ML20198J730

Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant

ML20198J730
Person / Time
Site:	Callaway
Issue date:	05/15/1997
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20198J711	List: ML20198J730 ULNRC-03946, Forwards RAI Re Proposed Conversion to Improved Tech Specs Sections 1.0,3.1,3.2,3.3,3.4,3.7,3.9 & 5.0.Suppl to Ref Will Be Provided at Later Date
References
NUDOCS 9812300250
Download: ML20198J730 (157)

Text

'

CHANGE MLMBE8 MBC DESCRIPTION L

addressed by the definition of the term Mode. This definition stipulates that fuel be in the vessel in order to be in a " MODE." Thesechangesareadministrative//nm. fare, 1 26 A

New sections 1.2.1.3, and 1.4 are incorporated into the improved TS to be consistent with NUREG 1431 Rev.1.

Section 1.2 provides specific examples of the use of the logical connectors MQ and 08 and the numbering sequence associated with their use in the improved TS. :Section 1.3 deals with the proper use and interpretation of Completion Times, and specific examples are given that will aid the user in understanding Completion Times. Section 1.4 deals with the proper use and interpretation of surveillance frequencies. Specific examples are given that will aid the user in understanding surveillance frequencies as they appear in the improved TS. The proposed changes are administrative in nature and by themselves are not h l $~l 1 27 M

The definition of Restricted AFD Operation (RAFD0) is deleted from the current TS. in accordance with NUREG 1431 m

Rev. 1.

See CN 115 M in the 3/4.2 package.

1 28 LG The current TS definition of CONTROLLED LEAKAGE is deleted to be consistent with NUREG 1431 Rev. 1.

The RCP seal water return flow limit is moved to a licensee controlled d%a a u.s=a 1 29 LS 3 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).

ra i r-2D6 1-30 A

Consistent with & d V M the definitions of

$ /,/-/

Channel Operational Test (C0T)4[ ] and Trip Actuating 7 %d mevice Operational Test (TADOT) are expanded to include

//4.t-/tr 88/d j

7 the details of acceptable performance methodology.

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Performance of these tests in a series of sequential, overlapping, or total #35D steps provides the necessary ssurance of appropriate operation of thed86D7h channel,relyjr d

dev/ce, ree/ ecd'n/g.This change also makes the COT *[] and TADOT definitions consistent with th definition of Channel Calibration which already cont ns similar wording.

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DESCRIPTION OF CHANGES TO CURRENT TS 6

5/15/97 O

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INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0

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TRAVELER #

STATUS DIFFERENCE #

COMMENTS T3TF 19, Rev. 1 @ Incorporated

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~we-JUSTIFICATIONS FOR DIFFERENCES FROM NL' REG-1431 Section 1.0 This enclosure contains a brief discussion / justification for each marked up technical change to the NUREG 1431 Revision 1 to make them plant-specific or to j

2.

incorporate generic changes resulting from the Industry /NRC generic change process.

l The Change Numbers are referenced directly from the NUREG-1431 mark ups. For l

Enclosures 3A. 3B, 4, 6A, and 6B, text in bracM s "[ ]" indicates the.information

)

is plant-specific and is not common to al1 the Joint Licensing Subcomittee (JLS) l plants. Empty brackets indicat at JLS nl

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ve plant.sp d f.1c information in that location.

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_t NUMBER JUSTIFICATION M/ue/ve se re/retta

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j 1.1-1 The NUREG 1431 Rev.1 definitihf Channel Calibratiorwm b wnhr ar*

hl-ew ythe itntire channel, including the Tae//M//r#/'*/ag required sensor. alarm, interlock. display, and trip functions."& Th

' Ac il /svest la /- 4.

5 c ange clarifies whatl n y

a se t e

re an i oy ew ain n

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isp ys, and ip nct ns A t/af/.e e/048to#m 1r to r

s if' d fet fun ion

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The ha el i

l/rfrev7/4/ O-fle r

on T t d ri h+ 's + 4 n na ice er ion Te d in' ions 2 I

4/sh La dhis change is consistent with TSTF-@ 2OC sim ar r is a

1.1 2 Not used.

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1.1 3 fn e mp to S

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1.1-4 Not used.

1.1 5 The definitions for ESF _ Response Time and RTS Response Time ar.e revised Qu e

e rd er' ie 1 li of me sur ons' t t th f)/,/-4 h

e ir n

of R

14 5

3.

1.1 an SR

.3

.10 is a e ur to is ncy t en e

fi ti sfrR su a

t re ir nt to ri ic v

ri Re e Ti

's w' hi mi s.

his an i consistent with traveler TSTF 111, l'WrERTCA-)

1.1 6 The definition of the Pressure and Temperature Limits Report is revised to include the maximum allowable PORV lift settings and arming temperature associated with the [ Cold Overpressure Hitigation System (COMS)] and to be consistent with the COLR definition. Improved Technical Specification 3.4.12 states that the PORV lift settings are specified in the PTLR. The current definition for PTLR does not identify these lift settings as being contained in the PTLR.

The [COMS) arming temperature was added to the PTLR, since changes in the heatup/cooldown figures could change the arming temperature. This change corrects the PTLR definition to be consistent with all of the requirements contained in the PTLR. Referenced methodologies for the PTLR contain the methodology used to develop the heatup and cooldown JUSTIFICATION FOR DIFFERENCES TS 1

5/15/97 l

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CHANGE I

NUMBER JUSTAFTCATTON i

figures, as well as the methodology for developing the [COMS]

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1.1 7 Notappicabi Ejli awa;g-ry.Se onversion mparison Table y.

(Enclosure 6B).

1.1 8 The reactor vessel head closure bolt requirements for MODES 4, 5 and 6 are clarified. The proposed change revises note b for MODES 4 and 5 to refer to " Required reactor vessel head closure bolts fully tensioned" and note c for MODE 6 is revised to read " Required reactor vessel head closure bolts less than fully tensioned." The transition point between MODES 5 and 6 would also be clarified as occurring when the required reactor vessel head closr e bolts are less than fully tensioned. The required ntaber of closure bolts, which may be less than the total ntaber, is established by analysis that demonstrates adequate 0 ring compression to prevent leakage and ensures that ASME Section III limits for affected components are not exceeded. This change is consistent

$ /,/-f with a;pmwTwnwann 1 e NRC SafeJy &nlas/rk 7W, Alex43 b.E.I'ebw// dates MeyM i9/t)& MAC-tggs[da} eof gle(Me,.a q, j977),

i 1.1-9 Consistent with6athe definitions of Channel Operational Test (C0T

] and Trip Actuati1g Device Operational Test (TADOT) are j /Y4.r/v,- fe/.7"l expanded d) [ include the details of acceptable performance me Y#6 7-,

f/ m Performance of these tests in a series or sequennai, overlappinn, or gg g, g y>

total 6 steps provides the necessary assurance of appropriate operation of the @ channel This change also makes the COTPand

~;

TADOT definitions consistent w the definition of Channel Calibration which already contains similar rding.

j relap or dehe, reryeelh"veh.

1.1 10 This change is based on the current TS definition of CONTROLLED LEAKAGE. This change is a clarification only and does not affect the way RCS water inventory balances are perfonned.

1.1 11 new example to ITS Section 1.4 to clarify surveillance freq 1es that contingent on both a specified frequency and plant itions.

