one train lof Control; Room' Emergency Recirculation System made:jnoperabl.e?bylthe actuation ?2 26 LS -

instrumentation.: i Otherwise,31ffin MCDES '1~,2,3:orL4,'be?in MODE!3 within the next 6; hours;and; MODE 5'within;the;next 30ihoursCIf in1 MODES 12-26 LS 5F 6. oreduring movement oftirradiated; fuel, immediately suspend;; core; alterations.and suspend l movement;offirradiated fue]; assemblies?

ACTION 25 - With the number of OPERABLE Channels on one or more trains 1 43 A= '

less than the Minimum Required Channels OPEP# LE requirc ent, declare the diesel generator (s) associated with the affected : 2 13 A': e train (s) inoperable and apply the appropriate ACTION for Specification 3.8.1.1.

ACTION 26 - With the number of OPERABLE channels one less than the Mmmum Required: Channels OPEPELE requirement, restore the inoperable s i.43 A -

channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (12; hours;for Safety InjectionjSequencefUNCTIONALUNIT):or be in at least HOT :2 24 LS STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s: however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

I CPSES Markup of CTS 3N.3 3/4 3-30 12/15/98

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP ALLOWABLE #2 01-A1 M FUNCTIONAL UNIT SETPOINT VALUE $2 W 9 ;

7. Automatic Initiation of ECCS Switchover to Containment Sump (Continued)

b. RWST Level--Low-Low

a. Unit 1 E 40.0% 2 38.9%

of spar. of span

b. Unit 2 E 40.0! 2 39.1% ,

of span of span Coincident With See Item 1. above for all Safety Injection Trip Setpoints and Allowable Safety Injection Values.

8. Loss of Power (6.9kV & 480V Safeguards System Undervoltage) 24-0,

a. 6.9kV Preferred Offsite Source E5004 V $5900 V .

Undervoltage 24900 V

b. 6.9kV Alternate Offsite Source 15004 V 55900 V Undervoltage 24900 V

c. 6.9kV Bus Undervoltage 12037 V 21935 V l 53450 V

d. 6.9kV Degraded Voltage E5054 V 25933 V

e. 480V Degraded Voltage t439-V 2435 V

f. 480V Low Grid Undervoltage _6 2443 V

Automatic" Actuation. Logic [NA I

'~~'and;ActuationfRe1ays 2-59-H j CP-3.3 011 .

i CPSES Markup ofCTS 3M.3 3M 3-36 12/1SM8

1 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ANALOG ACTUATING MODES g 3 44.g ,4 CHANNEL DEVICE MASTER SLAVE FOR '.IClj CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY " ' " " " " ' " " "

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS RE0UIRED

8. Loss of Power (6.9kV & 480V Safeguards System Undervoltage) 42-11-A.

a. 6.9kV Preferred Offsite Source N.A. R* N.A. (3. 2) N.A. N.A. N.A. 1. 2, 3. 4 Undervoltage

b. 6.9kV Alternate Offsite Source N.A. R* N.A. (3. 2) N.A. N.A. N.A. 1. 2. 3. 4 Undervoltage

c. 6.9kV Bus Undervoltage N.A. R* N.A. (3. 2) N.A. N.A. N.A. 1. 2. 3. 4

d. 6.9kV Degraded N.A. R* N.A. (3. 2) N.A. N.A. N.A. 1. 2. 3. 4

! Voltage

e. 480V Degraded N.A. R* N.A. (3. 2) N.A. N.A. N.A. 1, 2. 3. 4 Voltage

f. 480V Low Grid N.A. R* N.A. (3. 2) N.A. N.A. N.A. 1. 2. 3. 4 Undervoltage Automatic Actuation N.ATT f ; N.A"~~;T11N.AE2 : 3N.AyCZi(2)2?""IN;A'y N.~A? .

Logic and Actuation - - - - .

2-59-M Relays CP-3.3-011 l

This survcillonce test interval is extended to (but not to excccd) 24 ;;;caths for Train A. Unit 2. to .

rc;;;cin in effect until the co;;;pletion of the seccad refueling cut;gc for Unit 2. 01'31'^ #

i CPSESMarkup ofCTS3M.3 3M 3-44 12/15/98

CHANGE NUMBER ffSjiG DESCRIPTIQ!i 2151 Not; applicable _to;.CPSES;OSee':Conver.sion Comparison: Tab 1_e

.(Enclosure 138)J 2152 A Note 3e);to1 current;TSlTable'3;3f2;! app 11editoithe 0 3.3 65 TurbineTripland:Feethrater; Isolation : FunctionaE Units Sib f:isf reflected ;j n;ITS;TableJ3 ;3(2 fiU Functional tunit 5;bMfootnotel;(p)EThisifootnotelonly1 requires the affectedl channe1Lto; be_decl ared21noperableMThe; condition for:an tinoperableichannel:li s ,then;erterednThe:resulting actions;are,~ equivalentito; CTS 7 Table;3:332,1 note l.(e)MEven though;;the2footnotesjarejrepresentedlin:a'different manner!

theiCTSlandlITSirequirements!. are; functionally;equivalen.ti thereforenthis: change 1si: considered;be;4njadeinistrative change 1 2iS3 M NotZaMcable.(to1CPSESUSee;Conversi.on ComparisoniTab]e (Enclosurel3B)]-

2f54 M Notiapp1_icableito;CPSESE;See: Conversion.Compar,ison; Table

,( Enclosure!38.)I E!55 M Notejc)Lto: current}TS; Table 3;3t22forgthe; Steam:Line 04 N Isolation functional Unitsj4:a;2 3 b,q4;c M d;i:andl4;e isireyiseditoistateithatitheiLC0fequirementslareinot applicable 11n!M00ESJ2:end 3 whenithe MSIVsf are;. closed;and deactivated M his;changejisimorelrestrictive;31n.thatithe additionaltrequirement;to;deactiyate;the; closed valves:js imposedMThisichange11s[ consistent;with .NUREG:1431% Rev; I?

2156 LSf48 Not ;;applicableito1CPSESESee. Conversion , Comparison Jable (Enclosure 3B)?

215Z A Not; applicable!to;CPSESUSee_ Conversion Comparison? Table (Enclosuret38);

2158 A NotiapplicableitoiCPSES 7See , Conversion ;Compari son (Table (Enclosure 38);

2!59 M TheTLoss;of' Power;ESFAS~ Functional' Unit:is= modified I CP 3.3 011 withitheladdition?ofAutomatic: Actuation [ Logic;and 1 Actuation; Relays Functi.ont:A;new; action;is7added for this; function;and;a: surveillance;requirementiis;also;added.

S_inceinone;of;these1 requirements;existiin the CTSCthe additions are:more; restrictive;% The: addit _1ons;are;made;in almannericons.1stentjw.ith;otheriESFAS Functiona11 Uni _tsnthat have:simi.1_arlfunctionsland consistent;with other; functions inithisiFunctiona]Tunitl CPSES Description of Changes to CTS 3N.3 19a 12/15/98

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.3 Page 16 cf 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO COMANCHE WOLF CREEK CALLAWAY CANYON PEAK 2-53 In'this Callaway-specific change.:the tie'breakerfclosurel discussion in ACTION;19 No NO No Yes LG of CT3 Table 3.3 3_is~ moved to the Bases ~ for.ITS 3.5.5 Condition B as one' example of multiple channels: inoperable on one bus."

2 54 Deletion of ACTION.b.1l eliminates one possible. recourse _for an Allowable Value not No 9fNot in CTS No l Notiin yes Yes N net? CTS 2-55 Note-(c) to current ~TS Table 3.3-2.for the Steam Line~ Isolation Functional: Units No Yes No No N 4.a.2, 4.bs:4.c.14.d.: and,4.e 1s. revised to state that:the LCO requirements are l0-2-0; not" applicable;in1 NODES:2;and'3.when the MSIVs'are closed and 'deactivatedi l'-

2-56 DCPP CTS X, TION. Statement 35 is; revised to require MODE:2~ entry and,to delete the Yes No No No LS?48 requirement'to enter; LCO 3.0.3 which; requires;the.,unitito.be placed;1n.M00E 3.as a minim m!

2-57 Current;TSTTable 13 ;3-3 J Functional 1 Unit :::3.c.2)P Containment T. Purge l Isolation No'-TNot;in CTS No i Not2in Yes Yes A Automatic Actuation'Logiciand Actuation Relays',(SSPS) and Functional' Unit!9.b; CTS Control. Room' Isolation:-; Automatic Actuation Logic ~and Actuation Relays"(SSPS);1and associated surveillance requirements'are deleted; 2-58 .NCGS' Amendment' Mot:117 dated'Mayf28,;1998,7added'a'new' Action Statement.to CTS No No Yes No A 3/4.3.2.' Table 13.3-3,; Functional Unit;7.b.i Refueling Water Storage Tank: Level (RWST) 1 Low-Low Coincident:with Safety Injection; The Automatic Actuation Logic.and' Actuation Relays function is.added the ESFAS No Yes No N N Loss of Power Functional: Unit for CPSES: ll CP-3.3-01L l m -

3-01 The requirements of this specification [ CTS 3.3.3.1] are moved to [three] Yes Yes Yes Yes A separate specifications in the improved TS. The RCS Leakage Detection requirements are moved to improved TS 3.4.15. [ ] The Control Room requirements are moved to improved TS 3.3.7. [The Containment Ventilation requirements are moved to improved TS 3.3.6.]

3-02 The requirements stipulated in ACTION [a] are moved to ITS Tables [3.3.6-1 and Yes Yes Yes Yes M 3.3.7-1]. with explicit direction contained in the ITS ACTIONS Bases. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A0T for setpoint adjustment is eliminated.

CPSES Conversion Comparison Table - CTS 3N.3 12/15A98

i i

I LOP DG Start Instrumentation 3.3.5 l -

3.3 INSTRUMENTATION

! 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation

s-3-1M n, , ,,,

, . . _ _ _t u .. ...

LC0 3.3.5 .._ u. u__r . -, . .u..__

t.._ _t it_ ._u._

Three .. __ _ u.u_ .. _._.

. ._ ,. ._ rs, ___ vue v. .m .... v, .v CP 3.3 011 c..__ J _ ._; - _ L . _ _ a .. ___ t.._ _t it. ;-__.2_; .._u__

q ui sw w a vli u s su . Vi aus si ss 5 d yLa uug vu wars u% 31 uusu vvibuyw _- ..

. unction T.h. et Los. s :o.f. .P. ower Diesel _'Gener.ator$.St. ar..ttIns.t.rument. aio. n..!for. 3.3 115 l each, Function;in; Table;3:3{5f15shall be OPERABLE 2 CP 3.3 011 APPLICABILITY: MODES 1. 2. 3. and 4, J.. J fV4 .- L_ L.,

_ . . J..J 1 1L, m_. u ,vw.useu vu J, ,

. i #*n S n w A /*

.myu _ m_ uev vs nn.FMAntP

.-v., mv u . v . .a. ~ L 3.3 129 c_..____ e t . . ; _. ._ =

, svun us e si nu 6uvwi s .

l =:an w.. . .:

.=. : n . ==::.

wa.. < .n.. .-m.s.-

m :::.N0TE. . ..'s;;. a w.. .m

=;r== =r =r-~...x.,~...

w ..~n ~

= =;;r= - - ::.n;

...a.i.-,

1 Notiapplicabl.e;for16.9ckVfPreferred 0ffsite' Source._Undervoltage; function.when . 3.3 130 associated source br.eaker1.;1_sfopen.? o.3.3 130

.; .;=.;=, = ;=, ; =;=.u. _- ;%.u 3.a % . 2.#. ,. .

m u; um ;. == w =, =ua,,;=;; =;;=m= a;;x. a.;=;=;.;

m- . ' % s# =mw s.---.* - - - .m. w,.

ACTIONS

........................................ NOTES --- --- - --- - - ---- .-- --.-

M Separate Condition entry is allowed for each Function.

.._m.___ 2__u_.,__.c n.. ___ , _2___ 3.3 130

.n

.e- v.%w __,___m _.n,,_2... m _ c _. ._ .a _ __.w. p... . _u..-c 7,. . -yr . -- , % . -.

. .. .. . ..__ m..

Q 3.3 130 t __--s_x2 _ _ . . . - _ _ s___n._-2____.-

[ .s e.e.wi. ,. 4. .W M _ _ eFv4.., ,bb , M..i.tu.s4.. , , ,8 eF , vfb. 3 .

t l

I CONDITION REQUIRED ACTION COMPLETION TIME T4 m.c.--NOTEE 5!9 A A.1 "0T" 3.3 85L i . trapplicableito l The inoperabic chanaci ;r,ay l AutomaticTActuation bc bypassed for up to

! Logiciand!. Actuation 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for survcillar,cc l RelaysiFunction testin of other channeh- 3.3 115

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

CP 3.3 011

, a A. One or more Functions Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one channel per bus inoperable.

1 i

CPSES Markup ofNUREG-1431 - ITS 3.3 3.3 53 12/1S/98 i

t

l LOP DG Start Instrumentation 3.3.5 l

l E; Two: channels;peribus;for E.1 Re. store.cne: channel)per bus 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 3.3 131 l onelorimorejdegraded to.OPERABLEjstatus

! yoltagelor; low,gr.1.d

undervoltage: function QB l inoperable E.2.1 D~1areibothl. offs 1te I q C t;'y pui,er sources buses Ichour 3,3,131 i

inoperable 0 3.3 131 l

l alfQ E.~2.2 Open offsite.: power 6; hours j source 1 breakers;to;the a_ssociated; buses

! . One,or.xmore Automatic F.1 Restore train (s)'to OPERABLE

~ '

1~ hour 7

ActuationLLogicl.and status { Q 3.3-115 CP 3.3 011 i

betuati_on; Logic: Relays trainsLinoperable;

/

. Required Action and EFG.1 Enter applicable Immediately 3.3 1310 associated Condition (s) and Completion Time not Required Action (s) for met. the associated DG made inoperable by LOP DG start instrumentation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 "er'- : ""^J :L CliECX,hbed. . "erf -12 hour I

l CTUATION 'LOGICITEST: '

fo_ entering MODE 14;when'in

$115 !

H0DE 5,fo & 72 -

CP 3.3 011

hours and if l

not per. formed in previous ~'.92 days CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-55 12/15/98 l

n - . ,.4 a & - - , , -

w -> .% a LOP DG Start Instrumentation 3.3.5 SR 3.3.5.3 Perform CHANNEL CALIBRAT10tLKith s-tpoint 38 months i,s_.__.. . , _ , . . . .___ __m_ J_A .,,.L,_ u_,...

I vvvuu i w wuIuw TV s by y ,ww bp g .5 i b , n 5 tvvvuwsw v_uiuw _

.. c 11 m .. '

ua a v s a viv a .

. n_s----J .ts.Js. . . . . . L...

u. s s s vi i ww ; v i i e s bw avuswwa wwa J__..16._- _c..1A-mm un iuw s u v a buys buJa i ... v3 vvIbuys niIvvvuW4w A11m ..L1 u m 1. . . ?-enan-u -J _ annn u nnin u .4SL .

YuIuw .a er.r y v ; y ut vu , ar , ,'v e rvv ,y hsAL y vv i b s i L AJ_. ms rn 61 , r 9 bims uwsuy Joi ., vi Lv.v; A L J aw wvi ru . ...--J W}

M-132

.. . . . , . . ,_J e.. J . _ nn,e u muaa _

v s. Tv. buys .. i r sw w s ii b c ms v 0 3.3 133

.vv. J. b.. L, J,.

_w_ us . u,. .

_, en Lv.v; n,

. Lr ,; awwvuu.__ m_J 3.3 115

- tb J.m u v.

p CP 3.3 011 L - - a 1 A - A. - . rs. J am - _m.--- L... . J--.1A-__

p.

, n g bvi ,v uu bb , v s u_ a I, bs _, avut,ww Uwe us vuws ,vv i buys

_a 1 1_. .. L t . u _1. .. m ennn u a e annn u<

n s a v_wwna I_w wuaww _g , ,w.r y w, v , ,uu vgs g_ r.ryv _

v.

mk 1 e n L., r'1 . . . 1 t= L... .._J _.m1& __

ww.4 v.s ps y usuaJ A6 uua un suw; uvabuyw

. . L1. u 1. . . m inSE u .J SAEM u A11m i s urvu u s s vutus L Asus y u n s

iu ; v rav v J&L sJ_. J1... mt rn 67 i r 9 Wi kis u. bimw uwsuJ vs Lv.vJ A L J .,m as m_

w viiu L.

JL 6 e n L., r* 1 . . . 1r L.. Am .J J ..-1 ww . s. ves ss y wiuaa 46 uua uwysuusu vvT A11m ..kl. u 1. . . m EMSS u .4&L - &J_.

nievvvuusu auiuw ; usos y vs bis u bims A m1. . . mt rn 69 i r 1 ..___J ussuy vs Lv.v; A L g as wvi su .

I _m 1 Ann if f* 1 . . . 1r ki.. 1m . -JJ ..J-.16._m ww.4, rv v v vuuaa 46 uua u vvy yi su uu suw s vvibuyw A11m ..L1. L t .1. . . m AAS u ..J&L . AJ_m J ,.1 .

niaveruuIw wusuw g T7w a vs i b e i u bimw uw i r i at rn el i r 9 .-mmmJ vi Lv.vJ A g g aw vvi ru .

s. n Jon u t'1.._ 1r J._-.J J .. 14 All m

.. uw

m. m sw.k Tuv v v l uaa , 46 ;ubyl uuvu vvibuyv mi vnu u 1. . . Ase u . .J s L . &J_. J m1. . . mg yuauw c 7sv v vt I b l i u bimw uwIuJ Ve rn 69 r 1 J

.v; .i L 2 as , . w m.s ,u .

SR'3.3.5;4 Verify.7; qui c? LOP.DG: star.t;4nsteumenteM en 18 months 1on a ESFl. RESPONSE.tTIMESfare;within lim.its specified STAGrARED TEST in the;TRMl BASIS 3331 Q 3.3-55 1

CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-56 12/15/98

LOP DG Start Instrumentation 3.3.5 i

En 'f"2 1 . .f fiC.fi...l." Table;3:3:5f11(page;1 of.~1) 1 E E JC T' ; Loss cf PowerJ(LOP)! Diesel GeneratorL(DG):StartEInstrumentation 3.3 115 CP 3.3 011 l

\

REQUIRED SURVEILLANCE ALLOWABLE l FUNCTION CHANNELS REQUIREMENTS VALUE

)

l i

[1; Automati( Actuation Logic 2 trains 3;3.5',1 NA l and Actuation Relays 12i Preferred .offsite: source 2;.per.; bus 3;3.5;2 5.59003 i bus,undervoltage 3;3.5.3 and.! l 2;4900;V

!i3; Alternateioffsite;. source 2.'peribus 3:3.5 2 159001V bus;undervo]tage 3.3.5.3 and 214900.V (4.l 6.9 kv; Class 11E; bus 2l.per bus 3;3.5.2 2:1935 V undervoltage 3:3'.5.;3 and 5 3450;V

[5; 6.9'kv Class;;1E; bus 2 pernbus 3;3,5;2 E5933:V

degradedlyoltage 3.3;5j3 16l 480XC1 ass?1E; bus; 2.per xbus 3.3;5.2 2: 4431V 1.owl grid;undervoltagell 3.3.5;3 E7f 480LV:. Class"IE busi 2 per, bus 3;3.5'.2 2;.435;V .

degraded;voltagei 3;3.5.3 J 1 .h 44 x < :tf, <. % J CPSESMarkup ofNUREG-1431 - ITS 3.3 3.8-S6a 12/1S/98

LOP DG Start Instrumentation B 3.3.5 BASES i redundant;degradedjvoltage;relayston.each of;the(two 0 3.3 131 6.92kV; Class 11Elbuses,;and f redundant; degraded yoltage;rel.ays:on'eachlof;the two 480VlClass:1E buses?

Thrcc andcrvoltage relays with inverse tiac characteristics are provided on cach 4150 Class 1E instru cat bus for detecting a sustained degraded voltag; condition or a icas of bus voltagc.

The rclays arc combincd in a two-cut-of thrc; logic to scncrate An LO" signal if the voltage is below 75% for a short tir-cr below 00% for a long tiac. The LOP start actuatio ogic is described in FSAR. Section 8.3 (Ref. 1) nLgeneral; CP 3.3 011 sensing trelaysf;for;each train.Teea X wor.kEofRogic;and actuatjonirelaysJforltheir, respective trains M The; network ofalogiciandl actuation Erelays l actuate l theToffsite_ powet source reakers' and : generatorf start [ signal sias 'descr_ibed _in. .:.th.e. FSARJ Trio Setooints and Allowable Values The Trip Setpoints and;associatedjtimeidelays used in the relays are based on consistent with;the analytical limits presented in FSAR, Chapter 15 (Ref. 2). The selection of these Trip Setpoints is such that adequate protection is provided when all sensor and processing time delays are taken into account.

The actual nominal Trip Setpoint entered into the relays is normally still more conservative than that required by the 4

I (continued)

CPSES Markup ofNUREG-1431 Bases - ITS 3.3 B 3.3-153a 12/1S/98

LOP DG Start Instrumentation B 3.3.5 BASES account for each individual component of loss of power detection and subsequent actions.

The required channels of LOP DG start instrumentation, in conjunction with the ESF systems powered from the DGs, provide unit protection in the event of any of the analyzed accidents discussed in Reference 2, in which a loss of offsite power is assumed.

The delay times assumed in the safety analysis for the ESF equipment include the 10 second DG start delay, and the appropriate sequencing delay, if applicable. The response times for ESFAS actuated equipment in LC0 3.3.2, "Enginccred Safety Icature Actuatica Syste: (ESIAS' Instrumcatation," include the appropriate DG loading and sequers ng delay. The LOP DG start instrumentation channels satisfy Criterion 3 of the NPs0 Policy Statemcat.

10CFR50.36(c)(2)(ii).

LC0 The LC0 for LOP DG start instrumentation requires that Ethree two} channels per bus of both the undervoltage icss of 0-3.3 131 voltage and degraded voltage Functions shall be OPERABLE in H0 DES 1, 2, 3, and 4 when the LOP DG start instrumentation suonnete caety tyrt^~ =cenMated with the FRrA wo , .CP-3.3 011 trains-of: Automatic Actuation Logic and Actuation Relays shall also be OPERABLE in MODES 1, 2, 3 and 4f In MODES 5 and 6.-the [thrce] channc;s mus; cc UiL E LL WhenCVCr the CP 3.3.ED essociated DC is required to be OPEPX LE to casure that the automatic start of the DC is availabic when nccded. there is sufficient time available such that a' manual start'of the Bgs DGYis acceptable.- Loss of the LOP DG Start Instrumentation Function could result in the delay of safety systems initiation I when required. This could lead to unacceptable consequences during accidents. During the loss of offsite power the DG powers the motor driven auxiliary feedwater pumps. Failure of these pumps to start would leave only one turbine driven pump, as well as an increased potential for a loss of decay heat removal through the secondary system.

APPLICABILITY The LOP DG Start Instrumentation Functions are required in MODES 1, 2, 3, and 4 because ESF Functions are designed to provide protection in these MODES. Actuation in tiODE 5 or 6 is required whencycr the required DC must bc OPEPELE so that-+t-ean-(continued)

CPSESMarkup ofNUREG-1431 Bases -ITS3.3 B 3.3155 INIS/98

LOP DG Start Instrumentation B 3.3.5 BASES A Not; is added to allow bypassing an inopcrabic chanaci for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for survcillance testing of other chanacls. This allowanc; is made whcrc bypassing the channel docs not cause an actuation and wherc at least two cac cther channcis arc is monitoring that parametre-l The specified Completion Time and time alicwed for bypassing one channci arc?is reasonable considering the Function remains fully OPERABLE on every bus and the low probability of an event occurring during these intervals.

A;notehas;beeniaddedito; clarify;that1this;ConditionlislnD applicable to.the: Automatic Actuation Logicf and Actuation cP 3.3 011 Relay function. This::functioniisiaddressed;by. Condition FI B.1 B;2.1 Pand B:2.2 I

Condition B applies when acrc than cas both loss of voltage-ee more than onc degraded voltage channels on a singic bus!the Preferred.0ffsite Voltage Source' bus are is inoperable.

1 Required Action B.1 requires restoring all but one channel to OPERABLE status. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time should allow ample time to repair most failures and takes into account the low probability of an event requiring an LOP start occurring during this interval.

Alternatively,: Required. Actions' B.2.1Tand.B'.2.2;can be. completed.

Action ~B.2.1 reyuires the: Pref _ erred'0ffsite Voltage, Source bus to immediately be' declared! inoperable. i Action B.2.'2 requires that the Preferred Offsite Voltage.. Source. breaker be opened within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .J:In this circumstance,,the appropriate. Condition.specified in LC0f 3.8.1;7"AC;Sourcesf Operating.1 should be; entered.

C:1. C.2:1:~and C.2:2 Condition:Cl applies;when both less ofyol_tage channels' on the 0 3.3 131 Alternate;0ffsi.te; Voltage Source bus are; inoperable Required l Action:C.1' requires l restoring one channel 1to.0PERABLE status.' lThe 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months Completion Time'should allow ample time to repair'most; failures _.and takesLinto account the.. low probability ofjan. event ~ requiring an: LOP. start occurring during this interval!

(continued)

CPSETMarkup ofNUREG-1431 Bases -ITS 3.3 8 3.3-157 12/1588

l LOP DG Start Instrumentation ;

B 3.3.5 BASES l

fil I Condition F: applies!.whe.n;onejor;;more: trains;;of. Automatic Actuation' Logic;;.and; Actuation' Relay 5 function.are11noperable?

l Required' Action F.;1:requirestrestoring..the[inoperablettrain(s);t)

OPERABLE] status D The(1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; completion, Time; allows,timejto L

repair;. failures!;and. takes 11nto' account (theilow probability ofianievent requiring;. LOP;DG.l start occurring:during th.is CP-3.3-011 l interval.; ,

I i

l i

(continued)

CPSESMarkup ofNUREG-1431 Bases -ITS 3.3 3.8-158a 12/1588

l LOP OG Start Instrumentation B 3.3.5 BASES CFGs1 d

Condition 6fG applies to each of the LOP DG start Functions when the Required Action and assoc ted Completion Time for Condition A c- S sTA'throu are not met.

,. - v In these circumstances the Conditions specified in LC0 3.8.1, "AC Sources -Operating,is vs. bovIen 9 v.v.m. n 9 is A P P-,.

no vuu. wme PL...AJ-. ,N for vsubuvm.

the DG made inoperable by failure of the LOP DG start instrumentation are required to be entered immediately The .

actions of those LCOs provide for adequate compensatory actions l

to assure unit safety. l 4

4 J

2 SURVEILLANCE SR 3.3.5.1 ,Gxd CP-3.3 011 (.

REQUIREMENTS I n E--_ --- mt &L* Pt 1 A11&lPI Pi f f*PU ---. .,.mm.. 19 L-...

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w s .u imu. ..- - 1, (continued)

CPSES Markup ofNUREG-1431 Bases -ITS 3.3 3.8-159 12/15/98

. m . m _ _. - _

l LOP DG Start Instrumentation B 3.3.5 BASES J3.3;5:111s the o performance;of'an;: Actuation Logic 1 Test yn CP 3.3 011 the' Automatic; Actuation;Logiciand . Actuation Relay;functiord The; test 'is^ performed, priorito' entering M00E;4.;to; avoid

$nadvertentfloss'.'of; Class '1Eibusses in'MODESilh2;;;3 andL4f;ET l frequency;isiadequate basedion; the~ known reliability;of:such }

relay logic networksi.as: verified by; operating experience.A i

(continued)

CPSES Markup ofNUREG-1431 Bases - 1TS 3.3 3.8-159a j2/jSgg l

l CHANGE NUMBER JUSTIFICATION 3.3 107 Based upon operating experience to change Thermal Power in a controlled fashion without challenging the plant and consistent with the current TS which does not have a Completion Time for restoring one channel to l Operable status; but does prevent going above P-10 until it is 0 3.3-107 l

restored. the Completion Time for ITS 3.3.1 Required Actions F.1 and F.2 should be increased to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Condition F of ITS 3.3.1 is for one Intermediate Range Neutron Flux channel inoperable. Reactor )

protection would be provided by the Operable Intermediate Range Neutron '

Flux channel and Operable Power Range neutron Flux channels. Indication would be available from the Operable Intermediate Range Neutron Flux channel [from Operable NIS detectors] and from Operable Power Range !

Neutron Flux channels with power approaching P 10. The 'Jcstinghouse Owncrs Croup is considcring a scncric changc on this issuc. but delibcrations werc not completed at the ti:::c of our submittel- See TSTFi 246.

l 3.3-108 Not used.

3.3-109 Not used.

3.3 110 Not used. l 3.3-111 This change adds a note to ITS SR 3.3.1.7 for source range instrumentation to verify interlocks P-6 and P-10 are in their required state for existing unit conditions. This is consistent with the current TS and is an enhancement which is easily performed and provides additional assurance that the interlocks are functioning correctly.

3.3 112 Not used.

3.3-113 Not used.

3.3-114 Not used.

3.3 115 "M. The . speci fi cati on ; for, Los s t of Power; (LOP) : Diesel GeneratorJ(DG) Start-Instrumentationiis modified by the additio CP 3.3 011 of ~ the functionEAutomatic; Actuation . Logic' and -Actuation Relays.'

This function;is;not inlthe STS but11siincluded in' the CPSES' design.a d shouldf therefore be. included in the. ITS; 'To: add this function.1the format 1oflthe1 specification is changed to match other;simi1ar 1.nstrumentation specifications. . Table ~3.3.51"is added.' a new action added;isome LC0;andtsurveillance details are. moved 1to the new table; and .

aLnew surveillance;is added;for'the new function.

3.3 116 Not applicable to CPSES. See Conversion Comparison Table (Enclosure 6B).

3.3 117 Not applicabic to CPSES. Scc Conversica Comparison Table (Enclosurc SB). This change to ITSf 3;3.1 Condition. R' reflects o.3,3 117 CPSES Differencesfrom NUREG-1431 -ITS 3.3 12 12/15/98

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3 Page 18 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-115 cur Adds CPSES1 specific l Automatic Actuation. ylN/ANo N/ Ayes N#No NMNo L1 l.

Actuation Relay: function ~to'ITS 3.3.5; 1 CP-3.3-0 3.3-116 ACTION J of ITS 3.3.2 is not used since DCPP does not rely Yes No No No on motor-driven AFW pump start with loss of both main FW pumps.

3.3-117 This change to ITS 3.3.1 Condition R reflects current TS Yes "; nct in cur. cat Yes Yes

! 0-3.3-11 r l

Table [3.3-1. ACTION Statement 112] which was based on NRC & Yes _ __

Generic Letter 85-09.

3.3-118 This change is for consistency with ITS 3.7.10 Yes Yes Yes Yes Condition [G].

3.3-119 This change reflects Callaway-specific BDMS analysis No No No Yes restrictions associated with RCS mixing volume and dilution flow rate. These are administratively controlled under the current TS, as approved in OL Amendment No. 94 dated March 7, 1995. However, with the conversion to ITS 3.3.9.

these analysis assumptions should be included in the body of the TS.

3.3-120 ITS 3.3.1 Ocnditica 0 is rcviscd to rcficct ITS SR 3.2.4.2 Ves N/A YesLN/A Yes;N/A Ves;N/A cnd CN 3.215 i- thc 3/S.2 p;ch;;;. ".at~'used 0-3.3-11 ' l 3.3-121 For Callaway. ITS 3.3.9 is revised to reflect that only one No No No Yes BDMS train is required OPERABLE in MODE 5 and that the suspension of positive reactivity additions and accelerated SDH verifications are required only if no source range neutron flux indicator is OPERABl.E.

3.3-122 ITS 3.3.1 Applicability Note (b) for Functions 1. 5, 19-21 Yes Yes Yes Yes and Conditions C and K are revised to replace Actions 3.3-016 l requiring the RTBs to be opened with actions that ensure subcriticality is maintained (i.e., by fully initiating action to: inserting all rods and ensuring the Rod Control System is incapable of rod withdrawal) yet do not initiate a feedwater isolation (P-4 and low Tm) in MODE 3.

consistent with traveler TSTF-135.

CPSES Conversion Comparison Table -ITS3.3 12/15198

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

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: WC 3.3-019 APPLICABILITY: WC, CP, CA, DC REQUEST: In the conversion from CTS to ITS, informatie 1 contained within Action Statements that modified the initial required action was reformatted as a Note. Based on formatting requirements of NUMARC 93-03, " Writer's Guide for the Restructured Technical Specifications," the span of a Note is limited to the width of the text it modifies. Two case types currently exist within the ITS which require revision in order to meet both the intent of CTS requirements and formatting requirements of NUMARC 93-03. ,

I in the first case, notes span the full width of the Required Action column when they should only apply to a single Required Action. Notes that fall within this category and require reformatting to conform to both CTS and NUMARC 93-03.

In the second case, notes span only a single Required Action when they should apply to all Required Actions for the associated Condition. Notes that fall within this category and require reformatting to conform to both CTS and NUMARC 93-03. It was never the intent of the CTS that the clock for shutdown actions should start when a channel was bypassed for testing as allowed by these notes.

ATTACHED PAGES:

Attachment No. 9, CTS 3/4.3 - ITS 3.3, Instrumentation Encl. 5A 3.3-3, 3.3-27, 3.3-28, 3.3-29, 3.3-30 and 3.3-31 Encl.6A 14a Encl.68 22 !

l J

l l

l

l l

RTS Instrumentation 3.3.1 l

l l D. One Power Range Neutron --

- -NOTE- - ---- - 4-3.3 37-a Flux-High channel The inoperable channel or inoperable. anothetchannel;may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing and setpoint adjustment of other channels.

D.1.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 1

AND D.1.2 Reduce THERMAL POWER to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s 975% RTP.

QB D.2.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND s

".2;2 D --- -

NOTE--

T-Only ."Ot Only; required 33y019 g3 to be performed tmt4l 12IGt3Jefter.ii.Rt fre;;. er,; when th when thel,P'ower Range Neutron 20 Flux ch;nnel input inputito QPTR is inoperabic :nd3lC"".".

"0" Eft li: > 75% "TN Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

( 9-2-0 Perform SR 3.2.4.2.

QB 1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D.3 Be in MODE 3 i t

1 (continued) 1 1

l 1

CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-3 12/ISA8

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. .

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

One train may be bypassed for up 019 to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

........................ ) .B: ,

C .' estore train to OPERABLE 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months status.

m l

l C.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ANQ l C.2.2 Be in MODE 5. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months 1

, r x "

l D. One channel inoperable. ) B-1 l

f ..............N0TE -- --- -

l The inoperable channel [or :3.3 37:

l another. channel. may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for B' w surveillance testing of other channels. /

l y

l

! D .' Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l \

l s l

D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l 5 l

l D.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months (continued)

CPSES Markup ofNUREG-1431 - ITS 3.3 3.3-27 12/15/98

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

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment Pressure fE-4 channel inoperable. - ----- - -NOTE -- - --

3 __

One additional channel may be bypass *4' for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for ) [3f3g19 surveillance testing.

...............................y [

Ell Place channel in bypass. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months E

E.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months M

E.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months F. One channel or train F.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. OPERABLE status.

M F.2.1 Be in H0DE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months M

F.2.2 Be in MODE 4. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months (continued)

I l

l CPSF9 h1aAn 2 ofNUREG-1431 - ITS 3.3 3.3-28 12/15/98

l ESFAS Instrumentation 3.3.2 ACTIONS (continued) l l

CONDITION REQUIRED ACTION COMPLETION TIME l

f x G. One train inoperable. f G-1 3.3 145 j ..............N0TE ------ - -

3'3# '

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance -8 ,

testing provided the other train ;

l 1s OPERABLE. l

)

{ G1. estore train to 0FERABLE 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months i

status. !

l

% l G.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

1 AND G.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months i

r ~~

H. One train inoperable. E4

..............N0TE- - - -

K One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance B s testing provided the other train is OPERABLE.

................................j

)

( ll;l Restore train to OPERABLE 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months status.

M H.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued) l l

CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3 29 12/1588

r ESFAS Instrumentation 3.3.2 l

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. One channel inoperable. 3.3 145

3'3#

..............N0TE --

The inoperable channell.or anotherichannel may be bypassed g

)

T B.

for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for l surveillance testing of other j channels. /

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months j .I 1 Place channel in trip.

2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I.2 Be in MODE 3.

J. One Main Feedwater Pumps J.1 Place Pscstcrc channel to 6 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months trip channel inoperable. ^PEPsASLE status. in_ trip.'; 3.3-561 M

J.2 Be in MODE 3. 54 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued) l l

1 l

l l

1 I

l CPSESMarkup ofNUREG.1431 - ITS 3.3 3.3-30 12/15/98

A. a .am ._aa al _ ,l - 4,.,.2 _,.. . _-2 a a # g, ._,

4 ,,

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. One channel inoperable. .

.............N0TE............. 3.3 145 i ' One additional channel may be 0 3.3 019 h

bypassed for up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months for l surveillance testing. . B .- ,

.............................. )

K .'1 ace channel in bypass. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 03 K.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months MD K.2.2 Be in MODE 5. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months (continued) l l

I l

l l

1 4

CPSESMarkup ofNUREG-1431 - ITS 3.3 3.3-31 12/1588

CHANGE NUMBER JUSTIFICATION I

3;3f141 Not :. appl.icablelto;CPSESMSee _ Conversion ; Comparison; Table CA 3.3 002

.( Enclosure;168)]

Si3f142 Adds;"ottrai.ns"atoilTS.!3;3.1 Condition"Auconsi. stent with;ITS m-3.3-006 l 3;3.;2[and; travel.erATSTFjl35?

3;3:143 The FrequencyfofilTS;SR;3:3;1;1511sireyisedLtoireflectitraveler TR 3.3 007

TSTF2311RJhe: Applicabilitylof;theseLTurbinelTr,ipFunctions ;

l begins;1n1MODEi1E:atithel 9;Intetlock;.(50%;RTP)liThe;STS

! Frequency;M Priorito teactor;startup,"lislinconsistent;With1the Applicabilityiof;these? Functions which can be;testedjatipower,1with pinimal; perturbations 1to;plantisystens{ These!TADOTsiare; typically l

performed:prioratoJoading;thelmainiturbineRifinot;petformed,within the l

previousf311 days?.7Both;Ca11awayland; Wolf C_ reek: have;f11ed#Rsl[5] l l regarding;thislissueEThis:changelwasj previously; approved:for3vogtle.- :

l l

3;3s144 Not applicable lto;CPSESMSee;Conversionicomparison! Table i (Enclosure;6B); 0 3.3 144 l 3'.31145 In convertingLfrom; CTS;to.;ITS E1nformation; contained withinlan Action _ Statement;thatimodifiedfthe initial.l1 required: action.was convertedito;af ote.iN Basedioniformatting fequirementsfof NUMARC 93f 03,i.:"Wr:iterisiGuide;fot Restructured Technical: Specifications ~ ":the ,

spanfoff aiNotehis;11mitedjtoithe, width;of;theitext:1t;modifjesMTwo:ca types; currentlyfexi stiwithinitheJITS: which ' requi reirevi sionii n iorder; meet bothfthelintent[ofCTSlandl formatting; requirements 20f;NUMARC'9303llIn the:first:caseEnotesispan:theiwidth of;theiRequired; Action column,"but the;intentfinLCTS;is;tolmodify:ajsingle1 required: action [JIn the"second case,1 Notes 1spania! single; Required"ActionWbut applicationfoft the Note within(CTS."?affects:all? Required; Actions forithe;associatedjCondition L l The span,offaffected_'_ Required.. Action'. Notes hasLbeen revised;to. meet both the intent 1of;the CTS ~andiformatting, requirements of,NUMARC 93_03; l

l l

CPSES Differencesfrom NUREG-1431 -ITS 3.3 14a 1H1888

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 SECTION 3.3 Page 22 of 22 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3;3 140 Changes to RTS'and ESFAS DT Functions are made to; reflect No No No Yes Callaway OL" Amendment'No:7125: dated 4/13/98: ICA-33-007 I' 3.3-141 Changes to ESFAS;FeedwaterfIsolation Functions'are'madeito No No No Yes reflect.Callaway.0L Amendment No;J125 dated.4/13/98; [ CA-3.3-002 l 3.3-142 Addsytrain* to;ITS Condition A; consistent with,ITS Yes Yes Yes Yes 3.3'2)andLTSTF-1357

. lTR-3.3-00$l 3.3-143 Revise SR 3.3.1.15 Frequency per; traveler _TSTF4311""; Yes Yes Yes Ye5 TR-3.3-007 l 3.3-144 SR 3.3.7 3 andl3.3.7.4 arel deleted for.;DCPP'since there^are_

No Yes No

^-

No 0-3.3-144

- ^

no' actuation logic;or: master., relays' associated with the l CRYS pressurization system actuation via the CRYS atmosphereLintake radiation monitors { _

3.3-145 The span of affected Required Action Notes has been revised Yes Yes Yes Yes to; meet.both.the intent of the CTS and. formatting WC-3.3 019 l requirements of..NUMARC~ 93.03:

CPSES Conversion Comparison Table -ITS3.3 12/13/98

I l

ADDITIONAL INFORMATION COVER SHEET 1

ADDITIONAL INFORMATION NO: O 3.4.11-3 APPLICABILITY: CA, CP, DC, WC REQUEST: Change 4-05 LS 31 and Difference 3.4-39 Comment: TSTF-113 (presently Rev. 4) has not yet been approved by the NRC staff.

FLOG Response (original): TSTF-113 Rev. 4 revises the shutdown requirements of ITS I 3.4.11 to allow the plant to reduce T,, to <500 F within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , rather than MODE 4, to l address the concern of entering LCO 3.4.12 Applicability with one or more inoperable PORVs. l The shutdown requirements of ITS 3.4.16 are also revised, for consistency, to allow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to reduce T., to < 500 F. ITS 3.4.11 Condition B and C Bases changes have been made to the Callaway submittal to reflect Rev. 4 of the traveler; no changes are required for any other plants'submittals. The FLOG continues to pursue the changes proposed by this traveler.

FLOG Response (supplement): Based on the present status of the generic change process for the STS, it appears that traveler TSTF-113 will not be approved by the NRC in time to support the initial license amendments for the FLOG plants. In order to facilitate the issuance of these initial license amendments, an alternate approach has been developed by CPSES and DCPP which relies on the CTS, plant-specific information, and/or the NUREG but does not rely upon the traveler. This alternate approach is hereby provided as an interim submittal to allow i issuance of the initial license amendments for CPSES and DCPP. The changes which rely upon the traveler can be processed in subsequent license amendments following approval of the traveler by the NRC.

Callaway and WCGS continue to pursue the changes proposed by this traveler as a beyond scope change, primarily due to their high COMS/LTOP arming temperature of 368F. Required Actions in STS 3.4.11 for one or both PORVs inoperable would bring the plant to MODE 4 (350F). This could involve entering the COMS/LTOP LCO Applicability (ITS 3.4.12) with no means to mitigate a cold overpressure event since RHR is just being aligned for shutdown cooling during this time frame.

Callaway and WCGS propcse to terminate the shutdown tracks in ITS 3.4.11 at an RCS Tavg

< 500F, rather than 350F. At Tavg < 500F, saturation pressure is 666 psig. The lowest MSSV lift pressure is 1185 psig with a +3/-1% setting tolerance. The SG atmospheric steam dumps (ASDs, WCGS refers to these valves as the SG atmospheric relief valvss or ARVs) have a set pressure of 1125 psig. Operation in MODE 3 with RCS Tavg < 500F renders the effsite release

of radioactivity in the event of an SGTR extremely unlikely given: 1) the difference between the l initial SG pressure for this RCS Tavg and the ASD/ARV set pressure; 2) the secondary side l pressure increase would be driven by RCP and decay heat only since the plant is in MODE 3; and 3) operation of the steam dump to the condenser. The licensing basis SGTR analysis discussed in FSAR/USAR Section 15.6.3 uses worst case assumptions (e.g.,3636 MWt initial

' core power,18 MWt RCP heat, and 939 psia initial SG pressure for Callaway corresponding to 15% tube plugging) and ignores the steam dump to condenser to intentionally drive the secondary side pressure above the ASD/ARV lift setting to evaluate offsite doses. When i

consideration is given to the extremely low probability of lifting the ASDs/ARVs after an actual

. SGTR with RCS Tavg < 500F versus the real potential for entering COMS/LTOP LCO Applicability with no mitigation pathway, Callaway and WCGS maintain that the proposed change results in an enhancement to net plant safety.

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ATTACHED PAGES:

Attachment 10, CTS 3/4.4 - ITS 3.4, Reactor Coolant System Encl. 2 3/4 4-11 and 3/4 4-20 Encl.3A -7 Encl. 3B 5 Encl. 4 1,61,62 and 63 Encl. 5A - Traveler Status Sheet,3.4-24,3.4-25,3.4-26,3.4-44 and 3.4-45 Encl. 5B B 3.4-53, B 3.4-54 and B 3.4-55 Encl. 6A 7 Encl.6B 5 l

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1 1

REACTOR LOOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 1

l 3.4.4 Both power operated relief valves (PORVs) and their associated block valves shall l be OPERABLE.

l l APPLICABILITY: MODES 1. 2. and 3.

l Note:1 Separate Condition entry:is~ allowed for:each valve; s i mLs T -

ACTION:

l l a. With one or both PORV(s) inoperable because of excessive seat icekage i mL82 .>

I and capable'ofJbeing manually, cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore l the PORV(s) to OPERABLE status or close the associated block -- - ---

l valve (s) with power maintained to the block valve (s): oth se. 4-es+s be in at least HOT STANDBY w t_hin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months an _ccc ." '0 3.4.11-3

^^ '500"J" in "0T S!!UT000 n' HOT;SQwithin the followin hours. A l b. With one PORV inoperable duc to causcs other than excessive ;;;t b-u ; a icekogc and,noticapableiofgbeing manually; cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve: restore the PORV to OPERABLE status within the fc'r"- 79 hnurs or be in HOT r*" "

~

STANDBY within tha next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and C^M T__.te-400*j in liOT SiiUT00"QHOT SHUTDowJnithinthefollowing6hourg g

c. With both PORV(s) inoperable duc to causes other than excessive scat ic;koge and:.noticapableLof;being: manually' cycled, within 1 [ mts .

hour either restore at least one PORV to OPERABLE status or close its associated block valve and remove power from the h1nele valve and : mM n be in HOT STANDBY wi+h4a " next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and9-^ ' +- "$

emm,~ 6HOTiSHUID0i3D in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

m, um, K Q-3.4'11 3 l d. With one or both block valves inoperable *, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve (s) to OPERABLE status or place its associated PORV(s) in manual control. Restore at least one block valve to

, OPERABLE status within the next hour if both block valves are inoperable; l restore any remaining inoperable block valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ntha ~4 m- ce in at least H0 anRY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and T tc '500$i{liOT S!!UT00" n H0T SHUTDOWN e following 6

e. The provisions of Specification 3.0.4 are not applicable.

4 09 LS S ACTION 'd,does not apply.when block valve (s)11s inoperabl.el sol.ely as a 0-3.4.11 4

resultfof complying with1 ACTIONS b orce; t

CPSESMark-up of CTS 3/4.4 3/4 4-11 12/1S//98

REACTOR COOLANT SYSTEH l

3/4.4.7 SPECIFIC ACTIVITY l

LIMITING CONDITION FOR OPERATION l

3.4.7 The specific activity of the reactor coolant shall be limited to:

a. Less than or equal to 1 microcurie per gram DOSE EQUIVALENT I 131, and I l

b. Less than or equal to 100/E microCuries per gram of gross radioactivity.

APPLICABILITY: MODES 1, 2, 3?, 4, and 5. i et-Ls

ACTION

MODES 1, 2 and 3*: l l

a. LCO 3.0.4;isinot; applicable (for; operation in this' ACTION statementy vs4LS i With the specific activity of the reactor coolant greater than 1

microcurie per gram DOSE EQUIVALENT I 131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months l during one continuous time interval or exceeding the limit line shown on F ure 3. - thi 4.or,e l dd reduce ytt T., in less be at least H0T than 500 STANDBY"k;n F with fell;w C 0heurhr

?.4.11 3 l

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; and -

b. With the specific activity of the reactor coolant greater than 100/E microCuries per gram, be in at least HOT STANDBY u. m a 5 heur; an; r; _ l Q than 500 F within ,,,,,- ,ng) nouis. l MODES 1, 2, 3!, 4. and 5: 1 s.on-ts ' )

1 With the specific activity of the reactor coolant greater than 1 microcurie !

per gram DOSE EQUIVALENT I-131 or greater than 100/E microCuries per gram, '

perform the sampling and analysis requirements of Item 4.a) of Table 4.41 until the specific activity of the reactor coolant is restored to within its limits.

i l SURVEILLANCE REQUIREMENTS l

4.4.7 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.41.