MdY The ITS c ain:, many Surveillance Frequencies that are ntingent on

fueI, both a " spec 1 ed Frequency" and plant conditions, r example, "Within 7 days p r to the initiation of Physi ests," and " Prior to dIb entering MODE 4 from DE 5 if not performe ithin the previous 92 days." These Frequen-do not fal clearly under any of the existing Section 1.4 examples, h

oposed example is needed to make clear that 1) the SR 3.0.2 ext al of 1.25 times the specified frequency applies, and 2) t the int 1 allowed to perform a missed Surveillance by SR 3.0.'

pplies.

SR 3.0.2 is cle hat the 1.25 extension may be ap 'ed to "the interval spe ied in the Frequency". so the proposed chnge does not i

change t intent of the Specifications. SR 3.0.2 applies a

h,,

Surv ance is not performed within the "specified Frequency

Again, t

example does not change the intent of the Specifications but nly JUSTIFICATION FOR DIFFERENCES - TS 2

5/15/97

~

l CHANGE

(

NUMBER JUSTfFICATION p "frequ condMions.

application of SR 3.0.2 and SR 3.0.3 to sur -

es-

[

M with l

This change will eliminate d misapplication of the ITS and

@ l.b[ -

will ensure cans application of SR and SR 3.0.3 to these types o eillance Frequencies. This change 1 sistent with l.

e er AE3Cis633 TJYF-241 8 /4-/

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Tl* l* A~ ninon o-0 CHAWNEL. cat.xgggrzsg is,e yr,,)

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t JUSTIFICATION FOR DIFFERENCES TS 3

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wNVERSION COMPARISON TABLE FOR NUREG-1431 DIFFERENCES Page 1 of 2 i SECTION 1.0 DEFINITIONS i

DIFFERENCf FROH NUREG-1431 APPLICABILITY f

DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION

/

a-*C 1.1-1 This change c ifies 2 : :.._ r :::: t': nt'r: :h.... J Yes Yes Yes Yes hy

. m..

he definiti

t.t, "'h; _HANNEL CALIBRATIC'.y:" :- :----

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.h

-- re-': :, m-d' T hr: _, :.hac m..v....:.

• * -i r 'N' ' : c;&cd t--

p:r';-; :h; : ::t '!:d :$ty '...o ;u.a.~

TrgC0! ei.J -

-Meef definitionpqimilarly revised.

C&Qmh,, 7"Q b7 N/A N/A N/A N/A 1.1-2 Not used 8

g u.+ a.ra.

I )

1.1 4 Not used N/A N/A N/A N/A 1.1-5 The definitions for ESF Response Time and RTS Response Time Yes Yes Yes Yes are_ revised.ju s'

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.r ui so 1.1 6 The definition of the Pressure and Tegerature Limits Yes Yes Yes Yes Report is revised to include the maximum allowable PORY lift settings and the arming tem erature associated with the system. and to be consistent with the COLR definition.

1.1-7 The detinition of Channel Functional Test in the current TS Yes No Not part of No - Not part of No - Not part of will be retained in the i g roved TS. This definition is not current TS.

current TS.

current TS.

in NtJREG-1431 Rev 1.

gotebisrevisedtorefertothe"Requiredreactorvessel

-Ves-d(p

-Vet-M

-Ves-A/,

Yes 1.1-8 head closure bolts fully tensioned

• and note c is revised

((,/.JJ to read " Required reactor vessel head closure bolts less than fully tensioned."

.Tha Callakt mrjecificc$

e, CGrlVERSION COMPARISON TABLE - NUREG-1431 5/15/97

t

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b;d s

j CONVERSION COMP /RISON TABLE FOR NUREG-1431 DIFFERENCES Page 2 of 2 j SECTION 1.0 DEFINITIONS DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY I~.> Ms.rfer Melay Tu+; Slave Kelay 7e'.u+.

1.1-9 The definitions of Channel Operational Test (C0T)Y[ ] and Yes Yes Yes Yes Trip Actuating Device Operational Test (TADOT) are expanded to include the details of acceptable performance W I",*j aff methodology. Performance of these tests in a series of sequential overlapping. or total @ steps provides the necessary assurance of a repriate operation of the

& channe1 rt ley, er Viem,94rfec}fvely, 3

1.1-10 This change is based on the current T5 definition of No - Not part of No - Not part of No - Maintaining Yes CONTROLLED LEAKAGE. This change is a clarificattor; only current TS.

current TS.

ISTS wording.

and does not affect the way RCS water inventory balances sre performed.

1.1 11 FAdd x

e TS ect

-Vet A/

h A hk/)

W[

nci th ar on.

on 1

-que ya pi. co t1 s f /\\{g/ gr d,

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CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.1-25 APPLICABILITY: CA, CP, DC, WC REQUEST:

ITS 3.1.4 Rod Group Alignment Limits (All FLOG Plants)

JFD 3.1-16 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 (Z) (F, 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 (supp'ement): 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 (Fo ) 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:, CTS 3/4.1 - ITS 3.1 A, Traveler Status Sheet A, page 3 8, page 3, CTS 3/4.2 - ITS 3.2 Enclosure SA, Traveler Status Sheet A, page 3

.M

,g, -,

p.g.-aw1

+

2ndustry Travelers Applicable to Section 3.1 TRAVELER #

STATUS DIFFERENCE #

COMMENTS

-w TSTF 9, Incorporated 3.1 1 NRC approved.

Revision 1 TSTF 12.

Incorporated 3.1 15 NRC approved.

ITS Revision i Special Test Exception 3.1.10 is retained and re numbered as 3.1.8, j

consistent with this i

traveler and TSTF-136.

idit 13 Incorporated 3.1 4 NRC approved.

Revision 1 Idit 14 Incorporated 3.1 13 NRC approved, Revision g 4

-rg y,jg i

sit 15,_ ;

Incorporated NA NRC approved.

Revision t TsTF 89_

Incorporated 3.1 8 NRC approved.

tdit107gey.l Incorporated 3.1 6 g3, p/f idit-108.-

@ h orporated

$ NRC approved, Revision 1 7.1-01 swww NZ/-ddl

-TSTF-110 Incorporated 3.1 10 Revision g 2 NAC 9rwe).

TR-3,14

~ TSTF;136- ~

Incorporated 3.1 9, 3.1 15 NgC agnvel.

-r2-3./ gf TSTF 141 Not incorporated NA Disagree with change; traveler issued after cut off date.

TSTF 142

@[corporated

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werMD 3.1-22 t/ J AL ), 9-3./-M 3

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Q MARK UP OF WCG STS RE'l 1 (NUREG 1431) 5/15/97 n

w s

---+n

CHANGE NUMBER JUSTIFICATION l

g Thermal Power is within the defined power level for Mode 2 during the f%i performance of Physics Tests. since there is an Action that addresses M

Thermal Power not within limit yet there was no corresponding LCO or l

surveillance requirement. The Surveillance Frequency of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is retained from the current TS. This change is based on traveler i

TSTF 14, hi ;ien 3.

~772-2./ -445 3.1-14 Not used.