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With T,y greater than or equal to 500*F.

l CPSES Mark-up of CTS 3/4.4 3/4 4-20 12/15i98

CHANGE NUMBER NSHC DESCRIPTION 4 02 LS-6 In conformance with NUREG 1431 Rev. 1. the allowance for PORV inoperability has been expanded from previously only allowing block valve isolation when the PORV was inoperable for seat leakage to allowing block valve isolation when the PORV is still capable of manually being cycled. With the PORV still capable of being cycled it is available for mitigation of accidents such as the SGTR but has lost the functionality of automatic pressure reduction. As loss of the automatic function does not result in a degradation of equipment which is required to operate during an accident, this change is acceptable.

4 03 M The times to reduce Mode for inoperable PORVs are decreased by one hour. This change is acceptable because it is a more restrictive change.

4-04 LG The automatic actuation of the PORVs is not credited in MODES 1, 2, or 3. Therefore performance of the channel calibration is unnecessary as a TS requirement and is moved to a licensee controlled document The portions of the PORV actuation circuitry required for [LTOP] are calibrated in accordance with improved TS SR 3.4.12.9.

Moving this information is consistent with the NUREG-1431 philosophy of moving requirements, which are not required to satisfy accident analyses, out of the TS.

4-05 LS 31 .hc shutdown requirc;cnt of CTS 3.4.4 would require 0 3 A.11 3 the phnt te reduce T, te '500'r within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , rathcr than 90 to tiODE 4. to address the conccrn of catering [LTOP] LC0 Applicability with inoperabic POP"s.

For consistency the shutdown requirc; cats of CTS LC0

[3.4.7] would be similcrly rcvised. The proposed change adds a relaxation to the ACTIONS associated with current TS LC0 3.4.4 by keeping thc cad point of the shutdown action above the LC0 [3.4.0.3] Applicability. No cred M is taken for the automatic actection of the POPS"s in liODES 1, 2. cr 2. Credit is taken for the manual operation of the POR"3 during a Stca: Cencratcr Tubc Psupturc. The capability to manually cycic the POR"3 will bc unaffected by this changc. The release of radicactivity in the event cf = SGTR with RCSmT -400'I is unlikely since the saturation pressurc of the reactor cociant would bc less than the lift prcssurc of the main stca; safety and [SC atmosphcric relief] valves. This change is consistcat with TSTT-113. NotLApplicable.to CPSES?f See Conversion Compar.ison! Table ~(enclosure 3B);

4-06 LS-32 Not Applicable to CPSES. See Conversion Comparison Table (enclosure 3B).

4 07 LS-33 Not Applicable to CPSES. See Conversion Comparison Table (enclosure 3B).

CPSES Description of Changes to CTS 3N.4 7 12/15/98

CONVERSION COMPARISON TABLE - CURRENT TS 3/4,4 page S rf13 -

TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 4-04 This change moves the requirement to r .. .orm channel Yes - Moved to the Yes - Moved to the Yes - Moved to the Yes - Moved to the LG calibration of PORY actuation instrume station to a licensee FSAR. TRM. USAR. FSAR.

controlled document. ,

4-05 The shutdown requirement of CTS 3.4.4 would require the VesNo Z eafntaining VesNo - maintaining Yes Yes LS-31 plant to go to reduce T,,, to <500*F within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , rather CTS CTS ;

than go to MODE 4, to address the concern of entering [LTOP e LCO Applicability with inoperable PORVs. For consistency "

the shutdown requirements of CTS LCO [3.4.7] would be similarly revised.

4-06 This change provides a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time to restore an Yes No - Already part No - Already part No - Already part LS-32 inoperable block val

e. with the PORV placed in manual of CTS. of CTS. of CTS.

control mode. The current TS requires the block valve to be restored within one hour. or remove power from the solenoid.

4-07 This change provides a two hour completion time for Yes No - Already part No - Already part No - Already part LS-33 restoring an inoperable block valve when more than one block of CTS. of CTS. of CTS.

valve is inoperable, and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the remaining valves. The current TS requires the block valve to be restored within one hour for one or more valves inoperable.

4-08 Consistent with traveler TSTF-288 W9G-69, the requirement to Yes Yes Yes Yes LS-34 perform the PORV and block valve cycling surveillances is revised such that the surveillances are only required to be performed in MODES 1 and 2. l0-3.4.11-2 l 4-09 Consistent with traveler WOG-87, the requirement to perform Yes Yes Yes Yes LS-36 the 92 day surveillance of the pressurizer block valves (i.e., perform one complete cycle of each block valve) is revised such that it is not required if the block valve is l 0-3.4.11-4 l closed to meet ACTION a of the current TS LCO 3.4.4. In addition,ra Note 11s added;to' ACTION. [d];to prevent entry solely duelto: inoperable.PORV(s)'under Actions:[b oric];

5-01 This change rmves the Steam Generator Tube Surveillances to Yes No - Same as CPSES Yes Yes A SR 3.4.13.2 and the Administrative Controls Sections 5.5.9 change 1-14-A for and 5.6.10. CTS Section 3/4.0.

CPSES Conversion Comparison Table - CIS 3N.4 12f15/98

NO 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 Specifications) . . . . . . . . . . . . . . . . . . 10 "M" More Restrictive Requirements. . . . . . . . . . . . . . . . . 12 IV. Specific No Significant Hazards Considerations "LS" LS 1................................................ 15 LS-2................................................ 17 LS-3................................................ 19 LS 4............................ ................... 21 LS 5................................................ 23 LS-6................................................ 25 LS 7. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 8....................... ........................ 27 LS-9................................................ 29 LS-10............................................... 31 LS-11.......................... .................... 33 LS 12.. ......................................... 35 LS-13............................................... 37 LS-14............................................... 39 LS 15............................................... 41 LS 16................... ........................... 43 LS 17............................................ .. 45 LS 18............................................... 47 LS 19............................................... 49 LS 20............................................... 51 LS 21............................................... 53 LS 22. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS-23.................................. ............ 55 LS -24. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS - 25. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS - 26. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS - 2 7. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i ca bl e LS-28............................................... 57 LS 29............................................... 59 LS 30.................................... . . .Not Applicable 0 3*4'11 3 LS 31. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Gat _ Ap )l i cabl e 6D -

LS - 3 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iot App l i cabl e LS - 33. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 34.............................................. 64 i

LS-35........................................Notused66 LS-36.............................................. 68 0-3.5.5 1 LS 37.............................................. 70 LS 38/.. W.. 4 .v...i..w .J...e.......J ..... M 72 V. Recurring No Significant Hazards Considerations "TR" 0-3.4a4-3 TR 2.............................................. . 724 TR-3................................................ 746 CPSESNo SignificantHazards Consideration - CTS 3M.4 1 12/1S/98

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CPSESNo SignifIcant Ha:ards Consideration - CTS 3N.4 6I INIS/98 I

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CPSESNo Significant Ha:ards Consideration - CTS 3N.4 M i2/1S/98

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CPSESNo Significant Ha:ards Consideration - CTS 3N.4 63 12/15/98 l

t t

I

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 26 Incorpor ated 3.4 32 Approved by NRC.

TSTF 27, Rev.3 0 Incor.; orated 3.4-33 Approved!by;NRC g.3,4,z.1 TSTF-28 Incorporated 3.4-22 Approved by NRC.

TSTF-54, Rev. 1 Incorporated NA Approved;byiNRC 7g.3.4. cog TSTF 60 Incorporated 3.4 15 Approved by NRC.

l TSTF 61 Not incorporated NA Minor change that is adequately !

addressed in the Bases l TSTF-87, Rev. 21 Incorporated 3.4-31 Approved by:NRC. rR 3.4 ac4 l

TSTF-93, Rev. 31 Incorporated 3.4 17 Approved;byLNRC. g a.3,4,g.:

l i i TSTF 94 prev;11 Not incorporated NA Retained current TS. TR 3.4 0(5 TSTF 105 Ir.corporated 3+38 3.3.4.11 l TSTF 108, Rev. 1 Not incorporated NA LC0 3.4.19 does not apply.

IF113."cv.4 Ir.corporated 3+39 - -

0 3.4.11 :

3 TSTF-114 Incorporated NA Approved by NRC.

TSTF-116. Rev.2 Incorporated 3.4 36 o.3.4.13.;

1 TSTF 136 Incorporated NA Approved,by.NRC TR 3.4 005 TSTF 137 Incorporated NA Approved ~by NRC TR 3.4 005 TSTF-138 Not incorporated NA Inconsistent with RCS loops requirements of ITS 3.4.5 and 3.4.6.

l l

i l

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve E9- ;= fn NOTE n fru9Efffai inoperable. 8 equi _rediActions_do not: apply when; block yalvelis; inoperable 3 4.g solelyjasiairesult offcomplying o.3,4,11 4 WithRequiredJctions.B~.21or E 3:

Eibliff9F12M9? REEF 5 C.1 Place associated PORV in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months manual control.

l AND

C.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

D. Required Action and e Inj'd:t;;;tionto,r;; TAT b i:tcj h p/!(:);;Q41;;k;;;1';;1t;l( s j

l associated Completion Time of Condition A. B.i

[ 6 g

0-3.4.11-3 or C not met.

l D. 1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

AND D.[2)S; in "03E-4-- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

,&c: Jat:fE999.

Be:in MODE 4 i

l l

t i

l l

L CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4-24 12/15/98 i

l l-

Pressurizer PORVs 3.4.11 CONDITION REQUIRED ACTION COMPLETION TIME E. Two [or thrcc] PORVs /El s. :Ir.iti;t:3ctier_;t; I n di;t:12 inoperable and not capable of being [ ;;;;;rc er.c "0"Rt; 6

' B PS?

manually cycled.

\

M s

E.4@ Close associated block valves. I hour M

E. h Remove power from associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valves. g E 0 3.4.11-3 Be in MODE 3 E. f 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .e M

E. Scin"0DE1,"cduce gte ;t"""t- Be :in .

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months MUDE '4

- 9 T-l 79 VjNOTEf-y 9 .i nt J --

F. More than one block Required: Actions'do'.not apply 3,4,47 yalve inoperable. when block; valve;1slinoperable 0-3.4.11 e sol _el ylas :a; resul t:of; complying wi.th Required lAc_tions B.2;or E.3

. .;. .y. 9 . =:. y . . . .p 9 .;:.;.;

F.1 Place associated PORVs in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months manual control.

M F.2 Restore one block valve to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LB PSL OPERABLE status [if three block valves arc

inoperabic] .

l

-Sl@

f.3 ilcstore rc ining 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ;

B PS block valvc(s) to OPEPABLE stete -

I CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4-25 12/15/98

l Pressurizer PORVs 3.4.11 CONDITION REQUIRED ACTION COMPLETION TIME e ,

G. Required Aetion and m..

,_2A2_m_

........s.......,.

__i2__ m v

. . _.-. .2

. .a. _m associated Completion ispic5.c. 'leM'qiyc g Time of Condition F not( to-OPERAIEE-st-etet- y o.3,4,113 met. \ 8lE l ,

k ~ i G. 1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 8!Q l

l G. 2 Br ' "^r '- P,;decc 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

, . met '.50.0V- Be :in

~ - -

MODE!,4 i l

l SURVEILLANCE REQUIREMENTS I SURVEILLANCE FREQUENCY SR 3.4.11.1 -- - -

-NOTES - - - --- -- --

1:-Not required to be metperformed with block valve closed in accordance with the Required

!3.'4-479 l Action of Condition this: LCO." A9 3 cr E. 3.4-47 l Q 3.4.11 4 220nly'rlequiredito be';performedlin~. MODEST.II -. !

and.:2

, ........................................... .!.3.4-35 : -

l l r3:42471.

! Perform a complete cycle of each block valve. 92 days ,-r

_--..2m m_ m,__._ .. ,... _,___2 2_

snvwy u. , vy 3 .v s feu ww aa v yweg v.svw wsvww.

gia

},4 4/

u_

2____

,~ m ..u..% , ,.,__2

.2m _ _ .

m. m 4 _m _ _ _ _,

. . . . . . o.3.4.11-4 a_xn-

-e _- ._ ~ 2. 2. s. 2, _.. _ _ m

. %u =, . . ::=.z . m ._m' =.N0TE

-=._

m m;_==mw_=m ' ,; -

3 4~ Only requireditolbe:performedlin MODES!1;'f,CJ and 2 l ....=.:..=:=.....=_=;;.=......=,..

- - ~ ~ ~

SR 3.4.11.2 Perform a complete cycle of each PORV. 18 months 4

.:B1 -

SP,3.4.11.3 Perfor; o cc pletc cycic of cach sciencid [18] =cnth; (BPSl

air control valve and check valve on the

cir occumulator; in POP" control systems.

CPSESMark-up ofNUREG-1431 -ITS 3.4 3.4-26 12/15/98

~

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LC0 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: H0 DES 1 and 2 MODE 3 with Res average temperature (T,,,) 2 500*F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 - -- -

- Note -- -

> 1.0 gCi/gm. LC0 3.0.4 is not applicable.

A.1 Verify DOSE EQUIVALENT Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months I 131 within the acceptable region of Figure 3.4.16 1.

M A.2 Restore DOSE EQUIVALENT 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months I 131 to within limit.

E3~4-22"~ l Gross specific activity S.1 "arform SR 3.4.10.2.

B. 4-heurs of the reactor coolant 2 l r,ct within limit.> 100/E

'3.4225w~

1.

pC1/gmi M 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B.12 Ra in MODE 3 ith N g h./S.500*F. 0 3.4.11 3

+m = suu TT _

r e M ( 12MT-B.21Rd =0,tc Im : 500 ,E.~

l W. J (continued)

CPSES Mark-up afNUREG-1431 -ITS 3.4 3.4-44 12/1S/98

l RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in. MODE with

^

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion avg I 500!f 'N N Time of Condition A not 7 .,;; i .

met.

,,A N 08 ..~-- o.3.4.11 3 C.2 "^tec%K=3CC:(+

DOSE EQUIVALENT I-131 in the unacceptable region -~

of Figure 3.4.161.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific 7 days activity s 100/ C1/gm.

SR 3.4.16.2 - - - -

- -NOTE --- - - ---- -

Only required to be performed in H0DE 1.

Verify reactor coolant DOSE EQUIVALENT I 131 14 days specific activity s 1.0 Ci/gm.

AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of a 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued) i CPSESMark-up ofNUREG-1431 -ITS3.4 3.4-45 12/1588

Pressurizer PORVs B 3.4.11 BASES reasonable, based on challenges to the PORVs during this time period, and provide the operator adequate time to correct the situation. If the inoperable valve cannot be restored to OPERABLE status, it must be isolated within the specified time. Because there is at least one PORV that remains OPERABLE, an additional 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is provided to restore the inoperable PORV to OPERABLE status. um If the PORV cannot be restored within this additional time,. 03.4.113J the plant must be brought to "^^" '

ch th: LC0 dess -

. . - .. _ .. ,_ , . -. . . M D 4 a;nuushin.Wh1

@ LC01doesinot apply 3 as requ1rea oy conalt16n v.

C.1 and C.2 If one bloc.k valve is inoperable, then it is necessary to either restore the block valve to OPERABLE status within the Completion Time ;

of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or place the associated PORV in manual control. The prime importance for the capability to close the block valve is to isolate a steck open PORV. Therefore, if the block valve cannot be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the Required Action is to place tne PORV in manual control to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck open PORV at a time that the block valve is inoperable. The Completion Time of ,

I hour is reasonable, based on the small potential for challenges to j the system during this time period, and provides the operator time to '

correct the situation. Because at least one PORV remains OPERABLE, the operator is permitted a Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the inoperable block valve to OPERABLE status. The time allowed to restore the block valve is based upon the Completion Time for restoring an inoperable PORV in Condition B, since the PORVs are may not[be capable of mitigating an overpr;nur; event if!theMnoperable blockfvalvelisinotNullyfoponyA.a ple;;d in =n=1 centrol. If the block valve is restored within the Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the power will be restored and the PORV restored to OPERABLE status. If it cannot be restored within this additional tine, the plant must be l brought to K iwut s1n;wn1chithe:LCO;does(not, app g LC0 dec: net :pplyut 'Tr ' 5 hith T.,, M.. s i required by Condition v. ine hequired Acn w w are modi i bylalNotefstating;that the Required Actions do not; apply 1 _.

0 3.4.11 4 the; sole' reason;fordthe'blocktvalve being(declared l inoperablejisiasla:resultiofipower being;removeditoTcomply I with:other; Required:ActionsGIn:this event R the; Required' Action _sifer inoperable;PORV(s)1(which(requirecthel block valve. power;to;be_ removed i oncefitdsl closed)1arel adequate;toladdress ;the. condition; j D.1 and D.2 If the Required Action of Condition A, B, or C is not met. .

then the plant must be brought to a H0DE in which the LC0 i does not apply. To achieve thic status, the plant must be 0 3.4.11 3 brought to at least MODE 3 95in-T -499V-within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months diiTo MODE 7 4 w11;nin 12.nourh;8tc "00C 4 within 1Z neur . g. -wm=_iRT;,; Toito be jn109t;-

(continued)

CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4 53 12/1S/98 l

l i

Pressurizer PORVs

! B 3.4.11 i BASES i

i

, indi;t:ly te ce./,jn=l;ffert: te r;;tero t ir.ep;;ble 0 3.4.11 3 l " = v; :.r.d bl u t 5:l x t: OrErx tr :t;t a. _Thi;;.;ill ; n;;r; l

l ;;p di...t = nur; s.r; t 2 = t; r; nt:bli c th; eg rebjlity.;f,th; "00"(;) e d bl x k v;1v;.whil; n int;ining

-!=t :=ditir: dr;: "a"~ W' '-~ '"- "% i;m alivwed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In MODES 4, and 5 and:6;(with the;reactorfvesselihead'on), automatic me4ntaining PORV OPERABILITY may be required. See LC0 3.4.12.

E.1. E.2. E.3. and E.4 If more than one PORV is inoperable and not capable of being manually cycled, it is necessary to either restore at least one valve within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or isolate the flow path by closing and removing the power to the associated block valves. The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is reasonable, based on the small potential for challenges to the system during this time and provides the operator time to correct the situation. If-ene FOR" is rcstored and one POR" rc= ins inoperabic, then the plant will bc in Condition S with the ti c clock started at the criginal declaration of having two [cr threc] "0R"3 inopcr21c.

If no PORVs are restored within the Completion Time, then the plant must be brought to a MODE in which the LC0 does not apply. To achieve thh status the plant must be brouaht to at 1 m t MonF M3 0-3.4.11 3 dithin 12~ hourrJ am --s 4uwithin 43within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hour; ,a ., @to MODE b

1= i i;;; ired te b; jai; nr.; - ..as;y..t; r;;ter; th; inep r 21; "0""lte.0"E"X LE'

t;t;;. ,This will_; ; ;r;

xgdie..^ nnurn;r.r; t2;; to ic ;t: blic th; spreility c' en; "0"" whil; = int:ini= c1=t ;;nditism 2;;; "00 4 but 1:;s L the 50aYn ine allowed Completion Times are reasonaole. Dasea on-operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In MODES 4 end 5 and 6L(with the reactor vessel? head on), automatic mintaining PORV OPERABILITY may be required. See LCO 3.4.12.

F.1. and F.2. =d I.3 If more than one block valve is inoperable, it is necessary to either restore the block valves within the Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or place the associated PORVs in manual control and restore at least one block valve within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and restcrc the rc=ining bicek valve within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The Completion Times are j reasonable, based on the small potential for challenges to the i

! (continued)

CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-S4 12/1S/98 i

i

Pressuriger PORVs B 3.4.11 BASES (continued) i i

system during this time and provide the operator time to correct the situation. TheiRequired Actions lare modified 0 3.4.11-4 byfa'Noteistating;that;the. Required:Actionstdo not . apply;1f the: sole reasen; for; thel blocki val ve' being : decl ared inoperable 11s'as:alresultfofl power being removed to comply with other: Required'ActionstiInithis eventRthe* Required Actions;for, j inoperable.PORV(s)A(which require _the block (valve' power lto.be l

removed;oncedtlis closed) fare;adequatelto address;the1 condition; G.1 and G.2 If the Required Actions of Condition F are not met, then the plant must be brought to a H0DE in which the LCO does not apply. To achieve this status. the plant must be brought to at least MODE 3 p ,, M within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and to "00E 4 within -

12 hourgnd tolNuutg wn.nm a nourg _A_- r; .

_ _2 m

,;; 3 0 3.4.11-3 M% iP W WT ,5, , 5 SF . . U Wy B T WDN WW; B,W

, ,W, - T 95 WW 5 g , j3 I E 3 T. 3 is WWMc WW ,.E W eM W%FU h m - __m,. .._,.._,_e..

2--- ......-__m... ,m_

, 3 3 5 g ap , T.a TU ,3, DU WE . 55--,' .W ww u to ,, . W 5 .w s er / _, 4.W

,%PT he.ir i.,a.m. . ey wgg Wwer e s _n._ _ __r_u ent.- ,-- ss . --- = ....- _. _ __ _.._ a_L ._.u.

l _ ._ ._ _._., ,_e s.._, . s . .. s. . .. . ,. .,...,-.,

. a n n mv . ..

. . . - - . .. . . . . . . _,,,. _m

.A2i_ __2_A_2_2__ ___;>m___ c-end-b .eelt, v. e,3 .

, ... ---- -- .--- ,a L.

.A l

t'. n EC-~ :Ee allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging l plant systems. In H0 DES 4 cnd 5 and:6 (with the reactorivessel; head l on), automatic maintaining PORV OPERABILITY may be required. See LC0 3.4.12.

! SURVEILLANCE SR 3.4.11.1 l REQUIREMENTS i Block valve cycling verifies that the..,<._,_s,_

..mu_ m,__<

valve (s) can _,___

be opened and ;cl osed.,, y_.. 1 -r.. ._ .._ .

2,,,

___ m ____ .mm m_

,_m___ ....s,,

_, ,__m__

_. s..,,,,,..

n __ r. 2, 0 3.4.11 4 u - ; ww. swie

,.v g br 3 ,wr yw ginnigw U s, ww, -w is U VU s er,, w t , wvg r%4 U b U wt g _p ,WE ,,he IE r,ccded. The basis for the Frequency of 92 days is the ASME Code,Section XI (Ref. 3). M the block. .valve

__..11.. . _1 _ .J is .L.cic,cd to isolate a Anr*n A n

f T7*V _, .L.

"0""__that L1 L ..1.._

is capabic J. _,

of being j .uru s suu s s J bJwabu. b rw vi 6s v iLT E,.4 I i Vi bssw w i vbr% yuavs Iw wi i;portancc, because opening the block valve is necessary to perwR j the "0"" to be u cd for manual control of reactor prcssure. If the block valve is closed to isciate an othe wisc inoperabic "0";that isjncc-E-bl^ c' b;17;, ;T.cc'ly cycled, the maximum Ccaplation Ti=c to restore the "0"" and open the block valve is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , which is well within the allcuable limits (250 to extend the block valve Frcqucacy of ^2 days. Furtheracic, thesc test rcquirc; cats would be cm pleted by_, the reg.cning of a recently cissed block valvc upon

___.__u._._.,

. m ., b v. u v, .bL, .s. nnnu.

. vn bv vi nnen. m r .

e <

s a. . s_ . ,

i

___,_a__ _, u_ n__.4__; i_u___ ,. . ,b,4,,_

ubo. u_ en s

. vvv vy s b b i vi a vi bsis uswqu s a wu nw b i vi J iu i sisa 4 is .,r:1/ .

0 3.4.11-2 9

j CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-55 12/15/98 l

i

CHANGE NUMBER JUSTIFICATION 3.4 36 SR 3.4.13.1 and ACTIONS for LC0 3.4.15 are revised with i the addition of a note per TSTF-116. The note addresses the concern that an RCS water inventory balance cannot be meaningfully performed unless the unit is operating at or near steady state conditions. The note added to the l surveillance provides an exception for operation at less than steady stato conditions. The RCS water inventory balance will only be allowed to be deferred for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after re establishing steady state conditions.