3.1 15 Consistent with TSTF 12. "u oim 1 ISTS LCOs 3.1.9 and 3.1.11 are '/Z-71-#04 deleted. The physics tests contained in LC0 3.1.9 were only contained in some initial plant startup t+ ting programs. The physics 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 Wcrth Measurement in the N 1 condition. The use of other rod worth measurement techniques will maintain the shutdown margin during the entire measurement process and still provide the necessary physics data verification. Since the N 1 measurement

{

technique is no longer used, the SDM test 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 F (z) is within its a

1.

limit. F (z) is approximated by F/(z) (which is obtained via a

1 SR 3.2.1.1) and Fa"(z) (which is obtained via SR 3.2.1.2).

Thus, both F/(z) and Fa"(z) must be established to verify F (z). This change i a

consistent with Cra$eIP@dw] -Me curren./- T5

$J,/-2f 3.1-17 Consistent with current TS LC0 3.1.3.2 and the wording of ITS 3.1.7 Conditions A and B 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 102-LS-1 of the 3.0 package (see the LS 1 NSHC in the CTS Section 3/4.0, ITS Section 3.0 package).

rNEGMT~ tA-3A

& 2.1-2-)

3.1 19 Not used.

3.1-20 Consistent with current TS 3/4.10.3. " Physics Tests." ITS LCO 3.1.8 and its Condition C and SR 3.1.8.2 are modified to refer to " operating" RCS loops. Adopting the current TS wording is acceptable since valid T,y measurements are not obtainable for a non operating loop.

f, j-;2 l ENfER7~ lA-28

~7T T. /-06 /

7.1-22 T& 3./-sor JUSTIFICATION FOR DIFFERENCES TS 3

5/15/97

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1 CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.1 Page 3 of 3 TECH SPEC CHANGE APPLICABILITY t

NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.1-16 This change adds the requirement to perform SR 3.2.1.2 in Yes Yes Yes Yes

- I addition to SR 3.2.1.1 during performance of ITS 3.1.4 Required Action B.2.4, NwtfLWTwe'rms

$ S. /- Q f 3.1-17 Consistent with current TS LCO 3.1.3.2 and the wording of Yes Yes Yes Yes s

ITS 3.1.7 Conditions A and B. 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 Yes Yes Yes Yes the LCO Applicability, per the matrix discussed in CN y

1-02-LS-1 of the 3.0 package.

3.1-19 Not used.

N/A N/A N/A N/A 3.1 20 Consistent with current TS 3/4.10.3. " Physics Tests." ITS Yes Yes Yes Yes

[

LCO 3.1.8 and its Condition C and SR 3.1.8.2 are modified to refer to " operating" RCS loops.

j 7, /-2 l

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L CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97

l l

Zndustry Travelers Applicable to Section 3.A,yh& -), cAo c 2

/

on/y C ci m.r),

o

'h TRAVELER #

STATUS QIfFERENCE # [

COMMENTS TSTF 24 Not Incorporated NA Not NRC appoved as of gep, /

, traveler cut off date.

TSTF-95 Incorporated 3.2 06 Approved by NRC.

TSTF 97 Incorporated 3.2 07 Approved by NRC.

TSTF-98 Incorporated 3.2 03 Rev -t-2

-Tf-7,2-We 2 TSTF 99 Incorporated 3.2 08 Approved by NRC.

TSTF 109 Incorporated 3.2-15 Approved by NRC.

TSTF 110 Incorporated 3.2 10 ny,g j NAd, -r/--7.3-NF Rev. 2 7

TSTF 112,

-A t Incorporated 7."2-20[>trr; ler $t en d*e R-7. 2-e3

-4Wr-

"ct "9C ean = =d r cf Rev. 1 TSTF 136 Incorporated NA A,y -- a h #AC.

7-C-y,a g TSTF 164 Incorporated 3.2 11 Applicable to CAOC only (CPSES).

"40 ; -Rev. 1-Incorporated 3.2 05 "ill 'r.: rper:te-7T7F..24- /

3.2 1 ggpcrtier.: Of T r Q 3*"

g

^

85Y/

co f ra}eG f f 3,Yly) y

/

/ /p 3, j-2$-

Ayvd Ly Mc.

Ag iru lle 4* *

• ony ( ofSEr).

0 MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97 l

1 l

CHANGE NUMBER JUSTIFICATION 3.2 14 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 6B).

3.2 15 This change incorporates the industry traveler TSTF-109. Action A.2 would require the QPTR be determined rather than performing a specific surveillance because more than one surveillance can be used to end i

%ency determine OPTR. SR 3.2.4.1 was revised to retain allowance at SR 3.2.4.2 may be performed in lieu of SR 3.2.4.1.

The note or SR 3.2.4.2 is ch rg^d to requirc pcrfc = nce i, m os.t-io

.... ~..

.m

-inputs ere ineperchie. These changes are acceptable because they clarify the ISTS regar ing frequency and use of incore flux monitoring for QPTR measurement. The changes reflect that incore detectors provide an acceptabl QPTR determina} ion during all plant conditions.

are twired }o le cent,.r}e,& w&h fyorcoll've*W'n This change would require that both transient and static F measu,rements f 3.2-16 a

be determined wr'an performed for Required Actions 3.2.4 A.3 and 3.2.4 j r u /s &

o r

A.6.

The intent of the Required Actions is to verify that F (Z) is aferrs/of '

o Thischange{#

within its limit. F (Z) is approximated by F'a(Z) (which is obtained o

II' via SR 3.2.1.1) and F"fZ) (which is obtained via SR 3.2.1.2).

Thus.

j'"-

th FS (Z) and F*a(Z) must be established to verify Fo(Z).

a is consistent with &M5iRERBtRFD Vfe currenf TT.

S 3. /.25-m 3.2 17 T b requency requirement for performing Fa measurements has b I g3.t-3 revise o conform to CTS which do not specify a Comple ime.

Q 3 2-7 pSACurrent pr ice is to perform the measurements a on as practical.

The ITS SR Comp

'on Times are based on wha

's a normally reasonable Completion Time for orming a flux

, however. if problems occur.

the plant me be forced t duce er or shutdown. This would subject the plant to a tran ndition without sufficient safety basis. Therefore mai ing tta cu t TS requirement is acceptable because it would tinue to assure adequa eaking factor surveillanc thout subjecting the plant to unn ary shutdown transi s.

3.2 18 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).

3.2 19 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

Na+ *jy(liedle f 0* %Y S*

• O '"'"

O'*f""""

~M ~#' "M

g. 220 Dile En c losw-e j8}.

l t

JUSTIFICATION FOR DIFFERENCES - TS 3

5/15/97 L

l

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.2-6 APPLICABILITY: DC, CP, WC, CA 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 OPTR," to " Normalize excore detectors to eliminate tilt," 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 Power Tilt." What is status of WOG-957 FLOG RESPONSE:

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 l

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.

i 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 j

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:

Att. 8 CTS 3/4.2 -ITS 3.2 Power Distribution Limits Encl. SA Traveler page, 3.2-1 Encl. 5B B 3.2-5, insert A.1/A.2/A.3 Encl. 6A 3, Insert 3.2-21 Encl.6B 3

l r

F (Z) (F Methodology) o a

B 3.2.1B

)

j BASES ACTIONS M (continued) orderly manner and without allowing the plant to remain in ag unacceptable condition for an extended period of time.

[ 6 3. t-6 )

g m

5lA

) c A 3.1-c>o2-u A reduction of the Power Range Neutron Flux-High trip setpoints by 2 it for each it by which Fj(Z) exceeds its limit is a conservative action for protection against the consequences of severe transients with unanalyzed power distributions.

The Completion Time of 8 Z2 hours is sufficient considering the small likelihoed cf a severe transient in this time period and the preceding prompt reduction in DiERMAL POWER in accordance with Required Action A.1 7

{ g 3,t.s_

M Reduction in the Overpower AT trip setpoints by > It for each 1%

,G by which Fj(Z) exceeds its limit, is a conservative action for protection against the consequences of severe transients with unanalyzed power distributions.

The Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is sufficient considering the small likelihood of a severe.

transient in this time period, and the preceding prompt reduction W A.3

- in DiERMAL POWER in accordance with Required Action A

-_032R M

Verification that Fj(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 with safety analyses assumptions. Inh'erent' fin 3TsXct'ibn';is 5dedtTf.fcation. toy thEcf0sullif::the'Jo~ut~.ofilimit7tondit16ti ean'd

,thejco rrecti onjof ;the,;gausel,Dtojthelextent'r, ne_cessaryf.to'; allow sale operation llat'the3_igh,er 'powerfle~ vel.. The 6110wable power o

Jevel,Ms; determined 3.byleva]uat_ing.Tj(DJforthe.lhighe,r co.we.r a

level." 3R'372:1!1' must"beisht'isfied'p'ri6r '.t6 increasi#g. pow 6r abdye,;thelhigherL~a))owable:.; power ' level 'or restoration ~of any -

reduced ~Reactorlrip~ System"Setpo,ints;.

(continued)

MARK UP OF NUREG.1431 BASE'.

B 3.2 5 5/15/97

~

=.

I fndustry Travelers Applicable to Section 3. A,y/<*c.1/a 2

eAs c

/

onIy C ctve-d.

TRAVELER #

STATUS DIFFERENCE #

j/

COMMENTS TSTF 24 Not Incorporated NA Not NRC approved as of gev. /

, traveler cut off date.

TSTF 95 Incorporated 3.2 06 Approved by NRC.

TSTF 97 Incorporated 3.2 07 Approved by NRC.

1 TSTF 98.

Incorporated 3.2 03 Rev. + 2

-ff. 7,2-ce 2 TSTF-99 Incorporated 3.2 08 Approved by NRC.

1 TSTF 109 Incorporated 3.2 15 Approved by NRC.

TSTF 110 Incorporated 3.2 10 Onve//['N/d, T-t-7.2-Nf i

Rev. 2

-4m-

"ct "'I ennrnved ec et TSTF 112,

-Net Incorporated Z2-20[' travelerEUtcfrd*a T-7. 2 - e 3 '

Rev. 1 l

TSTF 136 Incorporated NA A,w _ e h WC.

7-(-y,p q TSTF 164 Incorporated 3.2 11 Applicable to CAOC only (CPSES).

t-l "d{ Q Rev. ~

ncorporated 3.2 05 Will ir.:cepcrate Q314 j

M P.34

-3 3.21gg

-pcrtic;c cf TSw-25_

t fyf/fcofp6ra}ec / / 3,2cly l,

! /D

$ 3.l-2.5 l

N A nved $

NAC*

ff 7

Appirulle -}s CAOC-only ( CfSE T.).

l 7

^1$ " W T f 2./ 87/7 I e- #-I j Q h1 I

h T ST F M N AC-(

MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97 i

l

. - ~

F (Z) (F Methodology) o o

3.2.1B

.'3.2 POWER DISTRIBUTION LIMITS

.3.2.1B ~ Heat Flux Hot Channel Factor (F (Z)) (F Methodology) a a

LC0 3.2.1B Fa(Z) as approximated by Fj(Z) snd Fj(Z) shall be within the limits specified in the COLR.

4 APPLICABILITY:

MODE'1.

ACTIONS I

CONDITION REQUIRED ACTION COMPLETION TIME A.

Fj(Z) not within limit.

A.1 Reduce THERMAL POWER

~ A h c A., (1.)

2 1% RTP for each 1% Fj(Z)

@MF j

exceeds limit.

(

M A.2 Reduce Power Range Neutron B 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> _

3.2 06 Flux-High trip setpoints K4 {

• U)

> 1% for each it Fj(Z) yr:.

-r ~

exceeds limit.

_~~

(

i M

A.3 R: duce Overpower AT trip 72 setpoints a 1% for each p 4 F,'($

1% Fj(Z) exceeds limit.

(v~ %

y g h-M A.4 Perform SR 3.2.1.1.

Prior to increasing THERMAL POWER above the limit of Required Action A.1 (continued) i

. MARK UP OF WOG STS REV 1 (NUREG 1431) 3.2 1 5/15/97

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

O 3.2-6 INSERT A.1 i

The maximum allowable power level initiaily determined by Required Action A.1 may be affected by subsequent determinations of F8(Z) and would require power reductions within 15 minutes of the F8(Z) determination, if necessary to comply with the decreased maximum allowable power level. Decreases in F8(Z) would allow increasing the maximum allowable power level and increasing power up to this revised limit.

INSERT A.2 The maximum allowable Power Range Neutron Flux - High trip, setpoints initially determined by i

Required Action A.3 may be affected by subsciuent determinations of F8(Z) and would require Power Range Neutron Flux - High trip setpoint reductions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the F8(Z) determination,if necessary to comply with the decreased maximum allowable Power Range Neutron Flux - High trip setpoints. Decreases in F8(Z) would allow increasing the maximum allowable Power Range Neutron Flux - High trip setpoints.

INSERT A.3 The maximum allowable Overpower AT trip setpoints initially determined by Required Action A.4 may be affected by subsequent determinations of F8(Z) and would require Overpower AT trip setpoint reductions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the F8(Z) determination,if necessary to comply with the decreased maximum allowable Overpower AT trip setpoints. Decreases in F8(Z) would allow increasing the maximum Overpower AT trip setpoints.

I l

[

l 4

r I

l CHANGE NUMBER JUSTIFICATION i

3.2 14 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 6B).

3.2-15 This change incorporates the industry traveler TSTF-109. Action A.2 would require the OPTR be determined rather than performing a specific l

surveillance because more than one surveillance can be used to and i

determine QPTR. SR 3.2.4.1 was revised to retat.n allowance th

%we^ey SR 3.2.4.2 may be performed in lieu of SR 3.2.4.1.

ThenoteNor SR 3.2.4.2 H chmged to requirc pciformance if-cnc "cr more" CPW-a3.t-ro i nputs ere inoperable. TFese changes are acceptable because they clarify the ISTS regar ing frequency and use of incore flux monitoring for OPTR measurement. The changes reflect that incore detectors provide an acceptabl QeiRdetermina}ionduringallplantconditions.

are mr. red lo le cons,Me,r) wrV4 &f ulfv*V fn f

d 3.2 16 This change would require that both transient and static F measurements Q ~

a be determined when performed for Required Actions 3.2.4 A.3 and 3.

1 grov,#e 4,-

A.6.

The intent of the Required Actions is to verify that F (Z) is agedehf a

within its limit. F (Z) is approximated by FC (Z) (which is obtained N&

a a

via SR 3.2.1.1) and FW (Z) (which is obtained via SR 3.2.1.2).

Thus,

N'N a

both FC (Z) and F"a(Z) must be established to verify F (Z). This change #

a o

1s consistent with greerwMs6 ffe curren+TT.