3.4-37 Not applicable to CPSES. See conversion comparison table (enclosure 68).

, 3.4,38 P wm. _.._ J. .m..

. A _ _ A. . . J. &. L. T... PT. P i.n~. E J A_J A L. .w.wu o u .1. ,.

m_

m, J

_ _ &. L,vu LV,. .

L .L.s_. ..,%.

l which the RCS ficw rate arc verificd is r,cVed from the S",

l 3.4.1.4 to the Sases. licving this information to the Base . olicws the use of precision heat balances, cibow tops. and othcr acccptabic acthods in order to perform

! this verification and is consistent with the "U"EC-1431 philosophy of acving clarifying information and 0-3.4.1 1 descriptiva details cut of the TS to the Cascs. Not applicabl.eito CPSESCSee;conversi_on; comparison table (encIosure168)n 3.4 39 ;c shutdown requircacats of ITS 3.4.11 would require tf phr.t tc reduct Tm tc ',.500T within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , rather than unnr* A &m -JJ____ &L. _ _ - _ _ . - .c A.._J _ PtTAn9 i PA

svv6 7 bv uuusuaa bszu vvi sww I sa va t-I I bu s Iisy L,6 s vs J Lwv O A 16 . .J E L J___ __L1. nAnU_ u_ s j v . r . a s. ,A,y__1 J _ _ L Jiwy yiawuvi 1 J &niwu

. invywiuviw i vn v a . s . . . . ,

i 2 n__. ._i2___ __-._ma ... e ua___-n- r

2. _. . uw . ._ ,._ns.y.2 _ a g.3,4,114

. ..w..r b.

. -_ -- w. . . . . . . . , . ,

a n s _ 2 - a 2_m _, .~ 2_ u a _w __sa___ __ ___m___m2__

-w.=

., me_

-va ->====i...nu-t=*w;=*=rv" , -' a---

,.u= vn 2______Ls --nous _s ,_a __ nanu L s _ _.. .._ ..__s VI 4.. Dr ww , E T WWyg.5 UUVw I wn y % op g, g MT WM _ V5 E Vg] y_ M 3 WhW% V W 5 T w eP / _

&_ A n en .n. c _m .m.._ -rt _ _ _ 2---~_ __m2___ .2s,___..__

ww ,vs ha v ium.m., ep & 95 www . _ 5 I Th dw s vousuwwse r W ww, uw w s wp t ap, vt 5 g i vu idwt w

___um _ _ _ _ . . _ _ _ ___ m_L__ i_ __ __.L,.2_L .L.

u.nys.w s wriw, , esswu ewu .we us w,,, wurgwa y_ wv,sm.,w www w u geve; wayw

_____L21 u . _s nnnur_s r_--.s nnnu L1_ _ e- . . 1. _ _ s . .L a s _

wyw3,45U 3 s s wg , W 3, a .wn TJ ey g_ , % M t EM , I ,VM y , p 4 wwg% TM 5 YwW / , WI 5 5 5w 2_&_2.2__ _i _ _ a ua___ _t _... unne 2 L. .. 2___

rnw s y y w%s u Iu v v r3 y a wi r n. ,% .v_ i ww I, b u vt u e_ wwwwse,ssvwk,7 wts b t ,w e d t,han-600T: icr consistency, the shutdown requircacats'

_c v, vre

. s i v. T, . 4.ve __ _,__

us viov __

is.

J &_

. . J.s_ w_ ui.v u

_ , , . . . sq un u num a L_..__ &_ ' 0 3.4.11 3 i i.v

,,n_A,. u_n

, r ,+n

, _ -c.n. n.ep . T. uL J.

L___- -_-_

e .w o u , ,3% J.._ s.vo . J. . 6 w-oe _ &n . on

. J. & L ETF-113.

Not? applicable;to'CPSES; 'See conversion comparison table riosure=68)i

' ' ' ~ '

j l 3.4 40 Not applicable to CPSES. See conversion comparison table (encit.sure 68).

3.4 41 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

3.4-42 Not applicable to CPSES. See Conversion Comparison Table (enclosure 6B).

I CPSES Differencesfrom NUREG-1431 -ITS 3.4 7 12/1S/98

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.4 s or6 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.4-38 Ccn;istcnt with TST" 105. thc dctoil: on the cthod t;y which-the-ES Yes Yes No Yes No Yes No '

~

fica r;tc is scrificd orc ;c;cd frc; the SR 3.4.1.4 to thc Cc;c;. !

Consistent:with;DCPP_ CTS; sri 4.2.3'3.Tthe, details:on the method by which the RCSJflow rateJs ver.ified;is: removed:from STS1SRJ3.4;T.4; text? t 3.4-39 The shutdown requirements of ITS 3.4.11 would require the plant to / VesNo'E adopting VesNo ladopt Yes Yes reduce T, to <500T within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . rather than H0DE 4. to address ISTS1 format ISTS; format j l 0'3'4~11-3 l theconcernofentering[LTOP]LCO3.4.12Applicabilitywithinoperable( j w s PORVs. For consistency. the shutdown requirements of ITS 3.4.16 are also revised to allow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to reduce m T to <500Tg; che.g g

[C

@ a;stcnt with TSir-l u. 3 3.4-40 The Note to SR 3.4.1.4 would be modified to specify a plant specific No - See CN No - See CN Yes Yes power and to provide additional time to perform an RCS precision flow 3.4-51 3.4-34 rate measurement. ,

3.4-41 LCO 3.4.1 is revised to reference Tables 3.4.1-1 and 3.4.1-2 for RCS Yes Allowance No No No total flow rate limits for DCPP Units I and 2 respectively. added per Amendment 60/59. ;

3.4-42 An exception to SR 3.4.14.1 frequency to leak test PIVs 8802A, 8802B Yes No No No and 8703 has been added. This change is consistent with the DCPP ,

current TS. !

3.4-43 A new Condition C is added to LCO 3.4.1 to reflect the current TS of No . No Yes Nr Wolf Creek for RCS flow rate.

3.4-44 Steam generator levels for Modes 3. 4 and 5 are specified to ensure SG No No NeYes Yes tubes are covered. The Colloucy current TS did not ensure tube Q-3.4.5-2 coverage. Q.3.4.5-3

i CPSES Conversion Comparison Table -ITS 3.4 12/15/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.4.12-1 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4-49 Comment: WOG-100 has not yet become a TSTF.

FLOG Response (original): WOG-100 has been approved by the TSTF and is designated as TSTF-280. This traveler has been submitted to the NRC and is under review. The proposed wording in TSTF-280 was modified from WOG-100, and these modifications have been incorporated into the ITS (added "or" to LCO list and SR 3.4.12.5 Note was deleted). The FLOG continues to pursue the changes proposed by this traveler.

FLOG Response (supplement): TSTF-280 has not yet been approved by the NRC. This traveler is being withdrawn. In place of the traveler, the ITS is being revised to match the CTS and to incorporate some clarifying editorial changes as agreed upon in a cor.ference call with the NRC staff on November 19,1998.

ATTACHED PAGES: 0, CTS 3/4.4 - ITS 3.4, Reactor Coolant System Encl. 5A Traveler Status Sheet (second page)

Encl.6A 8a and 8b

l )

l l TRAVELER # STATUS DIFFERENCE # COMMENTS l

l l TSTF-151 Rev.11 Incorporated NA m 3.4 00s f

l l

l TSTF 153 Incorporated 3.4-01 Approved.bytNRQ m-3.4-005 l l

l l TSTF-162 Incorporated NA Approved _by1NRC 3 3,4 0c6 WOC-51. Rev.1 Incorporated 3.4 45 & See also CNs 3.4-18 and o.3.4-12-2 TSTF;285 3.4 0352 3.4 20. ;

)

W9G-60 Incorporated 3.4-35 JSTF;288 o 3.4.11 2 W00-57. Rev. 1 Incorporated 3.4 10 Approved'by NRC. DCPP TSTF 233 only. m 3.4 00s WOG 87 Rev.12; Incorporated 3.4-47 0 3.4.11 4 W9G-99 Incorporated 3.4 40 Applicable to Callaway and TSTFj282 Wolf Creek only. 0 3.4.1-2 WOC 100TSTF 280 (1[ot3 orporate 3-4-49 NA k approved by;_NRC 5 s -- t time _for.. License 0 3.4.12 1 Amendment; i

i

l CMNGE NUMBER JUSTIFICATION status withinitimeltf+27.2?hoursiallows!.,thelpla.ntito; exit Condition;BW:If; power;were not1restcred .toithe; block val.ve:at t

thisitisc-;;1the;new Notelon Condition t would have noistanding and;ConditiomC(would beientered6Similariconclusions!can;be drawnifor ethel relationship between CondL+.1onslEfand;FOIf Condition ELisithe origi_nal; Condition; entered,;there;is nothing;to;bRgained by; Required: Action F:1:and Required Action ; F. 2 ;canit; beisati sfied yith, bl ockyal ve; power; removed ;

l WithM;2;notisatisfiedtRequired:ActionG;2;wouldirequire,the plant;to;belin MODEXbut Required l Action E:4~would;have al readyj had ithe~ pl ant 31nlMODE131twoihours; earl ier! This change is consistent with traveler W0G-87.

3.4 48 A note is added to ITS 3.4.8 ACTIONS, indicating that entry into MODE 5 Loops Not Filled from HODE 5 Loops Filled is not permitted while LC0 3.4.8 is not met. The addition of this note is based on the performance of a plant specific LC0 3.0.4 matrix (see CN 1-02 LS 1 of the CTS 3/4.0 package). LC013.0:41 has beenirevisedisoithat; changes iniMODESlor;lotherlspecified conditions 11n the 0 3.4.8 1 Applicab111tyithatjare;part offafshutdownloff theiunit shallfinot;be; prevented CiIn addition;jLC0;3.0'.4!has been; revi sed [so tthatiitli sl onlyfappl icableiforlentry m:i nto ; a H0DEfot.Lothetspecified conditionsiinitheLAppl.icabili.tylin

MODES [1',T 233 Eand NTThel MODE; change trestrictions ;in (LC0 l

3;0;4;were; previouslylappl icable:11n;all;MODESGITS LC0 3;4,8 1simodified;bylr4Notelstating:MWhileithis1LC0!isjnot met,?

entrytinto; MODE 15 LoopslNot Filledifrom1HODE;5LLoops J1.lled i s Lnot; perai tted; "2 The ' transition'l from . MODE 1 51(1.oopsifil l.ed) to' MODE; 5 ;(l oopsinotifill ed); removes ;thelsteam :generatorslas a; decay,; heat removal; system:while;the R R Systemiis potentially1degradedqTherefore~,Ethe Note ensures;that,the transition l1s! precluded;if LC0:3(4.7;b1(two SGs);were! chosen (inklieufof.;the second RHRLloop)1to" ensure;decayLheat; removal capabil i.ty, pri orJ.to!drai ni ng ;the l RCS .:

3.4 49 LC0 3.4.12 "[LTOP] System", provides four different methods for pressure relief. Any of the four methods may be used.

However, Surveillance Requirement 3.4.12.5 requires testing whether or not the equipment is being credited to meet the LCO. The proposed change adds the words " required" to the Surveillance to exempt its performance if tja annioment to be tested is not beina used to meet the.IC0 4 hisichange'lis gonsistentlwith:the: CTS;whichdoesinotrequire.this j surveillancefunless: vents-are._being1used(forfoverpressure (protectionA addition, an two mwi ioi cnangcr were was maae. Tne LC0 requirement pre entation was clarifie .

t e "ctc to 5",3.4.12.0 was revised to replace r requir e to a u t with requir e to a pcrform e-

, Sinc 2 the "pciformd" no ;nclaturC iS Oppicpriate 0 3.4.12 1 herc, consistent with the CTS.The' CTS surveillance vertsjtolSR13:4.12.8? requires [thatLthe; testing;be CPSES Differencesfrom NUREG-1431 -ITS 3.4 8a 12/15/98

I CHANGE NUMBER JUSTIFICATION

. ormed;withinL 3 1: days >priorito;enteringta confit1 [

iniwhichlthe, PORVli s1requi red ).to .;be; operable?f; Iri g )

othet;yordsH theiCTS;requi resithat;thel PORVJ actuation channelj:. neet; theyequirement ;;(1. e;7 bel capablelof successfully! passing theJSR);andLthatithelSR.bel successful Performed: prior;tolentering aLcondition;in whichtthe PORV;1 required;to;be;operablePlThe STS; note:for SR:3:4;12;8f.a110w that;thelSRidoesj.not;needlto be' met (.(1..e M bejcapable.of I

being;successfully performed);unt111;'12; hours ^after; entering (a condition jn which;the;PORV;is;requiredJto;:be;operabley ;

Since;the;SR;doesLnotineed z to;beinetR.neither;does it needito bel performed;unt112sometime during thel 12:hourse M he l l icensees; agree:.that ;the;SR Edoesinot1need ;to; be; performed unt111the:12;hourslallowedj;by'the;STS"and;submitt@.a less! l restrictivelDOC;(9112fLS) land:NSHCi(LSi20)lto] describe;and i

justifyithe;changeZThe licensees;do notlagreejthatfjt;1s acceptable,tol:allowlthat;the.SR;not:be met uponientering;the app 11 cab 1]itylof.theJLC0fand i therefore retain;this CTS requirement 3 In; order (tofretain the CTS.; requirement;that the SR be.. met upon entering;.a condition in whichfthe PORVTis requiredt the;wordsiin theJITS1SRL3;4;12.8.notel.a.re. changed fromTNot; required _to;belmet;. . 7". toi"Notj required tof.be performedi.I.Q.2 This chcasc is consistcat with travel .

"" 0",0 h"X: 100.

l CPSES Differencesfrom NUREG-1431 -ITS 3.4 8b 12/15/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.6.3-23 APPLICABILITY: CP, DC .

REQUEST: DOC 7-10 LS-9 l JFD 3.6-13 CTS 4.6.1.7.2 CTS 4.6.1.7.3 CTS 4.6.1.7.4 l CTS 4.6.3.4 l STS SR 3.6.3.7 and Associated Bases I ITS SR 3.6.3.7 and Associated Bases I A Note has been added to CTS 4.6.1.7.2,4.6.1.7.3,4.6.1.7.4,4.6.3.4 and STS SR 3.6.3.7 to clarify that leakage rate testing is not required for containment purge valves with resilient seals when the penetration flow path is isolated by a leak tested blank flange. The staff position is l that the valve would still need to be leak tested since the 10 CFR 50 Appendix J requires both i isolation devices in the containment penetration to be tested except for GDC 57 penetrations. l In addition, because the CTS does not currently contain this exception, the staff considers this change to be a beyond scope of review item for this conversion, as well as a generic change to the STS.

Comment: Delete this generic change.

FLOG response (original): While we recognize that this is a generic change to the STS, the change was sent to the Westinghouse Owners Group for consideration during their June,1998 meeting. We believe the technical merits of the change should justify rapid approval by the WOG, TSTF and the NRC. This change is of sufficient value in precluding confusion, LERs, and inspection findings that should we be required to remove it from our mubmittal, an LAR would be submitted upon NRC approval of the TSTF version of the change. We believe that it would be cost effective for all concerned to retain this change within the submittal pending NRC review of this proposed TSTF.

FLOG Response (supplement): Based on the present status to the generic change process for the STS, it appears that traveler WOG-126 will not be approved by the NRC in time to support the initial license amendments for the FLOG plants. In order to facilitate the issuance of these initial license amendments, an alternate approach has been developed which relies on the CTS, plant specific information and/or the NUREG but does not rely upon the traveler. This alternate approach is hereby provided as an interim submittal to allow issuance of the initial license amendments. The changes which rely upon the traveler can be processed in subsequent license amendments following approval of the traveler by the NRC.

ATTACHED PAGES:

Attachment 12, CTS 3/4.6 - ITS 3.6, Containment Systems Encl. 2 3/4.6-9 Enct 3A 8 Enci 3B 5 End.4 1, 30 and 31 Encl. 5A 3.6-17 Encl. 5B B 3.6-28 Encl.6A 4 Encl.6B 3

1

? l l

l CONTAINMENT SYSTEMS LIMITED CONDITION FOR OPERATION (continued) i (NEW)3With one'or more penetration flow; paths withLtwo: isolation valves

' inoperable for/anyl. reason lother than.leakager isolate the affected L7 " *,

penetration flow;pathswithiny1: hour by use ofiat 1 east one' closed:and l de activated automatic >valvet closed. manual. . valve : or. blind flange; otherwise be in.. HOT: STANDBY;.withinitheinext16Lhours and:C0LDl SHUTDOWN within. the.;next(30ihours.:

i 1

SURVEILLANCE REQUIREMENTS l

t 4.6.1.7.1 Each 48-inch and 12 inch containment and hydrogen purge supply and exhaust isolation valve shall be verified? to be locked closed at least once per 7 03-ALS 31 days',7except(for;one 'purgeivalve in:aipenetration flow path while;in Action 03.6.34 l 3;6.1.7ciasia .r_esult; of.measuredileakage. ratelin . excess _ofilimits.

4.6.1.7.2 t least once per 184 days and,within 92l days;of opening'the ya]VeI;n ; _CCEl1ED TEST SASIS, the inboard and outboard isolation valves with MHs resilient material seals in each locked closed 48 inch and 12 inch containment 7 14 M and hydrogen purge supply and exhaust penetration shall be demonstrated 7 15 A OPERABLE by verifying that-the measured leakage rate.1 les: then 0.05 L,-when 0 3.6.3 19 pre: urized to P,-

getc -

2 23 l 4.6.1.7.3 t least once peri 1841 days (and within 92 days;of opening the 7 06 ts valve," each 18 inch containment pressure relief discharge isolation valve with 7 16 A resilient material seals shall be demonstrated OPERABLE by verifying that the 0 3.6.3 19 0 3.6.3 20 measured leakage rate 1: 1000 than 0.06 L, when pre:curi cd te P,.

' 7-07-If, .

1 ~ L;;k;;;; ret; t;stin;; i: r.st. req;ir.ed for..catoir. .,.r.t pr;;; .3;l; tion was volvnfaith. re;ilier.t 0;;l;V.G th;;Factretien flw pth .is isolet;d1 0 3.6.3 23 he r 1;;% t ut;d bleak fl sii;.

l N Isolation; devices;inl.high radiation areas;may be1 verified by 3,g administrative means i

t I

CPSESMark-up ofCTS 3M.6 3 N 6-9 12/15/98 l

CHANGE-HUMBER NSHC DESCRIPTION 7 10 LS 0 A acts i; odded to clarify that k kagc rate testirb i; not required for containnat purgc valves with h resilicat xcis whcn the penetration ficw path is ischted by : leak te;ted bhnk fiengc. The purpo x of -

kok testing rcquircxat is to cn;ure containnat ic;k;;c integrity during on accidcat, and thereby li;;;it accident con;cqucxe;. Isciatica of the ficw path with : ic;k tested blind fung; ecco;;;plishc; this safety function and addition;l ic:k tc; ting of the volves in the ficw path is )

7: " S t and unaccc;;;ry. Notlused #

7 11 LS-25 Not applicable to CPSES. See conversion comparison table (enclosure 38).

7!12 M Consistent;with1NUREGi1431',7 Action blis;; revised to 0 3.6.3 36 l apply;tolonly aisingle: containment: pressure; relief l

discharge; isolation; valve inoperableMPreviouslyithis 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ^ Required ;' Action;al sotappl ied ;to ;two; val ves : 1noperable r l Two valves 21.noperable;is;;now; addressed:in;aEnewfaction requirement [which_hasia211hourscompletion; time:

ThisJchangeTadds?verificationtrequirements(forJthe 0 3.6.3 35 E13 M

[ containment;purget hyd @ purge;and the containment pressure reliePjsolation val _ves][to. CTS 3;6;1g ACTIONS 1a; [b]1andicGThefrequired; actions;forlinoperable containmentiventil_a_tionj i sol ation ( val ve( s);(CVI )iare: revi sed toiveri fyithe : penetration j fl ow, path ii sol atedioncel per 31[ days;fordisolati.onidevi.ces), outs.ideicontainmentl ANDl prior to;enterjngtMODE;41from MODE .511finotfperformed within;the previous;92idays forlisolation: devices;insidelconta1_nment f l Theseirequirementsido not;existLin the CTS;;The addition;of

theseo sore stringentirequirementsiis'consistentiwith l WestinghousejSTSf(NUREG 1431)?I 1

7.(14 M A'new;requirementjhas;been addedito' perform a _ _ _ . _ _ _ _ _

i 1.eakageitest2within;92;daysiof opening theival_vesyto 0 3.6.3 19 l recognize:thatycyclingithe avalve;couldl.jntroduce 0 3.6.3 20

additional [ seal; degradation beyond;that occurring to l aLvalvelthatthas,not;been opened.;T.his new

! requi rement;j s; nore irestrictive : because.51tiisposeslaitesti ng i requirementithat;1sinotlin; current;TST J herefore Lthe l

proposedichangeladdsfa more: stringent feguirement1that11s bothiappropriateland: cons.istentiwith.NUREGi1431;ERev,I?

7515 A Consistent;with.NUREGi1431Etheirequirement.to performithelsurve111anceifrequency;onla STAGGERED 0 3.6.3 19 l TEST 1BASISfis(deleted.JThe: deletion ofcthe 0 3.6.3 20

. STAGGERED? TEST; BASIS;requirementsis1 consider.ed an Admin _istrativejchangelsince.the frequency pera valve j- does;not; change l CPSES Description of Changes to CTS 3M.6 8 12/1S/98 i

I l

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.6 Page 5 of 12 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 07-07 The leakage rate test acceptance criteria for containment No -Criteria Yes Yes Yes LG isolation valves with resilient seals is moved to the already moved from Bases. CTS.

07-08 Adds new requirement to perform a 31 day surveillance to No - CTS already No - CPSES does not Yes Yes M verify closure of the mini-purge valve. contains this have any closure requirement. restrictions on this valves.

07-09 Details regarding the valve size and isolation requirements No - CTS does not No - This detail is Yes Yes LG have been moved to the ITS bases contain this not in the current requirement. TS.

07-10 A notc i; cddcd to c1;rify that ic;kagc r;t; tc; ting u ,ct No Z doc: not Ves-NA Ves-NA Vee-NA h rcquired for coatsi -~..t purgc v;lvcs wit' rcsilicat scels contoi, this l l 0-3.6.3-13 Ei

( Lhcn thc scactr;tica ' low path is iscietcd by ; ic;k tcsted ccqut mc. cat 2' N bh 9 r---- Not'used 07-11 Removes the requirement to blank flange the containment No - That No - That Yes Yes LS-25 shutdown purge supply and exhaust isolation valves and requirement was not requirement was not revises the surveillance requirement for verification of part of CTS. part of CTS.

closed shutdown purge valves and flanges inside containment.

07-12 Action b'is' revised to apply to;only a: single. containment Noi Yes No! Nofj M pressure relief: discharge isolation. valve; inoperable.I l 0-3.6.3- l6 l Previously:this'.4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action:'also applied._to_two valves'inoperabler:Two valves; inoperable 'is'now addressed in a.new actionfrequirement which has~a'l hourLcompletion time:

07-13 This' change: adds required actions;for inoperable Yes Yes Yes Yes M containment ventilation.' isolation valve (s) (CVIL to verify lQ-3.6.3-15 l the penetration flow path isolated once per;31 days for isolation devices'outside containment AND prior < to entering MODE 4 from MODE'5l1f not^ performed within the previous 92 days'for 1 solation devices inside containment.

CPSES Conversion Comparison Table - CTS 3N.6 12/15/98

L N0 SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC) l CONTENTS l

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 Specifications) . . . . . . . . . . . . . . . . . 10 "M" More Restrictive Requirements. . . . . . . . . . . . . . . . . 12 IV. Specific No Significant Hazards Considerations "LS" LS 1................................................ 15 LS 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 3................................................ 17 LS 4................................................ 19 LS 5................................................ 21 LS-6................................................ 23 LS 7................................................ 25 LS 8........................................... . 27 --

_0 3.6.3 23 LS-9...................................... Gua .. a30 m.

LS-10........................... .........Not tsed 31a- 0 3.6.3 28 LS 11............................................... 32 LS 12............................................... 34 LS 13............................................... 36 i LS 14............................................... 38 LS 15..................... ......................... 41 l LS-16............................................... 43 ,

LS 17............................................... 45 LS 18............................................... 48 LS 19............................................... 50 LS 20..........................................Not Used i LS-21..........................................Not Used i LS 22. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 23. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i ca bl e LS 24............................... ..........Not Used )

LS 25. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e L3;26...... ,......,.....m...m....m..,..,....

,_ y yy _

. . . .. . 7.z.. ,

. . . . .m. .~. 5 2 0 3.6.3 4 l i

. V. Recurring No Significant Hazards Considerations "TR" l TR 1................................................ 5056 TR 2..................................... .......... 5458 TR 3................................................ 5658 i

CPSES No Significant Hazards Considerations - 3N.6 1 12'15/98 j 1

l

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f CPSES No SignifIcant Hazards Considerations - 3N.6 31 12/15/98

Containment Isolation Valves (At cspheric, Subatmospheric. Ice Condenser, and DuaH , p3 3.6.3 SURVEILLANCE REQUIREMENTS (continued) i SURVEILLANCE FREQUENCY

~

[ kanTf-

> 3 , b..+,3.P 7

,L,..._.._.._2,.._2 ___ 2. __m ____.2_m . m_-AL_

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g.3.6.3 23

.-...s.-,w, .

_.j y-Perform leakage rate testing for 184 days containment purge,[ hydrogen' purge and -

!B PS contaip3ent; pressure 1 relief valves with AND resilient seals. Within 92 days after opening the valve SR 3.6.3.8 Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation 18 months ,B position on an actual or simulated actuation signal.

SR 3.6.3.9 Not'used 0",3.5.3." Cycic each weight or spring icaded check 18 months 3.6 2425 valve not testabic during operation 0 3.6.3 30 through onc C0;pictc cycic of full travel, and verify cach check valvc rc:ains cicsed B-PS when the differential prcssure in the direction of ficw is m [1.2] psid and opens when the differential pressure in the AJ__a&J__ _t #1_.. J. . F1 61 _,JJ =_J u II ww b a vis vs s s yv7 yJiu uniu IJ c L A . 4.J s' rc A9 _JJ (s.vj ydiu.

SR . 3. 6. 3'.'10 Not used S",3.5.3.10 i.'erify cach [ ] inch contain; cat purge 3.6 2425

[10] mon %s- 0 3.6.3 30 valyc is b'ocked to restrict the valve from

____J__

t vywi s s i sy -.LsvJs. ren,.

l

.B PS-l (continued)

CPSESMarkup ofNUREG-1431 -ITS3.6 3.6-17 12/15/98

l Containment Isolation Valves (Atas:pheric, Sabat;;sphcric. Ice Conden;cr. Rd Dual)

B 3.6.3 BASES Additionally, this SR must be performed within 92 days after opening the valve. The 92 day Frequency was chosen recognizing that cycling the valve could introduce additional seal degradation (beyond that occurring to a valve that has not been opened). Thus, decreasing the interval (from 184 days) isla prudent measure after a valve has been opened.

I The: containment purges hydrogen purgeK and containment l

' pressure gelief? valves;are; tested in-accordance:with the Containment' Leakage

Rate: Testing: Program;JLeakagelate

acceptance, criteria; appl iesias } follows

1) The; inboard 1and 1 outboard ;i sol ation(val ves" with1 res111entimaterial;sealsLin;eachilocked; closed 483 inch containment; purge land?l2; inch hydrogen' purge; supplyfandiexhaust penetration _measuredjeakage rate]

1s 10. 05; L/ When; pressurized , to; P/!

l

2) Each!18[ inch containmentipressurel relief; discharge) isolation: valve withiresilient materia 11 seals; ,

measuredjeakage ratedsm0.06;t/when pressurized' i to;Pd

...; ",,t; j;;;;,;le'd'istis th;t 1;;%;;; ret;;tutjag i; )

i;giredf;Es;.;;itc;; p;.7,. v;1vn;.;ithJd;ili...^ :4 Gl;

?.s th;R p;i,;ti;M;n fis p;th j;julet;d by5 is%

tsted,51s%fls,,.?J SR 3.6.3.8 Automatic containment isolation valves close on a containment isolation signal to prevent leakage of radioactive material from containment following a DBA. This SR ensures that each Phase "A" automatic containment isolation valve will actuate to its isolation position on a Phase?AEIsol.ationisignal; '

each; Phase "B"Tautomaticl containment; isolation = valve;will CP 3.6 002 actuatet tojitsiisolation; position onla: containment; Phase "B" Isolationisignaly and each pressure (relief,d1schargejvalve actuates:tojits:jsolation; position;oniaContainment Ventil.ation Isolation signal. This surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. The 10 acnth Frcqucacy is based on the n= d to pcrfora this Surveillance under the conditions th;t ;pply during a plant cutage and the potential for an unplanned transient if the Surveiliscc were perfor;;d with the reacter at p;wcr. Operating experience has shown that these components usually pass this Surveillance when performed at the 18 month Frequency. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

, (continued)

CPSES Mark-up ofNUREG-1431 Bases -ITS 3.6 B 3.6-28 12/15/98

t l

l l

1 l CHANGE NUMBER JUSTIFICATION secured in their required position undcr administrativo 0 3.6.3 11 control. this changc would provide that isciation t-iee l test 4ng is not required for automat 4c contaiment isolation valves that arc locked. scaled. cr otherwisc secured in their required positica under administrative control.1Not:used 3.6 13 o clarifying note is ;dded to SR 3.5.3.7 that would allow 0 3.6.3 23 that ic;kagc rate testing for containacnt purgc valves with resilient scals is not required when the pcnctration flow I

path is isciated by a icok tested blank flangc. The blank flangc provides-the required isciation and additional testing of ths

-lves is unnecessory. Not~used <

l 3.6-14 Not applicable to CPSES. See conversion comparison table l (enclosure 6B). !

i l

3.6-15 Not applicable to CPSES. See conversion comparison table j (enclosure 6B)..

3.6-16 Not applicable to CPSES. See conversion comparison table (enclosure 68).

3.6-17 Not applicable. See conversion comparison table (enclosure 6B).

3.6-18 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

3.6 19 Not applicable to CPSES. See conversion ccmparison table (enclosure 6B).

3.6 20 Not used.

3.6 21 Not applicable to CPSES. See conversion comparison table (enclosure 6B). ;

3.6 22 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

3.6 23 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

3'.6-24 Not; applicable; to CPSES. : Seel conversionicompari so.n tabl e o.3.6.6 9 l (enclosure l 68)!.

~.

l 3.~.6 25 Based;on_ CTS,7new surveillances SR 3.6.3~12'and-3.6.3 13 0 3.6.3 30 have been:added:

l CPSES Differencesfrom NUREG-1431 - ITS 3.6 4 12/15/98

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.6 Page 3 cf 4 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.6 13 r ing notc i; ;di d to SR 3.0 3.7 that would cllow VesNA VesNA VesNA that ic;k;;c r;tc tc; ting for ce,tci cnt pursc v;hc; with 0-3.6.3 23 l rc;i'icnt ;cch is r.;t rcgircd 24-. thc pcactration fica path i; i;cleted by ; k;k tc;tcd b hnk fkagc. Not:used 3.6-14 This change would incorporate DCPP specific operability Yes No No No criteria for containment fan cooler units required to meet design functional requirements.

3.6-15 SR 3.6.6.7 would be modified to reflect Callaway plant No No No Yes specific requirements for cooling water automatic functions as well as containment cooler functions.

3.6-16 Consistent with the current TS this specification has been No No No Yes modified to reflect the Callaway Recirculation Fluid pH Control System.

3.6-17 The ACTIONS and SR's of ITS 3.6.3 are modified to reflect Yes No No l No the DCPP current TS allowance to open at one time any 2 of the 3 DBA qualified 48 inch purge supply and/or exhaust valves and 12 inch vacuum / pressure relief valve.

3.6-18 Consistent with CTS 4.6.1.7.2, a new SR is being added to No - CTS does not No - CTS does not Yes Yes perform leakage rate testing for the 36 inch containment contain 24 month have the 24 month purge valves and associated blank flanges",once per 24 requirement. frequency.

months and following each reinstallation of the blank flange.

3.6-19 Consistent with CTS 4.6.1.7.4 SR 3.6.3.7 is being revised No - DCPP does not No - Not in CTS. Yes Yes to cover the leak rate testing of the mini-purge valves with have mini-purge resilient seals after opening for testing once each 184 days system.

and within 92 days after opening the valve.

CPSES Conversion Comparison Table -ITS3.6 12/15/98

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.7.1-4 APPLICABILITY: CP, WC, CA REQUEST: CTS 3.7.1.1 Action a ITS 3.7.1 Action A.1 and A.2 and Table 3.7.1-1 DOC 01-04-LS3 JFD 3.7-01 This change is beyond the scope of a conversion because of the industry travelers referenced in this DOC (WOG-83, Rev 0 and Rev.1) that have not been approved by the NRC.

Comment: Withdraw the change or adopt the STS.

FLOG RESPONSE (original): WOG-83 has been approved by the TSTF and is designated as TSTF-235. This traveler has been submitted to the NRC and is under review.

The proposed wording in TSTF-235 was modified from WOG-83 and these modifications have been incorporated into the ITS. Comanche Peak, Wolf Creek, and Callaway continue to pursue the changes proposed by this traveler. Diablo Canyon will no longer pursue this change due to issuance of LAs 125/123 (dated May 28,1998) which revised CTS 3/4.7.1.1, Table 3.7-1, ,

" Maximum Allowabie Power Range Neutron Flux High Setpoint With inoperable Steam Line Safety Valves" and the associated Bases. See licensee-initiated number DC 3.7-008 for more details.

FLOG RESPONSE (supplement): The NRC and the Technical Specification Task Force have agreed upon the acceptable changes to be included in this traveler. Most of these changes were incorporated into the FLOG submittals in the initial RAI response as noted above. The final set of needed modifications have been incorporated as noted in the attached pages.

For Callaway, tiwse revisions supplement a supplemental response submitted in the November 25,1998 follow-up btter.

ATTACHED PAGES: 3, CTS 3/4.7 - ITS 3.7, Plant Systems Encl. 2 3/4.7-1 Encl 3A 2 Enci 38 1 End.4 22 and 23 Encl. 5A Traveler Status Sheet and 3.7-1 Encl. 5B B 3.7-2,2a,3,5 and 5a

3/4.7 PLANT SYSTEMS 1 13 A 3f4.7.1 TURBINE CYCLE 0 3.7.1 1 SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift setting'; as specified in Tabic 3.7-2; 1*^ -

APPLICABILITY: MODES 1. 2. and 3.

&CTION:**

l#LS .

l a; With onelor more'. steam generators:With'one MSSV inoperable.;and the i

l ModeratorjTemperatur_e.. Coefficient;.(HTC) zeroior negative at.all lfjLS' ., l power' levels reduce . THERMAL. POWER: level ~ to 5 87*:RTPJ '

eb. With four reactor coolant loops and associated steam generators in {

operation and with ene two:or more ,in steam line Code safety valves inoperable or any steam generato with.oneLMSSV; e inoperable and the HTC positive lat anyl power; level, operation in MODES 1. 2. and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve (s) is ,,

restored to OPERABLE status or: power is reduced.to;1ess than_or equal :

to the.Haximum Allowed Power 1isted in Table;3;7;1; Land,LWithin the(

l ours the Power Range Neutron Flux High Trip Setpoint# is I reduced per Table 3.7-1: otherwise, be in at least HOT STANDBY -

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 105 M hours. ..

0 3.7.1-5

b. The provisions of Specificatica 3.0.4 are n ' cpplicable- l (New) With oneLor.more steam generators with less1than two MSSVs 0

OPERABLETbe in HOT STANDBY within'the next'six~ hours;and. HOT SHUTDOWN withinithe following six;h_ours.

[3 l7 SURVEILLANCE REQUIREMENTS

}05m 0 3.7.1-5 4.7.1.1 No cdditional requirc; cats othcr than those rcquired by Specification 1-07-A -

4+5- Verify.each required HSSV 11ft. setpoint per Table 3.7 2lin~accordance 0-3.7.1 5 with the Inservice: Testing Program.**iFol1owing testing,11ft. settings shall be -

within. 1%. 1 04.ts Q 3.7.1 4 I

7 Separate, Condition; entry t4me-is allowed for. each MSSV.

$Onlyrequiredtobeperformedin_H00ES:1land.2; d5h -5

7Only1 required in H00E 1';

1 02 LS Q 3.7.1 2 CPSES Mark.up of CTS 3N 7 JN. 7-1 12/15M8

CHANGE NUMBER HSHC DESCRIPTION I 01-04 LS 3 The CTS allow continued operation with inoperable MSSVs if the power range neutron flux high trips are reduced. ENUREG 1431 as revised ;;dified by}

proposed JSTFi235? industry trovcicr WOC S3, Rev. 0 =d draft Rcv. 1 ,

t provided revised ACTIONS to require that: 1) the reactor power be reduced to l l compensate for the loss of pressure relief capacity to a maximum allowable l power determined in accordance with Westinghouse NSAL 94 001 and NRC l Information Notice 94 60, 2) the power range neutron flux high trip setpoint i be reduced for inoperable MSSVs if a positive moderator temperature

! coefficient (MTC) exists at the allowed percent rated thermal power in MODE j 1, and 3) the power range neutron flux high trip setpoints be l reduced to account for a control od withdrawal at partial power with more than one MSSV inoperable. Based;on 0 3.7.1-4 l

WestinghousetNuclearJSafetyLAdvisory LetterENSAL594!001Gfor pl ants 11 icensed; to; operate;atlpartial E powerzlevel s;withiaipositi vei MTCi j

changes?are;made;tojrequire;aireductionlinithe;PowertRange NeutronfluxvHigh reactoritrip;setpointiinj additionjtolaireduction kin; reactor; power;whenithe MTC11s jositive C This;1s necessary;tollimitithe primary; side? heat generat1on thatLaayloccurjduring aiRCS1heatup; event;2 With:a; positive MTCla l heatupjofsthel coolant;willjresult;inja: power; increase which requires j additionalisteam relieving 1 capacity; JChangesfare?made toirequireia i

reductionfinitheiPower1 Range Neutronf FluxiHigh:reactorjtripcsetpointdn -

addition;tola reduction 11n;the:reactorspower whenithere is,more;than;one inoperable;MSSVionlany;singleisteam generatorEForJa1 reactivity 11nsertion !

l accident;suchiasian1 uncontrolled:RCCA;bankiwithdrawallfrom aipartiallpower j I

levelithelreactor; power williincrease during,theitransi,entiuntil[a;reactot '

trip occursion10vertemperature [N!16]TorfoweriRange; Neutron Flux 411gha l Withimoreithan[one; inoperable 1MSSV on;any;steamigeneratorfthe; combined:steau j floWicapacityfof!thednoperable1MSSVslandithe; turbine:may be;insufficientMn i l some; cases (to prevent [overpressurization of;the Main Steam' System; prior;to l

reachingitheEreactoritrip;setpointifThelActionforlreducingthe;PowerLRange j Neutronflux)Highireactor] trip;setpointiis; modified:by a footnoteito l indicatelthat;r. educing'thelsetpo1_nt11s:onlyjrequiredcin:H00Efl CIniM0DESi2 and;3;the; reactor: protection system trips:;in CTS:3:3113providesl sufficient protection) In addition, the complet time for resetting the high flux tripsisrevisedfromfourhoursto236'oursandtheACTIONisrevisedtj '

specifically require an appropriate power reaucuon wmun L h a a. uns j- is a relaxation since the CTS require the high neutron flux trip setpoint to L be reduced as required within four hours for inoperable MSSVs regardless of l the HTC value. Pending ;pproval of draft Rcv.1 of WOC S3, the changes l proposed in the traveler have b=n ;;dified to retain the currcat TS requir= cat to rcsct the powcr range acutron flux-high trip setpcints boxd l cn the number of tiSS"s inoperabic to e =cximum allowable powcr detcr;ined in l accordance with calculations or = clysis to account for Westinghouse tiSAL l 04 001 and lRC Information Notice 04 50. "cwcVer, the completion ti;c of 72 l hours propo xd by WOC 03 has bc = retained and is justified b =ed on the icw I

! pecb;bility of en cvent occurring during this ti;c and the n= d to provide l

st4ficient tiac to reset the ch=nels in on orderly ==ncr without inducing

! ; transient due to hu = crror. Rctcation of the CTS requir= cat for i resetting the reactor trip sctpcints is accept:ble because this requirement

, is acre conservative th= the ACTENS specified by cither the ISTS cr WOC I

S3, = TcVised. O CPSES Description of Changes to CTS 3M. 7 2 9/2S/98

CONVERSION COMPARIS0N TABLE - CURRENT TS 3/4.7 18/16 TECHNICAL SPECIFICATION CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 01-01 Reference to Table 3.7-2 is deleted from the LCO and moved to the YES YES YES YES A SR (refer to 01-07-A).

01-02 A note is added to allow separate condition entry for each MSSV YES YES

YES YES LS-1 which allows the full four hours for each inoperable MSSV.

01-03 This CPSES specific revision relaxes the as-found MSSV lift NO: YES NO NO LS-2 tolerances from +/- It to +/- 3*. LA 108/107 issued 10/1/95 to relax setpoint (refer also to 01 LS20).

01-04 Revised ACTIONS for inoperable MSSVs: 1) specifically requires a $ see YES YES YES LS-3 power reduction within four hours and 2) requires the reactor /123 j 0-3.7.1- 4 l!

power neutron flux high trip set point to be reduced withiQ j hours.

01-05 The ACTION of the CTS which allowed an exception to TS 3.0.4 is YES YES YES YES MA deleted due to the note associated with revised SR 4.7.1.1 which 0-3.7.1-5 l allows a MODE change into MODE 3. cne of the MODES of APPLICABILITY of the LCO.

01-06 The new ACTION adds an explicit requirement to be in MODE 3 in 6 YES YES YES YES M hours and MODE 4 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if any SG loop has less than 2 MSSVs operable. This is one hour less than allowed by LCO 3.0.3.

01-07 The CTS SR is revised to specifically reference the IST Program. YES YES YES YES A The surveillance directly references Table 3.7-2 for lift points and incorporates the footnote from the table requiring the MSSV as left setpoints to be within +/- It of the nominal setpoint.

01-08 NOT USED NA NA NA NA CPSES Conversion Comparison Table- CTS 3M.7 12/15/98

IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 3 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS The CTS allow continued operation with inoperable MSSVs if the power range neutron flux high reactor trip setpoints are reduced. The amount of reduction in the trip setpoint is dependent on the total number of inoperable MSSVs per SG and is intended to compensate for the lost relief capacity (heat removal capability and thus overpressure protection) should a transient requiring their operation occur. Based on. Westinghouse Nuclear. Safety. Advisory. Letter. NSAL 94 001', for plants licensed to operate at partial power levels with a positive MTC, . changes'are'made to requirefa' reduction in the.. Power Range Neutron Flux High' reactor trip 0 3.7.1-4 setpoint in addition to a. reduction in reactor power when the MTC_is positive._ ; This is necessary to limit the primary side heat' generation that may occur'during.a.RCS.heatup event. With a' positive MTC a heatup of the coolant will result in.a power increase which requires additional' steam reliev.ing capacity.'

Changes are.made.to require a' reduction in the Power Range. Neutron Flux High. reactor trip setpoint in addition _to a. reduction in.'the reactor power when there is more than one inoperable MSSV on any' single.. steam generator. -For a reactivity insertion accident.such.as an uncontrolled RCCA~ bank withdrawal from a partial. power level the reactor power will increase _during the transient until a reactor trip occurs on Overtemperature [N 16]'or Power Range Neutron Flux-High. .With more than one inoperable MSSV on any. steam l generator..the combined. steam flow capacity of. the inoperable MSSVs and the turbine may beLinsufficient =in some cases to prevent overpressurization offthe Main. Steam System prior.to reaching the reactor trip setpoint. 'The Action.for reducing the Power Range Neutron Flux High reactor trip setpoint'is modified by a footnote to indicate that reducing the'setpoint.is only

. required in MODE 1. In MODES 2 and 3 the reactor protection system trips.in CTS 3.3.1 provides sufficient protection. In the proposed specification, the CTS requirement to reduce the power range high neutron flux reactor trip setpoint is retained; however, the time to complete resetting the trip setpoints would be changed from four t urs. - 03714 The CTS require that if the MSSV cannot be restored to an OPERABLE status within four hours, the power range high neutron flux reactor trip setpoints must be reset in the same 4-hour period. NUREG-1431 requires that the reactor power be

! reduced in four hours if the MSSV cannot be returned to an OPERABLE status; however.

HUREG 1431 would not require resetting the power range neutron flux high setpoints.

l The Westinghouse Owners Group (WOG) has proposed changes to NUREG-1431 (traveler WOC 03, as revised through draft Rev. I via TSTF-235) that: 1) propose that the completion time for resetting the power range neutron flux high trip co3.7-am setpoint [ ].to compensate for a posit' MTC or a control rod withdrawal event at partial reactor power to b 72 36 um . 2) spccif 6 Mat power level reductions be per the Westinghouse Nuclear Safety Advisory Letter. NSAL 94-01 1 and 3) deletes the Maximum Allowable % RTP for 5 MSSVs OPERABLE. licwever.

pending approval of draft Rev.1 of WOC S3, the changes proposed in the 0 3.7.1 4 traveler havc bccn modified to retain the current TS requirc=nt to reset the CPSES No Significant Ha:ards Considerations - CTS 3N. 7 22 12/15/98

l IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 3 (continued) 1 Involve a significant increase in the probability or consequences of an ,

accident previously evaluated; or l

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

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

The proposed change does not result in any hardware changes or changes to operating methodologies. This revision does not affect an accident initiator of any analyzed accident. The proposed change is based on recognition that 1) Reactor power must be limited to compensate for lost pressure relief (heat removal capability) with inoperable MSSVs, and 2) that there is a need to prevent a reactor power increase via a reduced power range neutron flux high trip setting, for transients that would cause added heat transfer to the secondary system. The proposed change also allows for an appropriate amount of time to 1) restore the MSSV to OPERABLE or reduce power and 2) reduce the power range neutron flux high reactor trip setpoints. The proba it of an accident occurring and requiring MSSV 0-3.7.1 4 l operation during the M 3 _ our comoletion Time would be very small. The time ;

extension allows the reactor trip setpoint reduction to De performed in a core deliberate manner, thereby reducing the potential for inadvertent reactor trips introduced during the setpoint reduction. However, because the accident analyses are unaffected by the proposed change, the consequences of the acc: dent analyses are not affected by this change.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

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

The proposed changes do not require physical alteration to any plant system or change the method by which any safety related system performs its function. No

, changes in plant operation result from the changes, and no new event initiators are

! introduced.

l l Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

CPSES No Significant Ha:ards Considerations - CTS 3N.7 23 12/1SP)8

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.7 TRAVELER STATUS JUSTIFICATION COMMENTS NUMBER NUMBER TSTF 36, Rev 2 Incorporated 3.7-42 Only anolicable to DCPP TSTF-51 Not Incorporated Not Applicable kequires plant specific reanalysis to establish decay time dependence for fuel handling accident.

TSTF 70, Rev 1 Not Incorporated Not Applicable. NRCEapproved I TR 3.7 005 !

TSTF not I---- -

adopted since change was not applicable.

TSTF-100 Incorporated 3.7-05 and 3.7-19 NRC approved.

TSTF 101 Incorporated 3.7-29 NRC approved. I TSTF-139,7Rev;1 Incorporated 3-7-29 Not NRC:; approved

@plicableXBases fTR-3.70]i changej TSTF 140, Rev 1 Not[ incorporated NA Not NRC approved as of traveler cutoff date.

TSTFf173 Incorporated NRC; approved? TR-3.7-00l i

JSTFil73 Incorporated NRC; approved: TR 3.7-00?