& 3. /.2r I

3.2-17 Th requency requirement for performing F measurements haspb Q3.t-3 a

revise o conform to CTS which do not specify a Comple Time.

3 2-9 g Current pr ice is to perform the measurements a on as practical.

The ITS SR Comp

'on Times are based on wha

's a normally reasonable Completion Time for orming a flux

. however, if problems occur, the plant may be forced t duce er or shutdown. This would subject the plant to a tran ondition without sufficient safety basis. Therefore mai

' ing the cu t TS requirement is acceptable because it would tinue to assure adequa eaking factor surveillanc thout subjecting the plant to unne sary shutdown transi s.

3.2 18 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).

3.2 19 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

Na+ *pp :eAle f 0 Ilaw'Y. S' ' 0* *'"'** 09" " *

~DE~~' *~0#3 i

2.2-20 Dile (Enclo.ruce id).

3. ?_ - 2. J u

3.t-2./

l l

r JUSTIFICATION FOR DIFFERENCES - TS 3

5/15/97

O 3.2-6 INSERT 3.2-21 LCO 3.2.1 is revised to clarify the Completion Times consistent with TSTF-241. The proposed change will require Actions A.1, A.2 and A.3 to be repeated after each subsequent FE(Z) determination if F8(Z) is not within limits. This will ensure that Actions are continued until the parameter is within its limit.

t

v.

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431'. SECTION 3.2 Page 3.of 3 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION.

DIABLO CANYON COMANCHE PEAK-WOLF CREEK CAltf.WAY i

3.2-19 This Wolf Creek specific change modifies SR 3.2.3.1 to No No Yes No resolve a literal compliance concern regarding the use of 4

the LCO Note to modify the SR.

f. 2 -20 ff,, COEs-yeca#c cl ye G Acc lan+:

No far No No 9-' ' *7 y ) Note inincorjorder TJTf-U2 (i.e.,

e(,Je, onl Co br b ~A.ci cept,,)

na N*f kefuired Actr~ b 1 la s

can ta + d tuheneve-Cond.% b r, e,4enj i

3.2.-11 L.C O 32/ U TN y =4._

ya Ya 6/* b'~

4, a w:+ t a

't-S TF YI.

a

?

i e

CONVFRSION COMPARINON TARI F. MIRFG-1431 4/14/07

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR-3.3-007 APPLICABILITY: CA, CP, DC, WC REQUEST: hicorporate %veler TSTF-311 as indicated on the attached pages.

ATTACHED PAGES:

j, CTS 3/4.3 - ITS 3.3, page 3/4_3-10 A, page 6 B, page 5 A, Traveler Status Sheet and page 3.3-15

. Enclosure SB, page B 3.3-69 A, page 15 B, page 21 l

l L

i 1

.q

,m

.TAllLE 4.34 g g need),

" 4#

r

'p REAC10RTRIPSYSTEMINSTRUMENTATIONSURVEILLANCEREQUlliEMENTS t

l~

E TRIP 3

ANALOG ACTUATlHG lt00E S -

/-gf -

CilANNEL DEVICE

-ECn ',lllICli CllANNEL OPERATIONAL OPERATIONAL ACTUATION- - S'J'"!c ' L L f!!cE-CllANNEL c5 FUNCTIONAL UNIT CllECK CALIBRATION TEST TEST L_0GIC TEST -!S REQuinED

-4 13.

Steam Generator Water Level Low-Low a.

Steam Generator Water S

R(21) Q (15)

N.A.

N.A.

_1, 2

/- a7-A Level Low-Low (Adverse

. Containment Environment) b.

Steam Generator Water S

R(;21) Q (15) it. A.

N.A.

!, 2-

/- 13-A m2 Level Low-Low (Normal Containment Environment) m.

c.

Vessel AT (Power-1, S

Rhll) Q (15)

H.A.

N.A.

-1, 2

/ -:23-N 8

j Power-2) l d.

Containment Pressure-S R(21) Q (15)

H.A.

N.A.

I,

2--

/17-A Environmental Allowance Modifier k

14.

Undervoltage - React.or N.A.

R h21) N.A.

Q [/s)

N.A.

/-:t3-A

/MC g

Coolant Pumps A

=J k

15.

Underfrequency - Reactor N.A.

R(31)

N.A.

Q (18)

N.A. /_.J.y_.4 Coolant Pumps A

j _ g__g 16.

Turbine Trip

/g m

t-as-A

~

Low Fluid Oil Pressure N.A.

R C11) H.A.

> -SfB (,10)-

N.A.

-+-

g j,,g_g g a.

b.

Turbine Stop Valve N.A.

R(pt)

N. A.

h -GN-(

10)

N.A. -

/-27-A y -f$s f-] vla-1-2+-L.T [

rior -l0 exc*e i l-/s'-A Menlock wAan even -Ma unr+

ne-12-on bar ieen in MobE3

- ~ - - - - -

CHANGE WgER EE DESCRI/ TION i

(Ah "A;)

In addition, current ACTION Statement [8].is revised for those interlocks required to be OPERABLE in NODES 1 and 2.

i N

If one channel is inoperable, the interlock must be i

determined to be in its required state or the plant must j

be in at least HOT STANDBY within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

The changes to current ACTION Statement [8] and the addition of new ACTION Statement [8.1] are more restrictive, consistent with NUREG 1431 Rev.1. Current j

~

ACTION Statement [8] will continue to apply to P' -tional Units [18.a and 18.e.] Revised ACTION Stateme.

and I

new ACTION Statement [8.1] provide one less hour exit Applicability, i.e. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, than the current ACTION Statement [8] which has the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> interlock state verification or entry into LCO 3.0.3 which allows an additional 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> plus 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to exit Applicability, for a total of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

i 1 13 LS 6

[ ACTION Statement [9] is revised 20 note that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

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

This change does not impact the conclusions of

)

WCAP 10271 P A, Supplement 2. Rev.1 since there is no change to the bypass time. This change is consistent with traveler TSTF 168.] ACTION Statement [9] is [also]

revised to require restoration of an inoperable RTB within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or the plant must be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, consistent with NUREG 1431 Rev.1. This is less restrictive since an additional hour is provided for the transition to H0DE 3.

1 14 A

In the ISTS Table 3.3.11 Function 20, the Reactor Trip Breaker (RTB) Undervoltage and Shunt Trip Hechanisms are separate from the RTB Functional Unit. The current TS have been revised to reflect these requirements.

New [ footnote (d) has] been added to the RTB Functional Unit to note that the same OPERABILITY requirements and ACTIONS apply to a bypass breaker if it is racked in and closed for bypassing an RTB. The bypass breakers were already handled in this fashion. ACTION Statement [12] in current' TS Table 3.31 has been revised accordingly.

cusent 3A-(,

& I-i+-A l

1 15 A

The ApplicaDility for the Reactor Trip on Turbine Trip l

function is modified by new footnote [(c)] such that this i

}'

function is only required to be OPERABLE above the P 9 interlock setpoint (50% RTP). This is acceptable sinc the trip function is blocked below P 9.

[New] ACTION NU-dd7 ( '

4 e Ti also reflechd nrs api, Mig / gel b M8 mTIc tab en TMla +. g-t,

_Quene?