I WOG-64 Incorporated W 0 3.7.2-1 I TSTF 235 Partially 3.7-01 iletained CTS (v evil Incorporated exccpt for the 0;3.7.1-4 extension to 72

_ hours for trip Ng W90-86TSTFf2877 Incorporated 3.7 57 Notf. applicable o.3,7 10 t4 lteW1 to DCPP TR-3.7-005 WOG-98TSTFa289 Incorporated 3.7-56 0 3.7.2-

MSSVs 3.7.1 l

l f 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LC0 3.7.1 The Five MSSVs perlstean generatotjshall be OPERABLE. et spccified

&"3.7-Olc "

l in Tobic 3.7.1 1 and Table 3.7.12. "

APPLICABILITY: MODES 1. 2, and 3. 1 l

ACTIONS l

.............................N0TE -- ---- ---- -- .- -- - -.-

Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME I l

A: Onelor morejsteam A? ReduceiTHERMAL1 POWER to f 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months generators with one if873*[.RTP] 3"7 o1 MSSV!1noperable.fand 0-3*7' M 1 l

the~ Moderator I Temperature Coefficientt(MTC) !

zeroLorjnegativefat altpowerilevels3*1 ABJ One or more required AB.1 Reduce Thermal Power to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months steam.: generators;with less th'an or equal to the 3 7'01 two;or,.more MSSVs applicable Maximum O'3'7'l'4 inoperable. All_owableit RTP listed in specifiedjn Table EQB 3.7.1 1Efor.the.numbersof OPERABLE _MSSVs.

One;orimore steam generators with one 8NQ l MSSV;inoperablei:and the NTC: positive;at E P NOTEh5 =[ M f M i

anyf power;1evel3*.' Onlyl required;in. MODE 01.'_

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

n r

AB.2 .

Reduce;the' Power; Range ( 72 3 hours W

}MghiNeutronfluxiHigh reactor; trip;setpoint.to l

l less;than or:equalfto the (Q3.7.1-4 Maximum' Allowable %:RTP specified;inl Table:3.7.15 lifor;theinumber;of OPERABLE MSSVs. 1 i

CPSESMark-up ofNUREG-1431 -ITS 3.7 3. 7-1 11/15/98

MSSVs B 3.7.1 BASES presented in the FSAR, Section 15;2 (Ref. 3). Of these, the full power turbine trip without steam dump is typicallyethe limiting A00. This event also terminates normal feedwater flow to the steam generators.

The safety;ana.lysisJdemonstratesLthetitheJtransient response for turbine trip occurri.ng;frosifu1U power without a direct 0 3.7.1 4 reactor trip presents no hazard to the integrity of the RCS or the Main Steam System. If a mini;;; r=ctivity fccdbeck CP 3.7 15 is assu;cd. the reactor is trippcd on high pressuricar prasure. In this a sc. the pressuriccr safety volvcs open,

=d "CS picssure rc;; ins below 110t of the dcsign value. The MSSV3 also span to limit th; secondary stc= pressure.

If ;;;axi;;;;; reactivity feedteck is assu;cd, the reactor is trippcd on overt--erature oT (!E; Jt:n,...g;ter; teMcQ -;.1;W, 1;W. The dcparture fre; nuclaste boiling retic incr= scs t!,rcugheut the tr =;icat, =d ncycr drops bcicw its initial value. "ressurizar relief volvcs =d "SS','s are activated and prevcat cvcipicssurization in the primary and sacandary systems.

7 ne xturbineltrip;;;is; performed assuming t no_pr1 mary system pressurel Ps contro1Ebut;creditingreactor;tripion:high;pressurizeripressurej j toperation of the:pressurizerisafetv'valvesd This analys u demonstrates 2m 6 magnwy n;yjs ma.intafned bylshowing;that the I naximum;RCS7pressurefldoesinot; exceed 2110t;ofJthe.1 design? pressure l ;

A11Xcases!analyzedIdemonstrateithatithe MSSVslmaintain_ Main Steam System integrftylby;1imiting;theimaximum steam [ pressure to.;.lfss than ; 110*!of;theTsteam; generator; design : pr essure g Inladditionlto;thel decreased .heatf removallevents,Treactivity insertion events;may'alsolchallen ' relieving capacity 0 3.7.1 4 offthe..MSSVs 5The uncontrol.1ed;r ter control; assembly (RCCA) bank withdraua12at; power ev 11s character 12ea oy an 3 increase 11n; core l power;and: steam generation: ' ntil reactor 3 PS l trip; occurs;when,either4theOvertemperature si or Power Range '

NeutronfluxtHigh[setpointli.s; reached ESteam; oW to'the' turbine will;not increase;from;1t.sMnitialf valuelfor thislevenQ. he increased [heatftransfer;tolthe! secondary;sideLeausesfanJncrease intsteam' pressure Jnd;may result 11n opening;of,.thefMSSVs prior to reactot ttipH assuming;noJcredittforloperation rof n a atmospheric l gg or;condenserf steam;dumpTvalves1SThe FSC;i; [15.Qann.y I analysis;of the1RCCAlbank 1 withdrawal;at; power s event toea range of;initiallcore'powetlevelsidemonstrateslthat the MSSVsLare capable:ofl preventing:secondaryisideloverpressurization' for this A,00lL (Continued)

CPSES Markup ofNUREG-1431 Bases -ITS 3.7 B 3.7 2 12/1S/98

! MSSVs B 3.7.1 i BASES l

The FSARl safety; analyses; discussed:above: assume that.all? of the;MSSVs; forfeachl steam, generator are OPERABLE.~If there 0-3.7.14 are; inoperable 1MSSV(s)l;1tlis necessary to111mitithe primary s

CP 3.7 15 system powerfduring' steady, state. operation and:A00s;to;a l value thatidoes;not;l result. in, exceeding;the combined isteam fl ow ; capacity;of;the : turbine r (i f ' avail able) land ; the: remaining OPERABLE 1 MSSVsCThe;requiredfl.imitationlon primary, system: power l pecessary;to preventisecondaryfsystes.overpressurization'may be amme determined by system transient'analyjgrtnenserv;tively ;rri;53J-("Ti by : si;ple ha t bel ac; ::lcul: tion.lIn some: circumstances 1t 1

is;necessary to; limit the.. primary side; heat generation thatican

, beiachievedLduringlan A00 by feducing the:setpoint;of the. Power l Range Neutron 1Fl ux-Hi gh: reactor; tri p_ function . Forf exampl e, ; i f

[ moreLthan'one MSSV i on a_singl_e: steam generator is; inoperable,ian uncontrolled RCCA' bank; withdrawal;at powerievent; occurring fromla partiallpower;1evellmay; result 11n 'aniincreasetin reactor' power that exceeds 1the:ccab1_nedl steam fica capacity;of the turbine and;the: remaining;0PERABLE;MSSVs.?ThusRfor multiple inoperable'MSSVs on the1same~ steam aenerator{it is c -u ~j 0 3.7.1 4 to; prevent GEEEDthis powerQncreas'y uy wwermv.. se l Power Range Neutron Flux High,setpoint to an. appropriate

! val ue. : When;the. Moderator l Temperature" Coef fi cient L (MTC) ; i s l positiveUthe reactor power may;increasef above'thefinitial tvalue during'an RCS;heatup event (e.g; turbine trip).1Thus',1 for,any l number of-l inoperable MSSVs:it;is necessary, to reduce the, trip setpoint 1ffa: positive .HTC may'existiat. partial power conditions; unless11tJistderonstrated by analysis that a specified reactor power; reduction alonelis sufficientz.to: prevent'overpressuriution of the:steamisystem. The MSSVs are assumed to have two one active and onc passive failure modes. The active failure modes are spurious is' an inadver. tent opening and failure to reclose once opened. Thc possivc failurc modc is Failure to open upon demand is not assumed-(Ref. 3).

l The MSSVs satisfy Criterion 3 of the NRC Policy Stat = cat 10CFR50.36(c)(2)(1_1) .

l l

LC0 The accident analysis requires feue that.five MSSVs per steam

generator be;0PERABLE'to provide overpressure protection for I design basis transients occurring at 102% RTP. An tiSSV will I ts considered inoperabic if it fails to open on dc ;nd when 0 3.7.1 4 th;lpic;en pres =rc'i; within the lift act prawre tolerance. The LC0 requires that five MSSVs per steam (Continued) l l

i CPSES Markup ofNUREG-lul Bases - ITS 3. 7 B 3. 7-2a 12/15/98

MSSVs i

(

B 3.7.1 i

i BASES OPERABILITY of the MSSVs is determined by periodic surveillance i testing in accordance with the Inservice Testing Program.

The lift ;cttings, according to Tabic 3.7.1-2 in the 0 3.7.1 4 accompanying LCO, coricspond to ambient condition; cf the valve at acminal operating tcaperaturc and pressure.

This LC0 provides assurance that the MSSVs will perform their designed safety functions to mitigate the consequences of accidents that could result in a challenge to the RCPB or Main Steam: System; integrity.

APPLICABILITY In ."00E 1 abov 40 RTP, the numbcr of "SSV; per steam ,

scacrator rcquired to bc OPERASLE cast bc according to 0 3.7.1 4 Table 3.7.1 1 in the accompanying LCO. Sclow 40 RTP in MODES 1, 2, and 3. only two five MSSVs per steam generator l are required to be OPERABLE to prevent. Mein _ Steam System ;

overpressurization.

In MODES 4 and 5, there are no credible transients requiring the MSSVs. The steam generators are not normally used for heat removal in MODES 5 and 6, and thus cannot be overpressurized:

there is no requirement for the MSSVs to be OPERABLE in these MODES.

ACTIONS The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each MSSV.

Ad I l

1 With one or more MSSVs inoperable, action must be taken I reducc powcr so that the available MSSV relieving capacity 0-3.7.1 4 meets the Reference 2 overpressure. protection requirements, for the applicabic "iER"AL POWER as ;pccificd in .Toble CP 3.7-15 0.7.1 1.

~

T peration with less than al' five MSSVs OPERABLE for each steam generator is permissible, if THERMAL POWER is E03.7.14

-c-rtionallslimitedtothereliefcapacityoftheremaining MSSVs. Inis is accomplished by restricting THERMAL POWER so that l the energy transfer to the most limiting steam generator is not

greater than the available relief capacity in that steam l generator. For cxampic if onc "SSV is inoperabic in onc ;tcam generetor, the rclici capacity of that stca; generator is reduced by-CPSES Markup ofNUREG-1431 Bases -ITS 3. 7 B 3.7-3 JN15M l

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

MSSVs l B 3.7.1 BASES l

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' In1theicasefoflonlyia/singletinoperableJMSSVionjone;ot more' steam l generators;whenithe:Moderatorgesperature... Coefficient 11sa not positivelaireactorlpowerireduction1alone:1sisufficientitoflisit i prjaarysside. heat generationisuch that;overpressurizationLof;the l l secondary;sidejsjprecludedifotlany RCS heatup;eventO i Furthermore,1forithisicaseithereLis; sufficient;totalisteam flow I l capacity lprovidedfbytthelturbineiand: remaining 0PERABLE MSSVsIto l l Preclude;overpressurizationiin theleventlofjantincreased' reactor poweriduelto;reactivityjinsertion;)such asM nithe:eventsof an uncontrolled'RCCA bank withdrawaE at!powerCThereforeA Requi, red.

Action A:11requiresianlapproptiateireductionjin reactor; power l within1hourst !

l Themaximus3HERMAL1POWERicorresponding;toithe'heatjremoval. I PS can_acity of the remainino OPERABLEL.MSSVs11sidetermined;via ;a ]

6vetransient"analvskwith an; appropriate; allowance [for abrimetric powetuncertaintyfandlinstrumentluncertainties?

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B'.1 and B'.2 Inithe Leasej of multiple;inoperabl t e' .MSSVsf on one ; or, more . steam generatorsZ withTaireactor'powet reduction lalonetthere~may be insufficientitotalisteamiflow1 capacity;provided:by the turbine and remaini.ng; OPERABLE;MSSVs;to.: preclude.ioverpressurization in the" event;of an.} increased;reacton powerEdue toireactivity insertion [such"assin thelevent;ofian; uncontrolled.RCCAlbank withdrawalf at[ power!; Furthermore,Efor;aisingleylnoperable _MSSV on one orfmorejsteam. generators lwhen;the ModeratorjTemperature

[ (Continud) l CPSES Markup ofNUREG-1431 Bases -ITS 3.7 B 3.7-S 12/IS/98 l-l

MSSVs B 3.7.1 BASES Coe.fficientiisjpositivelthe; reactor / power,.-mayiincrease a_sla resu.l tf off an : RCS1heatupfevent Lsuchithat l flow : capacity:off the g,3,7,1,4 remainingLOPERABLE MSSVs:is? insufficient f reiere, y, I,

. . _ , .. , . . . . . . , ...... .. r .,... ,. . ...

.rr jrtG?Rti; . j I;; tee r;'J- _;jthf. DC ;,J,%;ir-A;ti;. % 2L.r uifi ; tMtJ.M I L E f,G R ".L ti n J A "i #,

T;Gter t.jk ~^re j-tik 75d.s.;d eitM J0 M; ;.2ThelhouC Completion 1 Time;foriRequi red; Action,LB;1li siconsi stent) with: A' 1M .

An:additiona]L32ihoursiis.Lallowedlin: RequiredLActioniB;2;to reduce;thelsetpoints "JThe1CompletioniTime;ofJ6Stoursiis based onia1 reasonable 1timelto correctitheLMSSVJjnoperabilityathe time requiredito performithelpower; reduction?foperatingiexperience;in resettingial]f channels lofl protective:functionRand onithellow probability;ofithe: occurrence off a transient 1that;could resultrin steam generator, overpressure;during this? period Q The maximusiTHERNAL1 POWER; corresponding to the;heatJremoval canacitv"of the' remaining.0PERABLE MSSVslis; determined via.a PS stem translentianalysThwith;anlappropr,1 ate; allowance for /

Nucleat m m. % .g.ation_SystesLtrip;channet uncertainties] /

Required:Acton;B;211s modified by a Note;5. indicating lthatithe s

Power Range: Neutron Flux High; reactor (triplsetpointfreduction 1s only. required 11n MODE %In MODEST 2landj3?the reactorf protection systemLtripsjspecifiedljn LC0 313,1CReactor: Trip . System Instrumentation;iprovidersufficient protection?

The: allowed Comp 1etion Times!are reasonable based;on operating experience tolaccomplish:the Required'; Actions;jn an; orderly manner 1without. challenging unit' systems:

CB.1 and CB.2 If the Required: Actions;areLnot; completed "SSVs corr.ct M CP 3.7 15

restcrcd to 0"E"J "LE, status within the associated Completion 0 3.7.1 4 Time, or if one or more steam generators have 2;,4. inoperable itss thr. t'ac "SSVs OPERABEE, the unit must be placed in a MODE in which the LC0 does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

CPSESMarkup ofNUREG-1431 Bases -ITS 3.7 B 3,7-Sa 12/15/98

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

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORM.ATION NO: O 3.7.10-14 APPLICABILITY: CP, WC, CA REQUEST: CTS 3.7.6 Action b, Modes 1,2,3 & 4; Action c, Modes 5 & 6 ITS 3.7.10 Action B, C, D, E, and F DOC 10-20-LS39 JFD 3.7-57 These changes are beyond the scope of a conversion because the industry traveler referenced in this DOC (WOG-86) has not been approved by the NRC.

l. In addition, for CPSES, the Action D condition statement appears to be contradictory because l with two inoperable trains, it is not clear how any pressurization occurs.

Comment: Withdraw the changes or adopt the S FS.

FLOG RESPONSE (original): WOG-86 has been approved by the TSTF and is designated as TSTF-287. This traveler has been submitted to the NRC and is under review.

The proposed wording in TSTF-287 was modified from WOG-86, and these modifications have been incorporated into the ITS. This results in changes only to the Bases for the Required Actions for ITS 3.7.10. The FLOG continues to pursue the changes proposed by this traveler.

This TSTF is not applicable to DCPP but is applicable to CPSES, For CPSES, Condition D refers to two CREFS trains inoperable due to inocerable CR boundarv. The CR boundary inoperablity is usually the result of boundary degradation such that with either CREFS trains running the system is unable to maintain a pressurization of 2.125 inches water gauge at 800 cfm. Action D merely requires repair of the degraded pressure boundary.

FLOG Response (supplement): The NRC and the Technical Specification fask Force have agreed upon the acceptable changes to be included in this traveler. Most of these changes were incorporated into the FLOG submittals in the initial RAI response as noted above. The final set of needed modifications have been incorporated as noted in the attached pages.

ATTACHED PAGES:

Attachment 13, CTS 3/4.7 - ITS 3.7, Plant Systems EnctSA Traveler Status Sheet,3.7-23 and 3.7-24a

.EncI5B B 3.7-56a l

i i

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

INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.7

! TRAVELER STATUS JUSTlFICATION COMMENTS NUMBER NUMBER TSTF 36, Rev 2 Incorporated 3.7 42 Only upplicable to DCPP I

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

l TSTF 70, Rev 1 Not Incorporated Not Applicable. NRCRapproved TR 3.7 00 i l TSTF not adopted since change was not l applicable.

TSTF-100 Incorporated 3.7 05 and 3.7-19 NRC approved.

TSTF 101 Incorporated 3.7 29 NRC approved.

TSTF 139,lRev:1 Incorporated 3 + 29 Not NRC: approved TR 3.7-00 5l l Applicable ? Bases changej TSTF 140, Rev 1 Not i. incorporated NA Not NRC approved as of traveler cutoff date.

TSTFf173 Incorporated NRCfapproved.' TR.3.7 00L TSTFil7,4 Incorporated NRC" approved; 7a.3,7 00 WOG-64 Incorporated W l03.7.2-1 W9G-&3 TSTF;235 i'artially 3.7 01 ilctained CTS Incorporated exeept-fee-the 0 3.7.1-4 cxten; ion to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for trip reset--

W9G-86TSTF 287! Incorporated 3.7-57 Notl applicable o.3,7 10- L4 l (M to;DCPP TR-3.7-00 i 3

W9G-98TSTF5289 Incorporated 3.7 56 a.3.7.2-l l

l l

l CREFS

)

3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Filtration / Pressurization System (CREFS)

PS LC0 3.7.10 Two CREFS trains shall be OPERABLE.

.3 9 p. . :. . =. . . . . .;.y . . . . z.y . (. . . q. N0TE = = - :

= - : .- -' , - "- '- - - a '- - ~ -~

The'Co.ntrol Room, boundary maybelopened ;. intermittently under ' administrative '

Controls 3.7 57

y. ."; .' . . . ; .;;; .v. . '. . . ; ; . ;;. . . . ; ; .J. . .- . ; . . . . . . . . . . . . . . . . . . . ... c . . . . . . r. j . . . . ; . . . . . . Q 3.7.10 14 APPLICABILITY: MODES 1, 2, 3. 4, 5,"6; B-PS;-

During movement of irradiated fuel assemblies During CORE ALTERATIONS ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i

A. One CREFS train A.1 Restore CREFS train to inoperable. OPERABLE status. 7 days BBl Two' CREFS:: Trains BB.1 Restore control" room 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable du_e' to boundary;to OPERABLE 3,7 57 inoperablefontrol Room) status,; capability;to

_ 0 3.7.10 14 boundaryJ n MODES 1, 2, ;;;ainteir._. prc;suFC in Q, Land 4; the Contr;' Ree;;;f.eithin w- -

CB. Required Action and CB.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or.B AND 3.7 57 not met in MODE 1, 2, 3, 0 3.7.10 14 or 4. CB.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months i

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l CPSES Mark.up ofNUREG-1431. ITS 3.7 3.7-23 12/1S/98

CREFS 3.7.10 l

1 CONDITION REQUIRED ACTION COMPLETION TIME

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i Two CREFS trains EOG;1 Suspend _, CORE .Immediately

'B;PS g ,

inoperable ';Cr n ; ; ALTERATIONS?

m.__. .m__ ,,__2,,__. m-l r - - u - . -- ~ . -u ,

jn.M00Ei5;orJ67oc [AtB during movement of irradiated fuel assemblies, or durirg E06.2 Suspend movement of Immediately irradiated fuel 00"_E ALTE"ATIL"E fee

,. _ _. _.-_ . ' ' - . . . ' ' . . . assemblies.

I N

EEH. Two CREFS trains FEli.1 Enter LC0 3.0.3. Immediately inoperable in 3.7 57 H0DE 1, 2, 3, or 4 0-3.7.10 14 for; reasons lothet than1 Condition;B;

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l CPSES Mark-up ofNUREG-1431 -ITS 3.7 B 3.7-24a 12/1S/98

CREFS B.3.7.10 BASES (continued)

A CREFS train is OPERABLE when.bothLfiltration. units;(ils.'. the emergency pressurization' unit l.(EPU)"and' emergency, filtration unit (EFU)) are.0PERABLE.LA filtration unit:is OPERABLEjwhen the associated:

a. Fan is OPERABLE:

b. HEPA filters and charcoal adsorbers are not excessively restricting flow, and are capable of performing their filtration functions (the.EFU~must meet Ventilation Filter CP 3.7 014 Testing; Program;(VFTP) requirements: the:EPU must meet VFTP requirementsT;except'for filtration' requirements): and

c. Heaters (EPU_ only), demister (EPU only), ductwork, valves, and dampers are OPERABLE, and air circulation can be maintained.

In addition, the control room boundary must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors.

e LC0jisimodified byia Note; allowing the Control:R boundary .to' be ' opened Lintermittently;underLadministrative l o.3.7 10 14 controls.JForientry;and'. exit.throughLdoors;the;administrativ control of;thefope.ni.ng;is;-performed .byf the; person (s) entering;or : exiting. the area. iForiother; openings 1these1 controls consist'ofsstationing=a-dedicated: individual at the opening who i isiin continuous: communication with the~ control. room ~ This individual wil.1 have;a. method,to rapidly;close the opening when needed for control room isolation.

l CPSESMarkup ofNUREG-1431 Bases -ITS3.7 B 3. 7-56a 12/1588

ADDITIONAL INFORMATION COVER SHEET I

ADDITIONAL INFORMATION NO: Q 3.9-7 APPLICABILITY: CA, CP, DC, WC l REQUEST: CTS 3.9.4 c 1) Footnote ** (Comanche Peak)

CTS 3.9.4 c 1) Footnote ** and 4.9.4.1 Footnote ** (Callaway) i CTS 3.9.4.c and 4.9.4 Footnote * (Diablo Canyon)

CTS 3.9.4.c Footnote ** and 4.9.4 Footnote ** (Wolf Creek)

DOC 4-10-LS-20 ITS 3.9.4 NOTE and SR 3.9.4.1 JFD 3.9-11 In DOC 4-10-LS-20 and JFD 3.9-11, it was stated that this change is consistent with traveler WOG-76.

Comment: Revise DOC by providing the TSTF number associated with WOG-76 and when the associated TSTF was approved. If WOG-76 has not made it to the TSTF process or the TSTF has not yet been approved, remove this item from the submittal since the inclusion of this footnote will be pending on the approval of the TSTF change.

FLOG Response (original): WOG-76 was initiated by the WOG Mini-Group in October 1996.

j While we recognize that this is a generic change to the STS, the change was approved by the

Westinghouse Owners Group over 18 months ago and was expected to have been approved by this time. We expect the TSTF committee to complete their review of WOG-76 in the very near future. We believe the technical merits of the change are consistent with traveler TSTF-l 68, which should justify rapid approval by the NRC. This traveler is of sufficient value in l

precluding confusion, LERs, and inspection findings that should we be required to remove it from our submittal, an LAR would be submitted upon NRC approval of the TSTF. We believe that it would be cost effective for all concemed to retain this change within the submittal pending NRC review of the proposed traveler.

Additional information supporting this DOC is in NSHC LS-8 in Enclosure 4. DOC 9-03-LS-8 is revised to include the following information:

l "A note is added to LCO 3.9.4.c and the 7-day SR to state that containment penetrations that provide direct access from the containment atmosphere to the outside atmosphere may be open under administrative controls. The note would allow these penetrations to be unisolated during CORE ALTERATIONS and movement of irradiated I fuel assemblies within containment provided that specified administrative controls were employed. The proposed Note is acceptable based on administrative controls that t consist of written procedures that require designated personnel having knowledge of the open status of the valves in question and specified persons designated and readily available to isolate the open penetration in the event of a fuel handling accident. These administrative controls provide protection equivalent to that afforded by the i administrative controls used to establish containment closure for a containment j personnel airlock. The NRC staff has allowed changes to the requirements for airlocks that allow both doors of an airlock to be open during CORE ALTERATIONS and during movement of irradiated fuel inside containment provided that administrative controls are in place to quickly close one door and establish containment closure.

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equivalent, will perform their required containment closure function and will serve to limit the consequences of a fuel handling accident as described in the Safety Analysis Report such that the results of the analyses in the Safety Analysis Report remain bounding. In considering the consequences of a design basis fuel handling accident inside containment, the assumptions in the analysis take no credit for the containment as a barrier to prevent the postulated release of radioactivity. For events that would occur during CORE ALTERATIONS or movement of irradiated fuel assemblies, containment closure is considered a defense-in-depth boundary to prevent uncontrolled release of radioactivity."

For DCPP, a preliminary dose calculation has been completed in accordance with the Reviewer's Note added by traveler WOG-76. This calculation shows sufficient time for closure with acceptable dose consequences.

FLOG Response (supplement): The proposed changes to CTS 3.9.4 and ITS 3.9.4 were based on traveler WOG-76. WOG-76 has recently been designated TSTF-312 and transmitted to the NRC in December 1998. Based on the present status of the generic change process for the STS, it appears that traveler TSTF-312 will not be approved by the NRC in time to support the initiallicense amendments for the FLOG plants. In order to facilitate the issuance of these initial licens9 amendments, an attemate approach has been developed which relies on the CTS, plant-specific information, and/or the NUREG but does not rely upon the traveler. This alternato approach is hereby provided as an interim submittal to allow issuance of the initial license amendments. The changes which rely upon the traveler can be processed in subsequent license amendments following approval of the traveler by the NRC.

The CTS and ITS have been modified to remove TSTF-312, which will result in DOC 4-10-LS-20 and JFD 3.9-11 as being "Not Used." For Wolf Creek, a Note to LCO 3.9.4 will be maintained to adopt the CTS wording approved by Amendment No.107, dated July 11,1997, that allowed penetrations P-63 and P-98 to be opened under administrative controls.

Additionally, SR 3.9.4.1 has been revised to except containment penetration P-63 and P-98 if they are open under administrative controls to comply with the I'l S format and rules or usage (e.g. SR 3.6.3.3 and associated Bases). New JFD 3.9-16 has been initiated to address the Wolf Creek specific changes to adopt CTS.

ATTACHED PAGES:

Attachment No.13, CTS 3/4.9 - ITS 3.9, Refueling Operations Enci. 2 3/4 9-5 Encl.3A 5 and Sa Encl. 3B 3 Encl. 4 1,37,38 and 39 Encl. SA Traveler Status Sheet,3.9-5 and 3.9-6 Encl. 5B B 3.9-15, B 3.9-16 and B 3.9-17 Encl.6A 2 l Encl.6B 2 l

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+ . _ . - - _ . . - . . . . . . ,-uw., .a. x . . - --

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I REFUELING OPERATIONS l 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITED CONDITION FOR OPERATION l

l 3.9.4 The containment building penetrations shall be in the following status:

l l a. The equipment hatch closed and held in place by a minimum of four l bolts,

b. A minimum of one door in the emergency airlock is closed, and one door in the personnel airlock is capable of being closed *, and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:

1) Closed by isolation valve, blind flange, er manual valve,sor . m LS' equivale_n or

2) Be capable of being closed by an OPERABLE automatic

~

N i Q 3.9 7 containment ventilation isolation valve.

t.PPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the ^ "' '

containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

Administrativc controls shall ensurc that:

1) Appropriate personnel arc aware that both personncl airlock doors ; 4-07-LG are open.

2) A spcGifiCd individual (s) is designated and available to Cicsc th; airlock fc110 wing a required evacuation of contain: cat. and

3) Any obstruction (s) (c.g., cabics and hoses) that could prcycat closurc of an open airlock bc capable of being quickly removed, flW paths that picVide ' direct accCs_s 'fice thC Containr&;;nt i

l ["; nitration ht esph;re to the cutsidc;at;;spkr; may M unisclated und;r Administrative Contr0ls.

f3%

CPSESMarkup of CTS 3/4.9 .w. m 12/15/98 i

CHANGE NUMBER NSHC DESCRIPTION 1

l CVI signal would be generated by the containment gaseous monitoring instrumentation and then verifying the valve closure capability by remote manual closure from the control room. The combination of these two activities completely tested the automatic closure circuitry of these valves. The NUREG 1431 surveillance requirement performs the same function. The details of how the test is performed is not required to be in the TS.

1 4 07 LG The specific administrative controls used to assure I personnel airlock closure capability would be moved from the LC0 to the Bases. This change moves details that are not required to be in the TS to protect the health and safety of the public while retaining the basic limiting conditions for operation.

1 4 08 LG Not applicable to CPSES. See conversion comparison table (enclosure 3B).

4 09 LS-14 LC0 3.9.4 would be modified to permit an approved functional equivalent of a valve or blind flange to isolate containment penetrations. This change is consistent with NUREG-1431.

w 4 10 L" 20 Adds a fcctacte stating that pen-tratica flow paths tha]t providc dir ct access from the containmcat atmosphere-to the cutside atmosphcrc may bc unisciated under

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CPSES Description of Changes to CTS 3N.9 5 12MS/98

1 CHANGE NUMBER NSHC DESCRIPTION ______

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g This char,,,c is consistcat with travelcr '.100 75 and with

, previcaly approved ed;;;inistrative controls for p;rsen ,cl j cir locks. N.ot_"used ,

j g --_

j 5 01 R This change relocates the current TS section dealing with 'j

maintaining direct communication between the control room !

i and the refueling station to a licensee controlled i document as part of the conversion of the current

Technical Specification to the format and expanded Bases i 0 3.9 9

of the improved Standard Technical Specifications. The {

! speci ficationf requi resf communication l between l the: control, i roomland3 thelrefueling stationitoiensure3that anyfabnormal change s inithelfacilityistatus oricore feactivityLobserved on.;thelcontroproomlinstrumentation;can;be, communicated to the; refueling ! station l personnel :during : core; al terations !

Thisiproposed;TS! revision ~relocatesirequirementshwhich'do notimeet;thex TSicriterial n'10C.FR50.36(c)(2)(ii)? i to documents with; established contro11 programs:;This regulation addresses,thel scope [andlpurposejofiTS. ;In doingiso',litisets;forth;af specificiset;offobjective criterialfor; determining;whichiregulatory;requirementsiand operati.ng irestrj etions ishoul d '.be ;i ncl uded ; i ni thej TS'. .

Rel ocati_onlof;these; requi rementsiall ows ; the;TSi tolbe reserved ;only;forithoseicondi tions torfl imitations ' upon reactorioperationdwhichlareinecessaryztolobviate;the possibility otanfabnormallsituation orieventigiving; rise tof anjimmediate: threat;tojthe public1 health land(safety thereby; focusing lthe scope;of the;TS7An evaluation.of:the applicabilityiof'theseicriterialto this! specification;is Provided;infAttachment121:

To ensure an appropriate;1evel;of2 controlEthese requirements w1]l:be relocated to:1)fdocumentsLthat are subjectito;thelpro_ visions loffl0;CFR 50'59;T2)rother .

CPSES Description of Changes to CTS 3N.9 Sa 12/IS/98

CONVERSION COMPARISON TABLE - CURRENT TS 3/4.9 Page 3 of 8 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY-4-03 The frequency of verifying that [ containment ventilation Yes Yes Yes Yes LS-5 isolation] occurs is changed from 7 days to 18 months.

4-04 Revised Surveillance requirement to allow for increased Yes Yes Yes Yes TR-1 flexibility in using an actual or simulated actuation signal.

Identification of the specific actuation signal is moved to the Bases.

4-05 Moves SR to verify the trip set point concentration value for No - not in CTS No not in CTS No - not in CTS Yes - Moved to FSAR '

LG the Containment Purge Monitors is reset during CORE ,

ALTERATIONS or other movement of irradiated fuel in I containment.

4-06 The requirement to verify the capability to close the No - not in CTS Yes No - not in CTS No - not in CTS LS-23 containment ventilation isolation valves from the control room would be deleted.

4-07 The specific administrative controls used to assure personnel No - not in CTS Yes No - Amendment 95 Yes LG airlock closure capability would be moved from the LCO to the did not put admin Bases. controls in LCO.

I 4 08 Moves the references to Heavy Loads in the Applicability Yes No - not in CTS No - not in CTS No - not in CTS LG and Action sections of CTS 3.9.4 (Containment Penetrations) to the Heavy Loads Program.

4-09 LCO 3.9.4 would be modified to permit an approved functional Yes Yes No - already in CTS Yes [

LS-14 equivalent of a valve or blind flange to isolate containment (Amendment 74) l penetratio3 4-10 /ootnctc

, ma f stating th;t p;nctrati;n ficw path; that VesNA VesNA YesNA VesNA

p. eeidc dircct occc;; 'ro ; thc cu.ici. .m st;c;phcrc to thc l 0-3.9-7 l!

cutsidc ct ;c;phc. c : y bc uni ~.- ..~s. _.i-i;trativ; t. *N;. Not used 5-01 This change relocates the current TS section dealing with Yes -See attachment Yes - relocated to No - relocated per No - relocated per R maintaining direct communication between the control room and 21. page 19. TRM Amendment 89 Amendment 103 the refueling station.

CPSES Conversion Comparison Table - CTS 3/4.9 12/1S/98 v

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N0 SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC)

CONTENTS f

I. O rga n i z a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 II. Description of NSHC Evaluations........................................ 3 III. Generic No Significant Hazards Consideration "A" Admini strati ve Changes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 "R" Relocated Technical Specifications. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 "LG" - Less Restrictive (Moving Information Out of the Techni cal Speci fi cations) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 "M" - More Restrictive Requi rements. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

IV. Specific No Significant Hazards Consideration "LS" LS 1.................................................................... 15 LS 2.................................................................... 17 LS 3.................................................................... 19 LS 4.................................................................... 22 LS 5........ ........................................................... 24 LS 6.................................................................... 26 LS 7 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c a bl e LS 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c a bl e LS 9 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c abl e LS 10................................................................... 28 LS - 11. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i c abl e LS 12 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i c abl e LS 13 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c a bl e LS 14................................................................... 30 LS 15 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i ca bl e LS 16 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c a bl e LS 17................................................................Not used LS 18................................... ........................... ... 32 LS 19............................................................. . .

-~

.34 -

LS 2 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . dot u sed 3 6 0-3.9 7 LS 21................................................................. ..J9 _

LS-22.................................................. ................ 41 LS-23................................................................... 43 LS 24 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N o t a ppl i c a bl e l LS - 2 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N o t a ppl i c abl e l

LS - 26 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot a ppl i c a bl e i,

V. Recurring No Significant Hazards Considerations "TR" TR 1.................................................................... 45 CPSES No Significant Ha:ards Consideration - CTS 3N.9 1 12/15/98 l

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CPSES No Significant Ha:ards Consideration - CTS 3N.9 37 1MS/98

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.- .-__ _. L.J____L .J1-i. J__- TL. .... .c J_ J J a m a a . .. --L_1. J. LLJ.

un s vysi s hvi s b u i s ems u s b u si svun uvvi, ssru uaw vs u% m u s s s a bs u b a ww wvisbavsa sus bli s a

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--_..J_. Lu. -L.J_- L. _Ja.J-

- . . . . _ - u . . . ,u Jo. _i,. rua. J.

s myu s s w bs N wus s bu s i mms s b bv t..u s . u b u s s i u -es waaus s uvu s

.. susIJ Jbu s iu s .-_-J. se

.- 1J- L1- J.._J_- 1 _L . L . . L J _. . . -_ - c..12-- .J uyynavuuis uut :iry yiuss6 as s%s buvvi s s vs a wauuaissy evi . .Lsw_a ennr-s vvim nw as3 venATvruic Ls v s a vsia ussu

__..____L _s J _.JJ.L J s. . 1 ..._L1J-. J- LL. - L.J____L - - . . . y mv v www s i b vs aaauuaubEu auwa uJewmuasLa ssa bsis hvii b u 3 I mms a b ww b u s s I

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j uww s uhi s bu s uumuys bv bsis ayus s b suse uus Isry b u ss as vysi u b i vil ui w w i u J a i s a w%s uJ

s. . 1 L. 21J-_ __JJ- L_ TL. _____..J L.-__ L.. L_.- J... 1-__J _ _ - - J J _ J a-4 usa s sus su s a i sy uww a uns i b J . sssw y1 vyvasu wssusryw a su a wwwsi uwwwavybu s ui s J s un s ivy LL. J_--_L.--- t LL. _--L.J--- L L-.._J._. J_ 1J_JLJ . LL. -- . _...--_. e ~

bris smyvr busrww vs b s tw vvisbuaammiab uvus suus y ssa e a m i b s ry bu N hvs I JUqub i sww J vs u CPSES No Significant Ha:ards Consideration - CTS 3M.9 38 12/15/98 l

l

. _ _ _ m _. _

IV. SPECIFIC NO SIGNIFICAN' HAZARDS CONSIDERATIONS I 1

NSHC LS-20 (continued) 1

., s. . 1 L - _ . 41 J - ,. -- JJm A TL. _---. J L-.. -il .. tm

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IIIJ syissi Ibusik.

Lin P T rif

k&' LI A7 A nne PfutPTMPnATTMt nf*Tr*nhJ T LI A T T M1 siw J 4 Ui f 'i l i sru.mitus hviss a ubin i Avis u6 s buu sa sin i a vsi o-__J m_ .L. L_... ... ,.. .a__ a. 2_ mm__,..JJ .u 4 tum --.2.44 - ,. _2 t m a . 4 u vuJLu via bssu uuvvu v v u au w wivsi, Ib ia hvs sw s uuvu bu su b basu wwbiy ILswa uaavuiukuu vs i bi s Ltet lP ast e n n ti . 1 L 2 m, $_-_ LL. --_.--*2-_ L- LL- A_--..J TP 2>-L -Laaf,. LL, -- l fisisu Lv LV s UJu i b Illy : I VIII bish kvi t y si J I vi s bv bisb s isfyi v v Wu iw s vi isIU b JubsaeJ bi as asy

]

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l i

l l

n l

, CPSES No Significant Ha:ards Consideration - CTS 3N.9 39 12/IS/98 1

Industry Travelers Applicable to Section 3.9 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-20 Incorporated 3.9-2 Approved by NRC.

TSTF-21; Rev 1 Not incorporated NA A i;;;reved by 1R 3.9 001 NRC, Change not consistent,with current plant bperation; l

TSTF-23, Rev. 23 Incorporated 3.9-13 Traveler bracketed ITS 9 3,9 37~

3.9.2 and revised the Bases for 3.9.3. l l Bracketed Bases I information from the traveler that is not )

l applicable to a specific plant l was not incorporated.

Approved by_NRC.

l j TSTF-51 Not incorporated NA Requires plant-specific reanalysis to establish decay time dependence for fuel l handling accident. j

! 1 j TSTF-68, Rev.1 Not incorporated NA Similar changes l (Difference #3.9-1) were incorporated into the ITS

based on current licensing basis.

l TSTF-92, Rev. I Not incorporated Not NRC approved as of l traveler cut-off date.

TSTF-96 Incorporated 3.9-4 Approved by NRC.

TSTF-136 Incorporated NA l TSTF-139 Incorporated NA TSTF-153 Not incorporated No: N!!C ;;;;;rav d as af 1R 3.9 002 tray;;;rc;:--;'f date: Editorial change to 3.9.5 unnecessary whe.reas 3.4 and 3.5 were revised to

~

match 3.i>5 wording TSTF-31219 No neorporated .

c 3,9 7

,,mm,.

WOC-1031 Incorporated 3.9-15 ( 3.9 la

,. T_STF_-27.2

Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations l

LC0 3.9.4 The containment penetrations shall be in the following status: !

i

a. The equipment hatch closed and held in place by four 18 '

]

bolts: 1

b. One door in eeeh the emergency air lock closed and one j doorjinithel personnel l airlock; capable 1of.;being1c1osed; and 4914 1

c. Each penetration providing direct access from the containment I

atmosphere to the outside atmosphere either: '

1

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by an OPERABLE Contain= nt ;pg, i'ur;c and Exhaust Isciation System containment ventilation; isolation system yalve, e3.9a7: 4 Z.. f._ . .b idt ;t(5 k N h M t5 5'[ k hidir. N b 55l G G n I d 5IA apt;i. ..t:4 ,;pt c;it: thel: tside;4 nptar; =y be s+n ugini;t;jj;.ipc.gi;tratiy:s.trel;;. 0397 w.~. .

_ .. -. -s._ . _ ss ,2 APPLICABILITY: During CORE ALTERATIONS, I l During movement of irradiated fuel assemblies within containment.

ACTIONS l

l I

l l CPSESMarkup ofNUREG-1431 -ITS3.9 3.9-5 12/15/98 i

I

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend CORE ALTERATIONS. Immediately penetrations not in l required status. ANQ J

A.2 Suspend movement of irradiated fuel assemblies Immediately within containment.

1 l

Containment Penetrations l 3.9.4 SURVEILLANCE REQUIREMENTS j SURVEILLANCE FREQUENCY l

SR 3.9.4.1 7 days Verify each required copa=n* nanatr2HnQ intharecuiredStatuski.gccptf;Ecer,tcirs,,, B+H j

I h tE -ti G N M i 976 M R p 4 j d;ir,ipt, p Q 3.9 7 Ceii9]^. j- 7 SR 3.9.4.2 Verify each required containment purg; ar.d 18 months iB:

cxhaust vent 11ation21 solation valve actuates to ,

the isolation position on an actual or ' PS ::

simulated actuation signal.

l J

CPSESMarkup ofNUREG-1431 -ITS 3.9 3.9-6 12/15M8 i

Containment Penetrations B 3.9.4 l BASES l

BACKGROUND The other containment penetrations that provide direct access (Continued) from containment atmosphere to outside atmosphere must be m isolated on at least one side.gc;; cp;p cadcg=ni;tr;tj

@ trols. ) Isolation may be achieved oy a A c xd :n OPEr n0 ;3.9-7 g automatic isolation valver or by-e-manual isolation valve, or l bysaLblind flanger or equivalent. Equivalent isolation methods l must be approved and may include use of a material that can i provide a temporary, atmospheric pressure, ventilation barrier for the other containment penetrations during fuel movements (Ref. 1).

l APPLICABLE During CORE ALTERATIONS or movement of irradiated fuel SAFETY ANALYSES assemblies within containment, the most severe radiological consequences result from a fuel handling accident. The fuel handling accident is a postulated event that involves damage to irradiated fuel (Ref. I 2). Fuel handling accidents, analyzed in Reference 2 3, include dropping a single irradiated fuel assembly in;either the containment or,fue_1 building with no: credit;for isolationLor filtrationi and handling toci cr a heavy object on':e other irradiated fuel assc blics. The requirements of LC0 3.9.7,

" Refueling Cavity Water Level," and the minimum decay time of 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to CORE ALTERATIONS ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the guideline values specified in 10 CFR 100. Standard Review Plan, Section 15.7.4, Rev.1 (Ref. 2 3), defines "well within" 10 CFR 100 to be 25% or less of the 10 CFR 100 values.

Containment penetration elosure_1s:not;requiredtto meet;the acceptance limits for offsite radiation exposure of will be 25%

of 10 CFR 100 values (Ref;3) cr the NRC staff approved licensing basis (e.g., a specified fraction of 10 CIR 100 limits).

i Containment penetrations satisfy Criterion 43-of the NRC Policy State cat 10 CFR;50.36(c)(2)(11).

l LC0 This LC0 limits the consequences of a fuel handling accident in containment by limiting the potential escape paths for fission product radioactivity released within containment. The LC0 requires any penetration providir.g direct access from the containment atmosphere to the outside atmosphere to be closed except for the OPERABLE containment purgc and cxhaust ventilation penetrations and;the: personnel air.. locks. For the OPERABLE containment purge and exhaust ventilation penetrations, this LC0 ensures that these penetrations are isolable by the Containment l CPSESMarkup ofNUREG-1431 Bases - HS 3.9 B 3.9-15 12/15/98 l

l

Containment Penetrations B 3.9.4 BASES Purg; and Exhaust Ventilation Isolation System. The OPERABILITY requirements for this LC0 ensure that the automatic purg; and exhau;t vent 11ationtisolation valve closure t4mes function specified in the FSAR can be achieved and, therefore, meet the assumptions used in the safety analysis to ensure that releases through the valves are terminated, such that radiological doses are within the acceptance limit.

Both containmentipersonneliair;1ock doors ~.may be:open_~during movement:oflirradiated;fuellor CORE'ALERATION,2provided anf air lock:doorni.stcapableiofibeing closedf anditheLwater11evellinithe r_efueli ng; pool ti s1 maintained ; as : requi red .; 2Admini strati ve controisiensure that 1)Lappropriate:perconnellare awar.e .oft the openjstatus:of the: containment;ouring(movement;of, irradiated fuel or CORE ^ALTERATIONSU2)j specified individualsfare; designated 'and readily availableito,closelthe airilock;followi_ng;an. evacuation that would toccuriin)thelevent of,a fuel; handling? accident and~3) any obstruct 1.ons'(e,ggcablesfand1 hoses) that wouldl prevent1 rapid closure;offaniopenfairilockican be_.quickly; removed.:

,h; LCO i; ;;difi;d by X not^ all;Wjoi N ati;ti G fl I Rth with diistinsnifie;;;stoi . .st,;te;phere, t;:b; ;ij:;;l;t.

Ord;EJd;;;inistr;tiv;5en'vr;J;. Ad;;;jni;tr;tiy;5;ntr;is:s;;r; 0-3.9 7 th;t X ;ppropriete:F ranal Or;; ;;r; 3 7;th; A g n;; tot;( ;f th;Lgntr.;tica 'l= pth;durin; ;;re oiter;tienslcr ;;;;gant i offirr;dicted.f;;1/n;;blic:; within esteinantf ad 2))F;ifyd l individuels :;r; daignt;dlnd E;;dily ev;il;bi; t;'i;;let; th-

)

fl;Wpth in th:3y stlc'l;if=lih adling =;ide t.

l APPLICABILITY The containment penetration requirements are applicable during l CORE ALTERATIONS or movement of irradiated fuel assemblies within i containment because this is when there is a potential for a fuel !

handling accident. In MODES 1, 2, 3. and 4, containment I penetration requirements are addressed by LCO 3.6.1. In H0 DES 5 and 6, when CORE ALTERATIONS or movement of irradiated fuel assemblies within containment are not being conducted, the potential for a fuel handling accident does not exist.

Therefore, under these conditions no requirements are placed on containment penetration status.

ACTIONS A.1 and A.2 If the containment equipment hatch, air locks, or any containment penetration that provides direct access from the containment .

atmosphere to the outside atmosphere is not in the required )

status, including the Contai ment Purg; and Exhaust I;olatten l System containment ventilation isolation; system not capable of CPSESMadup ofNUREG-1431 Bases -ITS 3.9 B 3.9-16 12/1S/98

j Containment Penetrations B 3.9.4 BASES l automatic actuation when the purgc and cxhaust isolation valves are open, the unit must be placed in a condition where the isolation functica is not needed. This is accomplished by immediately suspending CORE ALTERATIONS and movement of l irradiated fuel assemblies within containment. Performance of these actions shall not preclude completion of movement of a component to a safe position.

SURVEILLANCE SR 3.9.4.1 REQUIREMENTS This Surveillance demonstrates that each of the containment ,

penetrations required to be in its closed position is in that I position. The Surveillance on the open purgc and exhaust I isolation valves will demonstrate that the required; valves are not blocked from closing. Also the Surveillance will demonstrate that each valve operator has motive power, which will ensure that each required _ yalve is capable of being closed by an OPERABLE automatic containment purg and exhaust ventilation isolation j signal JTh; SR ;g;ifi;; tt,;tjer,teir.x;,; gr,xr;mr.g.,/ !

er; eg niunderfe iini;tr;tiy; centr:1; 3r;Laet f; aired to 0 3.9 7 j x;;th;pi-ingth;; tin.t@tth;;gatr;tions3;egaj The Surveillance is performed every 7 days during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment. The Surveillance interval is selected to be commensurate with the normal duration of time to complete fuel handling operations. A surveillance before the start of refueling operations will provide two or three surveillance verifications during the applicable period for this LCO. As such, this Surveillance ensures that a postulated fuel handling accident that releases fission product radioactivity within the containment will not result in a release of fission product radioactivity to the environment.

l SR 3.9.4.2 This Surveillance demonstrates that each required; containment purgc and cxhaust ventilation valve actuates to its isolation position on manual initiation or on an actual or simulated high radiation signal from a containment atmosphere CP 3.9 002 gaseousLaonitoringiinstrumentation_ channel. The 18 month Frequency maintains consistency with other similar ESFAS i l instrumentation and valve testing requirements. In LC0 3.3.6. !

the Containment l' urge and Exhaust (continued)

CPSESMarkup ofNUREG-1131 Bases -ITS 3.9 B 3.9-17 1N15/98

CHANGE NUMBER JUSTIFICATION l

3.9 7 In accordance with the current TS LC0 3.9.4 status item c.2, and associated Bases, would be modified to state " capable of being i I

closed by an OPERABLE [ containment ventilation isolation valve]"

(i.e., the word valve would replace the word system). l 3.9-8 Not applicable to CPSES. See conversion cc:::parison table ]

(enclosure 6B).