6 5/15/97 DESCRIPTION OF CHANGES TO CURRENT TS

CONVERSION COPFARISON TABLE - CURRENT TS 3/4.3 Page 5 of 26 TECH SPEC CHANGE APPLICABILITV MNER DESCRIPTION DIABLO CANYON COMANCE PEAK WOLF CREEK CALLAWAY-1-14 In the ISTS Table 3.3.1-1. Function 20. the Reactor Trip Yes Yes Yes Yes

[

A Breaker (RTB) Undervoltage and Shunt Trip Mechanisms are separate from the RTB Functional Unit. The current TS have been revised to reflect these requirements.

i New [ footnote (d) has] been added to the RTB Functional Unit to note that the same OPERABILITY requirements and i

I ACTIONS apply to a bypass breaker if it is racked in and closed for~ bypassing an RTB. The bypass breakers were i

already handled in this fashion. ACTION Statement [12] in current TS Table 3.3-1 has been revised accordingly.

.[

\\!

1-15 The Applicability for the Reactor Trip on Turbine Trip No - see CN No - already in Yes Yes A

function is modified by new footnote [(c)] such that this 1-48-LS 4.

currentTS.See.

7)P-y,g7 i

function is only required to be OPERABLE above the P-9 e/n dAr /-fo.A,

_ / j interlock setpoi 50t RTP). This is acceptable since the i

trip function i ked below P 9.

[New] ACTION Statements lied to the Low Fluid Oil Pressure and i

bi d U/ ) M-k 7. 7-C

'[

Turbine Stop Valve-uosure u ip iom.ux...,

1-16 The requirement to verify the setpoint dur the emialy Yes Yes Ye's Yes LS-40 TADOT for RCP Underfrequency [and RCP Under liege] is deleted.

t 1-17 The bypass allowance can be used for surveill testing Yes Yes Yes Yes A

or setpoint adjustment. Setpoint adjustment n be i

i performed at power and may be required by ot Technical Specifications.

f i

1-18 The current TS requirement to reduce the Power tange Yes Yes Yes Yes LS-7 Neutron Flux Trip setpoints in the event a powe range flux channel is inoperable is deleted. The time to i educe power below 752 RTP is increased from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 12 h urs and, if actions are not completed as required, the unitj must be in l

H00E 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. M f

8 2 " F - /.2 d j

=

rrbykc.hk9eLy rz.la ~RadJ rn %,.,J r y-. n y l

W Qe/e n

on rule ~ +,3'-/.

l N

x CONVERSION COMPARISON TABLE - CURRENT TS 5/15/97 l

1NDUSTRY TRAVELERS APPLICABLE TO SECTION 3.3 TRAVELER #

STATUS DIFFERENCE #

COMMENTS g4 E4)ITSTF 19. Rev. 1 die & Incorporated NA

-Net NRC approved,-= ef "TE-N/Nef-tr =ler =t f' tt0.

nLmn ulu.

m ET" 35.' ".= 2 Incrprote 3.3 34 4 y, 3..99-TSTF-37. Rev. 1 Not Incorporated NA ITS 5.6.8 still addresses PAM j

reports. Sections after ITS 5.6.7 were not renumbered.

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

T37:'.E St E arpreted

-NA-

- U-i; Rtp; int; are All -.bl e nl m.

Tv, leo, of ;;1t;;; :nd i

s

__2_2

.._, m __

a,,

___,4 g-4.-

-in ths TS.

-rg-3,3-e.f TSTF111.Rev.d Incorporated NA g/,gg /

5 TSTF 135)/ev 3 Prti't T.341.3.344 ' =ture; th:

3 xir i; t=

"^2" :::P in Incorporated f

.3 93, n:

Id k: kG 4

3.3 95.

^"0 21 50^2 ite t =01 R.

3 3, pao 3.3 122,3,1-14'l " rti= ; -f tk t n = lor that

.4

}

3,wg,j ci;;n 'irrth cirify d

7,9 /#4 f ep"abi'it; req ir.unt; hem

• M J

be r ';2 r p ret;d.

rp-3,ygg l

TSTF-161Ary,/

Incorporated 3.3 79 Appewe/ ly Ngd, Q23-71 TSTF 168 Incorporated 3.3 43 Affe,ve/ /7 Ngc, 4 F.S+3 Affe, peg j Ngc, ry-3,y.g3 TSTF-169 Incorporated 3.3 42 y

i E -105 73yr. m Incorporated 3.3 49 4yy "r:pned tn'fele-Incorporated 3.3 107 "0C "ini-Crap Mti= Itr 137f-:3+f 4H5-a 1. 3 - fo 7 I F-~2//

Scoyor 4ed 3,3-/fg g g,.g m A-N j

7 i

t?

a 4

4

~

MARK UP 0F WOG STS REV 1 (NUREG-1431) 5/15/97 i

l'

_. ~ -

l RTS Instrumentation 1

3.3.1 j

i

(

. WM I

Q)SURVEILLANCEREQUIRENENTS (continued) l SURVEILLANCE FREQUENCY l

SR 3.3.1.12 Notiusedi 13.3 50.

w,re

.w a.

"P]. J. _....e,....

11.._.__.._

J. _ _.1.

. J _.

__.J 2.J..._AJ

.X.

j

.._.._J

• l-_11 r

r. _ _1. w_._. t

___J..A____

e.._ A _

A -

___A..__

es _ _ A __ _

I www t e,J es wwsu.. L ap er wu..ww wy u bu. b siwe.w ww.

1,,___

s. 1. _..

a_t__1__

L.____

__A.

~,,

6 le-eenths I-SR. 3.3.1.13 Perform COT.

18 months 9

SR 3.3.1.14 '-

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

Verification of setpoint is not required.

l l.

},

Perform TADOT.

18 months

.B l

t s

L SR~ 3.3.1.15

- NOTE

-- NOTE -

\\

l Verification of setpoint is not required.

On requi

}

when perfcc within previ 31 days I

Perform TADOT.

P ior to reac r i

UN tar

} 23-M7 U

i SR 3.3.1.16 NOTE L,

Neutron detectors are excluded from response j

i time testing.

/

Verify M RTS RESPONSE TIMES'are 4e 18 months on a B-within limits.rfeerhel /n #4e ##A#,

STAGGERED TEST 3.3 55 BASIS l.

.s~

$ 2.1i'-SC t

\\

f fru3a.-lo ex ceedi fhef-jin4-ea.f]ch

~

7

"#"A(**

-/' b leen 5/15/97 7""'bE3})ifno-l'fe&o.ma MARKUP 0F WOG STS REV 1 (NUREG 1431) 3.3 15

'" N0

(

rrevion s

.t

RTS Instrumentation B 3.3.1 Mn d $$

BASES w

SURVEILLANCE SR 3.3.1.14 (continued)

REQUIREMENTS 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.

tXct*Yiy !