3.9 9 Not applicable to CPSES. See conversion comparison table 1 (enclosure 6B).

3.9 10 Consistent with the currcat TS CTS;LC0![3.9,9;1], ITS 3.9.7 Applicability is being revised to delete "During CORE ALTERATIONS, except during latching and unlatching of control rod )

drive shafts.. vt_

ism A__,

yr , 2 _s. mL suib4 , a t ,. .

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tb.L. 4s 4

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s Equ a i virmi 3 b 3e uuyI abub yw vi u I wavwubwu bvws au a a vu I wyww I a wu b c vsi

___.4_____s t__ __. u__ .. .. 1 ..u__ 1_ . . 1 a..ma__ __.. - .a _s a u gu u i wrim u s b a vi i www bus vsasui nu bwe awwwa uun a:ry unu y wisuu s s b vi

_1 svi .sbs v __J,.

i vu r r _ _1_ _ u _ J s - _ L J uselvwubwu bmws o s s wu 1,

_ , , _ J c: _ u a o n n erew i s , wu b s v.s . . . / . .m, 2 0 3.9 23 The- ~ located specification place; a ic'vcr li;;;it on the ; cunt .

.__ _L _.._ .u_ .__ _,.u_ , . . _ , ____u,2_. 2_ mu_ __. .__ '

bwa uuvvw bssw bvy vi bs m auvi u J rwrisa# s i w a isi beav s www bvI

..~1 Ama__ __..-_-_t _s ___m__1 __A vu- n.. . rrere vUJdus uus iiry inv v w rim s i b v' wvt 3 b i Vs i vuae assu uudua L g b i iJ

,M eMk.n n\1 .&.&_ ALos &LJ_ _ _ _ . . _ _ _ AL. ...L__ _ _ _ . .. . nn er _t AL_

s //J @buww ba su b bis a a siswun wa betw vvu bE s swinvvwa s s re vs 6:15

. . . . ._ _ ; i n & :_m__ _.- ._ta..as.. __1_.._; r__ AL_ ..._m..__ _c ._

u J auruw u a v's a vu i s aw yuy ubb y Iby i Liwuavu a a Uru barw s uybus s vs uns J .J4 a _J s. . _1 ...__L1.. J. AL_ _.__t _t - c. . _1 L _;14__ .__JA&

ussuusubsu suss u a wwrins i g saa bi m w w wi s h vi u suus u sus tu s a s sy uww . uwi s k p ril A 4 Il_.....m AL. ..----A _f ___A__1 __A J.

g s s in / .

__& . .__J.&_J ,

a TVvyw y w s , btis nrv v wisew s a b vs uvil b u v i ivud iw s av b uJavwsubEv i

. .J & L 4L. J J L J .1 ___JJLJ_ . _E - PtfA .J &L_ n..__ A __L vv i ha s bars sis s b s u s bus iu s b s viis vs u i s in , uuru bits uuaws uv s iv b

.Ad__., __m.._Ad__ 2_.J,.. L__L _464.11L., . .L 4 a.L __.14 u vu l 5JJ u t iJ. , , . . . svi rwEi__ .__-si I syul u s 13 I s Iuu y w a bElIb wa i b i bu s i bJ svi I i wi i wvuIu icad to a breach of the fuel rod This;STSfApplicabilityldoes;not address;the movement?of.f.fue1Lin containment 1exceptfwithin1the reactor 1vesseDJ ItYdoes ,;however. ; apply: to CORE' ALTERATIONS l otherthanEfuehmovement:;ThisLrequirement'does;notmeetthe .

I criteria offl0.CFR'5.0;361.1n t -

terms;offits association.w.ith an' FHA.'-

- l The;revisedLApplicability;provides; assurance;o.fJsufficient water I to;assureiremovallof;99 Eof ^a 10%; iodine; gap releasesin the event ofda. FHA?in the; containment;while; moving 11rradiated; fuel?

__L, ._ _A 3.9 11 .____A_.

_ uwwvivu.mw .- .uubsk,

. . . . . _ , _ _ i nn x bi u wm .ss - v.

.L.

bs m www irn 2.

s. mvus,2_; swu bv re s su i y

. ___u_.u__ , , _ . . _au mLu _ _..a A _ m__u ____.. ,_ _ .L.

u ys , is b i u b a vil B 8 vvs yu b u s bifu b yuvviuwa u I a vw b uwksaa i i vvn bgrv

___s.a____s s_ AL_ _..A.JA a__.L__ s. L. .._4._1 t_J ..A_

svi s b u a a verswil b hv bstw vubJluw w benvJyi m 6 u bv uw usisaviubwu un guw s ad;;;inistrative controls. The clicencc to havc contain;.cnt fic'

_..L. . .a t t 22___. ______ ,___ .L_ ___..a____t ot__ _L___ ._

yu bs id v4 I bis uliVvb uwwSJJ 33 viss bs N hvli b u li nim e r b u binv ays iw a U bv

.L. ....2A u__ _L___ _ , u _2 A_ . A 4. 2 . _ u a bu m vubesus o bmv eri rs s u u.s . . _ 2.,v ubwu rus s u unissise b. u b .._vu S.

controls is based on confir;;;atorf !c;c calculation; cf a fuci o.3.9 7 u _;, .__a;__i ..La_L ..___m L,_ _.24_,__2_ ,

usussu a _ _uwwsuwsav Isry svi s s ws a 2,_22_. truiwubu _ V.wsybuuiU iuuivsvyivua

._J &_ J__1___ A . A J J , s m .& 4. ._ ___&__1. &L s 00 % _y_u...___.

u wsmw. uiru bv i nry s wism. i b uumissiebiubius v un i b i v i o kiiu b

__..__ AL s sL_ s1 -. . .sa__. . .J 11 L_ _____s1m _1_ _J wisdua w bi tu b birw a s vys __N(s yE k s u b s vi ed vv i a i uw ya vissy k I J wsvawu c_11_.4__ . s. . 1 L._J14-_ m J A_ A a_ ___..JA At__._ J A_ t a u s s uvv s i ty u suwi u suiiu a s i sy uww s uwi s b . bv ysvuauw -u wwiwasas- s u s us y bs mL A_ ___s m___m L1_ A- _ .__.._ .__ yk.

e_yny_ _v_ uws bv sim w b uwwwybuwsw wwww vvi s awquwi rww a . sirs

. A 2 _a _s _ .m2.._ ___m._i m. Ar2__a a_ AL. n i _ _ .s 4s _vs- .m ._i b ui e .__ us i , i ,mu Not uumssssJbiubius hvi s b e v i syu s als him vuemJ.

used CPSES Differencesfrom NUREG-1431 -ITS 3.9 2 12/15/98

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 3.9 Page 2 of 2 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY

=

3.9-8 The NOTE of ITS 3.9.5 is expanded to incorporate current Yes No - not in CTS nom not in CTS No - not in CTS licensing basis allowing the RHR pump to be removed from service for less than or equal to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months fnr leak testing of the RHR suction isolation valves.

3.9-9 The surveillances of ITS 3.9.5 and 3.9.6 are modified to Yes No - not in CTS No; not in CTS No - not in CTS incorporate current licensing basis of two RHR flows dependant upon the number of hours the reactor has been subcritical.

3.9-10 ITS 3.9.7 Applicability is being revised to delete "During ;Yesy Yes: Yes rcicc;ted pcr Yes rclocated pcr CORE ALTERATIONS. except during latching and unlatching of f.c.d. cat 00 1.~.-A cnt 100 control rod drive shafts.' 'hc fspliciility i; Scing rcvi:;cd bcc;;;c t';i; rcq;irc.s..t is duplicativ: ; rcloc;ted tcch-ic;l ;pccific; tion rcqu1. s .. t for rc;; tor vc; ci j 0 3.9-23 l u;tcr icvci dur'n; .cv_.m.J. of centrol rod;.

3.9-11 i ~;ccordancc with tr;;clcr '."C 75, thc LCO i; ;cdi' icd to VesNA YesNA VesNA VesNA pcr;;t ; pcactration fica p;t' th;t pre.idc; dircct ;;;c;; .0-3.9-7 l I frc; thc m.tci.~.t to thc cut:idc ct c;phcrc to te (unisciatedundcrad;i-i;trativcccatrols.Mt'used 3.9-12 A note is added to the Applicability of LCO 3.9.6 Yes Yes Yes Yes indicating that entry into a H0DE or other specified condition in the Applicability is not permitted while the LCO is not met.

3.9-13 In accordance with DCPP current TS. LCO 3.9.2 would not be Yes No No No used. .

4 3.9-14 A note is added to the Applicability of LCO 3.9.1 Yes Yes Yes Yes indicating that entry into MODE 6 from H0DE 5 is not permitted while the LCO is not met.

3.9-15 LCO 3.9.1 has been revised to clarify that boron Yes Yes Yes Yes concentration limits do not apply to flooded areas that are not connected to the R*5.

CPSES Conversion Comparison Table-ITS 3.9 12/1588

=. -. . ..

l l

ADDITIONAL INFORMATION COVER SHEET 1 j ADDITIONAL INFORMATION NO: O 5.5-4 APPLICABILITY: CA, CP, DC, WC )

REQUEST: ITS 5.5.4 e and Difference 5.5-13 Comment: WOG-72 has not yet become a TSTF. Use current ITS.

l FLOG RESPONSE (original): This change to ITS 5.5.4 e was prepared in accordance with l WOG-72, Rev.1 which is currently under TSTF review. The change specifies that the requirement to determine cumulative dose contributions from radioactive effluents need be l

done on a current quarterly and annual basis instead of every 31 days. We believe there is a strong technical basis for this change to the ITS. We request that the NRC keep this as an open item under the assumption that the traveler will be approved prior to issuance of the SER.

FLOG RESPONSE (revised): Based on the present status to the generic change process for the STS, it appears that traveler TSTF-308 (previously WOG-72) will not be approved by the NRC in time to support the initial license amendments for the FLOG plants. In order to facilitate the issuance of these initiallicense amendments, an alternate approach has been developed which relies on the CTS, plant specific information and/or the NUREG but does not rely upon the traveler. This alteniate approach is hereby provided as an interim submittal to allow issuance of the initiallicense amendments. The changes which rely upon the traveler can be processed in subsequent license amendments following approval of the trsveler by the NRC.

ATTACHED PAGES:

Attachment 18, CTS 6.0- ITS 5.0, Administrative Conditions Encl. 2 6-6 Encl. 3A 3 Encl. 38 3 Encl. 5A Traveler Status Sheet and 5.0-10 Encl.6A 3 Encl.68 4 l

l l

l

\

l i

M MINISTRATIVE CONTROLS

e. Radioactive Effluent Controls Procram (Continued)

2) Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted area conforming to 10 times the concentration values in Appendix B. Table 2. Column i 2, to 10 CFR 20.1001 20.2402,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, l

4) Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas )

conforming to Appendix I to 10CFR50, i mummmmmes

5) Determination of cumulative ar.d projecteddndirojecteDdose contributions from radioactive effluents for tie um mt N m

o.5.4 4 l calendar quarter and current calendar year in accordance with . l the met _hodology and paramptore in the OnCM at least dy" ":t;Q: tic;t;' tM pr;j;;ted d;x ;wtribtimi_fer f5

y. I N 3 2,

- n

. $ N,. 5. h. .d $ $ N,. 3 N'C'

6) Limitations on the Operability functionsl. capability and use of r 2 08-Ag j the liquid and gaseous effluent treatment systems to ensure that ,

the appropriate portions of these systems are used to reduce j releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitncent conforming to Appendix I to 10CFR50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary conforming to the following:

a. For noble gases: Less than or equal to a dose rate of 500 mrem /yr to the total body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and

b. For Iodine 131, for Iodine 133, for tritium, and for all L

radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 !

mrem /yr to any organ. !

l 8) Limitations on the annual and quarterly air doses resulting from l noble gases released in gaseous effluents from each unit to areas l

beyond the site boundary conforming to Appendix I to 10CFR50,

9) Limitations on the annual and quarterly doses to a member of the !

public from Iodine 131. Iodine 133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the site boundary conforming to Appendix I to 10CFR50, and 1

l CPSES Markup of CTS 6.0 6-6 12/15/98

i i

CHANGE NUMBER NSHC DESCRIPTION l

the TS. These changes are consistent with NUREG 1431 and traveler TSTF 5. i 1

02-03 A Not applicable to CPSES, See conversion comparison table (enclosure 38).

02 04 LG Not applicable to CPSES. See conversion comparison table (enclosure 3B).

02-05 A Revises the radioactive effluent controls program to reflect wording in NUREG 1431 and format of the Administrative Controls section. % term " operability" is i

replaced with

functional capability" to avoid confusion with the TS definition of operability.

02 06 A Not applicable to CPSES. See conversion comparison table (enc 4sure 3B).

02-07 f(A Reviscs Radicactive Effluent Controls I'rogram dose l 0 5.5 4 projections to cct original intent of TS prior to impic;catation of CL 80-01. CL 80 01 provided the wording for the STS (Section 3.5.4.e' which combined the requirc cats for cumulative and projected dosc. This requires a plant to make projected dcscs for the quarter and year on a 31 day basis. It is only necessary and reasonable to make a projection for the next 11 days. A cumulative dcsc projcction is still rcquired for the current calender quarter and ycar in accordance with the 00CM. This change is ccasistent wi-th traveler '400 72.

Not~used!

02 08 H Revises the procedures section to refer to all programs listed in the program section of the Administrative Controls and ensures implementing procedure control for these programs. This change is consistent with NUREG-1431. This change is more restrictive because it now includes all programs (current and added) in the TS as well as those already specified in this paragraph.

02-09 A Not applicable to CPSES. See conversion comparison table (enclosure 3B).

l 02 10 M New program requirements include the " Technical Requirements Manual (TRH)." The TRM. as a program in the ITS, is consistent with the way similar programs (e.g.,

ODCH, Inservice Testing, etc.) are treated. Although this new program essentially reflects current practice, delineating it in the ITS is considered to be more restrictive.

l i

[ CPSES Description of Changes to CTS 6.0 3 12/1S/98 i

CONVERSION COMPARIS0N TABLE - CURRENT TS 6.0 Page 3 of 8 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 02-01 CTS Section [6.6a.] for Reportable Event actions has been Yes No - Deleted from Yes Yes A deleted from the CTS. CTS per Amendment 50/36 02-02 The " Safety Limit Violation" section is deleted from the Yes Yes Yes Yes LS-4 CTS The NRC reporting requirements are duplicative of 10 CFR 50.72. 10 CFR 50.73 and 10 CFR 50.36.

02-03 The implementation procedure requirements related to [ ] Yes No - Deleted from Yes Yes A the process control programs and radiological environmental CTS per Amendment and offsite dose calculation programs are deleted from the 50/36 CTS.

02 04 The In-Plant Radiation Monitoring Program is deleted from Yes No - Deleted from Yes Yes LG the CTS but the program commitment will be in the FSAR and moved to FSAR CTS per Amendment moved to USAR moved to FSAR implementing procedures. Any changes to the programmatic 50/36 provisions in the FSAR would be controlled by 10 CFR 50.59.

02-05 Revises the radioactive effluent controls program to Yes Yes Yes Yes A reflect wording in NUREG-1431 and format of the Administrative Controls section. The term "cperability" is replaced with " functional capability" to avoid confusion with the TS definition of operability.

02-06 The Radiological Environmental Monitoring Program is Yes No - Deleted from Yes Yes A deleted. The details and description of the program are CTS per Amendment duplicative of [00CM] requirements. The program only 50/36 maintains consistency with the requirements of 10 CFR 50 Appendix I.

02-07 bei;c; Rc5Accti;c Efflucnt Ccatrol; ."rosic;;; do;c VesNA VesNA VesNA C projcction; to acc: criginci "rtcat of TS prict to Q ~.;ction of CL 00 01. 000 72' Not:used 0-5.5-4 l CPSES Conversion Comparison Table - CTS 6.0 12/15/98

i Industry Travelers Applicable to CTS Section 6.0/ITS 5.0 TRAVELER # STATUS DIFFEftENCE # COMMENTS TSTF-9, Rev.1 Incorporated B.? ' NRC Approved.

TSTF-37, Rev.1 Incorporated 5.6-2 DCPP only TSTF-52,:Rev/1 incorporated 5.5-4 lacorporated draft Rev.

I per_Q3.6.1-6 0 3.6.1-6 l l

l TSTF-65{Rev.1 Not Incorporated NA5.2-9 Net NRC approved neef l 1R 5.0 005 l tran ;r c;;-c'i l

date.(CPSES,ordy)

TSTF-106, Rev. I Not Incorporated NA Retain CTS TSTF-115 Not Incorporated NA Not NRC approved as of traveler cut-off date.

1 TSTF-118 Incorporated 5.5-8 NRC Approved 1R 5.0 006 l

1 t l TSTF-119 N;; incorpar;;;d NA !! rdr. CTS 1R-5.0 006 TSTF-120,LRev.~ 1, Not Incorporated NA Retain CTS 1R 5.0 006 TSTF-121 incorporated Sr2-2 0 5.2 1

l TSTF-152 Incorporated 5.6-4 NRC' Approved 1R 5.0 006 TSTF-167 Incscpara: :d 6.-7-2 0 5.2-1 W O C-57,!!cv.! Incorporated 5.6-5 NRC Approved ag.5.0 003 TSTFJ-233]

W O C-72 Incorpar;;cd 56-13 C 0 5.5 4 WOC-05TSTF-237 Incorporated 5.5-14 0 5.5 2

" reps;;d Trave:er Incorporated 5.2-2, 5.2-3, 5.2-6[

TSTF-258 5.3-2.,15.5-1, 5.5-1 6;

[05.21 5.6-6, 5.7-1

i i

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Proaram This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentatior, including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming : 5.5-1 to 10 CIT! 20, Appendix 0. Tabic 2. Column 210) times ;the concentration: values;in Appendix;BGTable 2,1 Column:2 Lto 10-CFR 20.1001 F 20,2402:

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCH;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. DeterMnation of cumulative and projected do;c contributions from radicactive effluent; for the current calendar quarter and 5 + +3 currcat calcadar ycar in accordance with the acth-" '- and 0 5.5 4 ar -^t^ : S the 000", at lea;t every 31 da s stion of cumul;tive de h ... sut en 77;;;; redi;;ctivc efflucat; fet _the curidat calcnO; q=tterA4 jurrcat edichdor yar..in eserix; With athedel;;;y rd per;ater; in th; 000 . ",

Octer;;;in; tic cf. projected de;c..sntribution;jer r di;ective a"lant; jn ;Gerdsco with =thedel;;;y in_th; 000" at lent cycry. 31 day:;. Determination.:of ~ cumulativeland ; projected ; dose contributions from. radioactive.effluentsiforithe current: calendar quarter land' current cal.endar year in accordance with the thodology!.and parameters in:the ODCM at.least every 31 days:

(continued)

CPSESMerkup ofNUREG-1431 -ITS 5.0 5.0-10 12/15/98

CHANGE NUMBER JUSTIFICATION 5.5-9 Not applicable to CPSES. See conversion comparison table (enclosure 68).

5.5 10 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

5.5-11 The documents refetenced for the testing frequency for the VFTP do not provide frequencies for combined pressure drop tests or the heater power rating test. The CTS frequency is added for these tests.

5.5 12 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

5.5-13 This chang ^ reviscs "adioactive Effluent Controls "regram dose 0 5.5-4 projections to mcct criginal intent of TS prior to impicmentation of -

CL 00 01. CL 00 01 provided th; wording for the STS (Section 5.5.4.c) which combined the requirements for cumulative and projectcc dosc. This rcquires a plant to make projected dosc for the quartee end year on a 31 day basis. It is only necessary and reasonabic te make a projection for the next 31 days. A cumulative dose projection still required for the curren'. calender quarter and year in (acMacc 1 with the CDCli. This is consistent with WOC 72. No 5.5 14 Section 5.5.7 is being revised consistent with TSTF 237 W9G-65 [ ]. 0 5.5 2 The proposed changes to Section 5.5.7 provide an exception to the examination requirements in Regulatory Guide 1.14. Revision 1

" Reactor Coolant Pump Flywheel Integrity." The proposed exception to the recommendations of Regulatory Position C.4.b would allow for an acceptable inspection method of either an ultrasonic volumetric or surface examination. The acceptable inspection method would be conducted at approximately 10 year intervals. This change is consistent with the NRC Safety Evaluation Report associated with WCAP-14535, " Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination."

5.5 15 Not applicable to CPSES. See conversion comparison table (enclosure 6B).

5.5 16 The Radioactive Effluents Controls Program is revised to include l0-5.21 l clarification statements denoting that the provisions of SR 3.0.2 and SR 3.0.3 are applicable to these activities. . These statements of appl.icability clarify the-allowance for surveillance frequency extensions'and. allowance to. perform missed surviellances. . Generic Letter 89;01,;" Implementation. of Programmatir.: Controls forLRadiological Effluent Technical; Specifications and the Relocation of Details of RETS

, to the Offsite Dose _ Calculation Manual or the Process Control Program" l allowed licensees to relocate the Radiological' Effluent Technical Specifications'and establish'the Radioactive. Effluents Control Program CPSESDifferencesfrom NUREG-1431 -ITS5.0 3 12/1588

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431,SECTION Sc0 Page 4 of 6 TECH SPEC CHANGE APPLICABILITY.

NUPEER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 5.5-11 The documents referenced for the testing frequency for the No Yes Yes Yes Ventilation Filter Testing Program (VFTP) do not provide See CN 5.5-12 frequencies for combined pressure drop tests or the heater power rating test. The CTS frequency is added for these two tests.

5.5-12 The referenced frequencies for the tests listed in the Yes No No No Ventilation Filter Testing Program (VFTP) were evaluated as part of the DCPP 24 month fuel cycle program (see LAR %-

09).

di "cdicactivc Efflucnt Control; cyc; dccc" YesNA YesNA VesNA VesNA 0-5.5-4 l.

projcction; to ;cct original 'ttnt of 5 prior to 5.5-13 ( of CL C0 01. C'.00 72) Not1used g.~..tatica j 5.5-14 Section 5.5.7 is being revised consistent with TSTF-237 e Yes Yes Yes Yes WOG-65 [ ] The proposed changes to Section 5.5.7 provide an exception to the examination requirements in Regulatory gg.5.5-2 l' Guide 1.14. Revision 1. " Reactor Coolant Pump F1.ywheel Integrity."

5.5-15 This change prcvides a time interval of within 31 days No No No Yes after removal in which a laboratory test of a sample obtained from the charcoal adsorber must be tested. This change is consistent with the Callaway CTS.

5.5-16 The Radioactive Effluents', Controls Program.'is revised;to Yes Yes Include' clarification statements' denoting that;the Yes Yes l 0-5.2 1l provisions'of SR'3.01and SR:3.3.3;are; applicable,to these s activities; 5.5-17 This change ~ deletes the_ phrase "and low pressure turbine Yes No Yes fes disc ~ stress; corrosion cracking 9fron~ITS 5.5;10;to make the l CA-5.0-0)3 l program l consistent ~with CTS;6.8.4.cs' 5.5-18 Revises DCPP. Sections 5.5.9 'and 5.6.10 to reflect License Yes! No! No No Amendment ~124/122. dated March 1271998[whichallows

-5.0-033 l 1mplementation.of steam generator tube' voltage ~ based repair criteria.for ODSCC:1ndications'at: tube to. tube support" plate intersections:

CPSES Conversion Comparison Table -ITS5.0 12/1588

ML20198J254

Text

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