• M N' b l 4[e A inheloele

^ " " ' " '

SR 3.3.1.15 de

'n MbES. 71,s.

t SR 3.3.1.15 is the performance c f a TADOT of Turbine Trip Functions. This TADOT i; ;; '-~qikd in 2 3.3.1.4 a;;pt tMt thi; t;;; is performed prior tukLwMW D

G{ll3]Ppq) Surveillance is not required if it has been performed within the previous 31 days.. Verification of the Trip Setpoint does not have to be performed for this Surveillance. Performance of this test will ensure that the turbine trip Function is OPERABLE prior t g

act er cal in I

c s

r e

a a

and st o

pepturep.

or o ac st up exeendr

+$e A-f in1hteloele y

SR 3.3.1.16 j,

6? 3.~T6 SR 3.3.1.16 verifies that theffielfu6W) individual channel Meetn actuation response times are less t1an or equal to the maximum values assumed in the accident analysis. Response time test 4ng Wafgcatf._ GCr.%W acceptance criteria are yg included in Tst...ini ";;; irs.;...;; ";n;;1. geg Individual component response times are not modeled in the an lyses. The analyses model the overall or total elapsed time, rom the point at which the parameter exceeds the trip setpoint alue at the sensor t; the p; int ;t d.ich tk ;quipant rG;t ; the required fur.ctionel ;tetc (i.e.. satrol 7.r.d ;hutd;w, r y. fully faserted in the r;;;ter ;;rc'. untitftbss:.nestationa pner"cnN l'on in e

de

.p,,.

f,Y,'j, 9'I

-/w % m # < sa

• ~e.

Mr ar N.

For channels that mciuue uynamic tranuar runmuns te.g.. lag, -

r lead / lag, rate / lag, etc.), the response time te;t ;;y k verification'is performed with the tr=;fer function xt t; cx with th; roultin;; ;;nur;d re;p;nx tin s p;r;d to th

ppr;priate ISA" ra p;n x ti n. Alt;rr;tcly. th; r;;p;n;; ti;e tc;t an k p;rfer ;d with th; ti;; ;;n t=t; nt to tMir ne;iral ;r.lua, pro'eid;d th rcquir;d rap;nx tix i; i

(continued)

MARK.UP OF NUREG 1431 BASES B 3.3-69 5/15/97

. -. ~. -

CHANGE NLMIER JUSTIFTCATION (y%- 3.3 127-Not applicable to Callaway. See Conversion Comparison Table j k "W' (Enclostre 6B).

1 3.3 128 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

3.3 129 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

3.3 130' Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

l-3.3 131 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

l 3.3 132 Not applicable to Callaway. See Conversion Comparison Table j-(Enclosure.68).

l 3.3 133 Not applicable to Callaway. See Conversion Comparison Table l

(Enclosure 68).

l 3.3 134.

Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

,.s.,

L y gj..' 3.3 135 A MODE change restriction has been added to ITS 3.3.1 Condition C per i

u' j

the matrix discussed in CN 102 LS 1 of the 3.0 package (see the LS 1

)

l NSHC in the CTS Section 3/4.0. ITS Section 3.0 package).

1 3.3-136 The TADOT performed under ITS SR 3.3.2.7 includes verification of r'elay setpoints since the trip actuating devices being tested are the same l

circuits tested under ITS SR 3.3.5.2.

.rhtreR7-lA-/C l

l p

,s i

JUSTIFICATION FOR DIFFERENCES TS 15 5/15/97

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

I i

INSERT 6A-15 a

s 3.3-137 Not applicable to Callaway. See Conversion Comparison Table CA-9,7-g/2 j.

(Enclosure 68).

t 3.3-138 Not applicable to Callaway. See Conversion Comparison Table C/~M-403 (Enclosure 68).

3.3-139 Not applicable to Callaway. See Conversion Comparison Table b c-Att_gg (Enclosure 68).

1 j

3.3-140 Changes to RTS and ESFAS AT Functions are made to reflect C ": ';ay CA_y,g_g_j j

OL Amendment No.125 dated April 13,1998.

i j'

3.3-141 Changes to ESFAS Feedwater Isolation Functions are made to reflect CA y,g_ g l

Callaway OL Amendment No.126 dated April 23,1998.

3.3-142 Adds "or trains" to ITS 3.3.1 Condition A, consistent with ITS 3.3.2 and 7/_g,y_ g traveler TSTF-135.

i l

3.3-143 The Frequency of ITS SR 3.3.1.15 is revised to reflect traveler TSTF-311.

--y,y.g7 The Applicability of these Turbine Trip Functions begins in MODE 1 at the l.

P-9 Interlock (50% RTP). The STS Frequency, " Prior to reactor startup,"

is inconsistent with the Applicability of these Functions which can be 9..

tested at power with minimal perturbations to plant systems. These

~

TADOTs are typically performed prior to loading the main turbine, if not performed within the previous 31 days. Both Callaway and Wolf Creek have filed LERs (Callaway LER 97-005-05, ULNRC-03695 dated December 19,1997] regarding this issue. This change was previously approved for Vogtle.

l 3.3-144 Not applicable to Callaway. See Conversion Comparison Table

( 7,3-/44 (Enclosure 68).

3.3-145 In converting from CTS to ITS, information contained within an Action VC-7,7-6/9 Statement that modified the initial required action was converted to a Note. Based on formatting requirements of MUMARC 93-03, " Writer's Guide for Restructured Technical Specifications " the span of a Note is limited to the width of the text it modifies. Two case types currently exist l

within the ITS which require revision in order to meet both the intent of the i

CTS and formatting requirements of NUMARC 93-03. In the first case, notes span the width of the Required Action colurrn, but the intent in the CTS is to modify a single Required Action. In the second case, Notes span a single Required Action, but application of the Note within the CTS affects all Required Actions for the associated Condition. The span of i

t affected Required Action Notes has been revised to meet both the intent l

of the CTS and formatting requirements of NUMARC 93-03.

I l

I I

~

3 z

CONVERSION COMPARISON TABLE FOR DIFF' ERENCES FROM NUREG 1431, SECTION 3.3 P ge 21 of 21 TECH SPEC CHANGE-APPLICABILITY i

NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY l

' 3.3-136 The TADOT performed under ITS SR 3.3.2.7 includes No - adopted ISTS No - adopted ISTS Yes Yes verification of relay setpoints since'the trip actuating format.

format.

device being tested are the same circuits tested under ITt

.3 U l

'13-131

'the

"!.*fron O r Snc}ro,, 4.c it changa) fes

/Vo - r,,re,4 /

N,- 1,,ra,.)- /

g,_ x,,,, 4 7 r.,,,c

.,sie.,s i, e c ~t r + w w,+1.

b cfr c,s.

CA-23-6/2.

TI,rr cfJcs-acifra change revirer *T2 Ale 7.2.H, 22-in riote i,fe -r,,

,+, o,e,je g e,, n N -ii do jeg.

Q, A/,

s

• rums t1.,1+ a in Amendmen+sy4/,

c,.,.,,,,,,

y nd tal.*aH B,-

if / in lad 97-0bt a-

'I~his c la

.s..

SA 3.3*. D.13 w hre$ ft ffe 2 2-/39,*a-fo.,,,3,eud].r1,ew,p,,, ty man +L Tabor, sn 222.r f

y*

y*

}\\/,

ffoQ'*(*oha TAbd7 every D4-p c_pte.x 2

.r,,,,,.4 / : f AcHon.,y/rar f> can+.7,,ma.,4,oratruna H,3

-3, ~+ Hijk.1 (diffe,an+ hry).

yper 4

c A nges b bs,,) EsfAs 6 fu~ck nr 7 y-go No a,e p,,Je -lo r effec + Call <wy dL Asche,d-No A),

fer cA-3.f-do7 No.127 da-leol 4k'/U.

/

x s-i+1 cA.,.t s esrss f.ej,,.se-zr.i.ia,, r-.-ir,,,c N,

No No fe<

'A ~* *'~ "

ave Aa/e -/a re//ec4 Ca//aso. Of_ /In,e-q/s*, eor l~

No. /26 d-4ed //12,l47, Y

~1X-3.3-cig 2.3-/42 A4lr "oa -/> sins" }, 17'r C na:/4,, A, yer f*<

l co nris fes,+ sul}$ r T.T 2.3,2 o d fg_.jg EY/~~/SS.

3 3*I4*3 V'5

.2.~:i'-/f$ %.Zhff gf> Qj 3.~1-144- [U

}/es fer YES W~S*

N~

N,

' N,

& zz-510t COMPARISON Btf. MIRFG _ 1 5/15/

g g_,

gggy g_2; h

INSERT 68-21

. c 3.3-143 Revise SR 3.3.1.15 Frequency per traveler TSTF-311.

7 _yygg 7 3.3-144 SR 3.3.7.3 and 3.3.7.4 are deleted for DCPP since there are no actuation

~/O logic or master relays associated with the CRVS pressurization system actuation via the CRVS atmosphere intake radiation monitors.

3.3-145-The span of affected Required Action Notes has been revised to 4/C ?. F.-d/$

meet both the intent of the CTS and formatting requirements of NU. MARC 93-03.

l l

r l

1 i

l i

i l.

!c l

I l-

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: WC 3.3-019 APPLICABILITY: CA, CP, DC, WC REQUEST: In the conversion from CTS to ITS, information contained within Action Statements that modified the initial required action was converted 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.

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 require reformatting to conform to both the 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 require reformatting to conform to both the CTS and NUMARC 93-03. It was not the intent of the CTS that the clock for shutdown actions should start when a channel is bypassed for testing as allowed by these Notes.

ATTACHED PAGES:, CTS 3/4.3 - ITS 3.3 Enclosure SA, pages 3.3-3, 3.3-26, 3.3-27, 3.3-28, 3.3-29, 3.3-30, 3.3-33, 3.3-76, and 3.3-77 A, page 15 8, page 21 I

l l

l l

l I

i l

RTS Instrumentation 3.3.1

.s

-.~.-a ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME dM)

D.

(continued)

-E NOTE h @ required to be gg,3jy gp3t$/

1 Range Ne$ron Flux 6 to 0PTR is inoperable # y j DER 8TFWZiprnysA 5 eNE)

L5C--32.-l9 T'2 h Perform SR 3.2.4.2.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> x

E D.3 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E.

One channel inoperable.

NOTE The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing end-gggg

^ ; - -, o

=

m.m.. of other

.rm.

channels.

E.1 Place channel in trip.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> E

E.2 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F.

T" R"/.L PCWER : P5 F.1 Reduce THERMAL POWER to 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.3 95 and - P 10. One

< P 6.

3.3 107 Intermediate Range Neutron Flux channel E

inoperable.

l F.2 Increase THERMAL POWER to 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.3-107 l

> P 10.

1 (continued) l HARKUP OF WOG STS REV 1 (NUREG 1431) 3.3 3 5/15/97

ESFAS Instrumentation 3.3.2

-?

i ACTIONS (continued)

[

REQUIRED ACTION COMPLETION TIME CONDITION

~

C.

One train inoper ble. %

S

.7 72 NOTE One train may be bypassed

B Q

for up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for W surveillance testing

~

7 provided the other train is 3.3-/46'

g._.,_ __. _--Mr7-E----

,0PERABLE.

NC-3.7-0/1 o1,,rai n,ca-p, w a m r -- --------,,,,a 7^O')T#'"8/'"I*.'-

C.2 Restore train to OPERABLE 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

~

nd A' o( A 14

^

k

.Lc0 h4.3, "C,o,#arded u

3 C.

1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> z>,/.-b',n V /y,,," A;;

eon +arnmen+gu a.1rolakn' 1

M ulves nde o,

,.llei.

t isoldfon frukn-la#!.

3 C.

2 Be in MODE 5.

42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />

.h N ___ W f

x D.

One ' channel inoperable. @

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

g,f

+-- The inoperable channel may h/C-27-0/4 be bypassed for up to

$ hours for surveillance B;

testing of other channels.

b.l Place channel in trip.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> k

,T D.2.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i

M D.2.2 Be in MODE 4.

18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> i

i (continued)

?

l MARKUP OF WOG STS REV 1 (NUREG 1431) 3.3 26 5/15/97 i

i ESFAS Instrumentation 3.3.2 17 e pry ACTIONS (continued)

CONDITION.

REQUIRED ACTION COMPLETION TIME

[

m --

E.

One Containment Pressure @.

- NOTE -

l channel inoperable.

'e-One additional channel may 7.7-/ M l

be bypassed for up to Lt/c-3.7-4/4 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> for surveillance

8 testing.

e.................b.........

~

C hilwrML NcTE E / Place channel in bypass.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> L

l m'

E.2.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 81 0 l

E.2.2 Be in MODE 4.

18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> L,,

s F.

One channel or train F.1 Restore channel or train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable.

OPERABLE status.

E l

F.2.1 Be in MODE 3.

54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> AND l

F.2.2 Be in MODE 4.

60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> l

t I

(continued) l i

MARKUP 0F WOG STS REV 1 (NUREG 1431) 3.3-27 5/15/97 i

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

l ESFAS Instrumentation 3.3.2 l

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 1

G.

One train inoperable.

- - -NOTE 7 --

i it---One train may be bypassed 2,3-Itf forupto4hoursfor Wc-7.7.gq B

j surveillance testing provided the other train is OPERABLE.

p........ 2.........).........

Mull wT +k MrrE 1

C,/'RestoretraintoOPERABLE 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A

status.

m 2

G.2.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i

s AND G.2.2 Be in MODE 4.

18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />

')

H.

h. +"4.a 4.,-..^_'..

gygg

)

3 --

One tre => bc tm cd --

g.y-/+/

y y,g-

-f0r up t: jh;;r:f;r

~o

raille. ice t=tir; F ;.id;d thc st,b t.elii ia m-..

vs w vuJL.L.

5 I U

~'

t;.t.;;

-:.2 De ni H00: 0.-

-12 huu.e (continued) i l

i l

l MARKUP OF WOG STS REV 1 (NUREG-1431) 3.3-28 5/15/97

ESFAS Instrumentation l

3.3.2 i

L 7-y -

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l

[

x I.

One channel inoperable. / @ - - -- - NOTE

\\

e---The inoperable channel say 3,1- /+f be bypassed for up to wc-7.7dli 6hoursforsurveillance B-l testing of other channels.

g_...Nu...............,........

( II suidh hic 1E) f/ Place channel in trip.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A

0B l

1.2 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> J. One Main Feedwater Pumps @m trip channel inoperable. 'e - m

7. "J-/4(

l N

L4fd-27-d/4 4

testtJggof," M

• ~@iN Tl lS~ ci! Restere channel te I 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

3;3 56-:

i A

^^ "X L st:ta;. jgLpg[ g x

i J.2 Be in MODE 3.

54Zhours 3.3 56s (continued)

MARKUP OF WOG STS REV 1 (NUREG 1431) 3.3-29 5/15/97

ESFAS Instrumentation 3.3.2

,m.

Mqd ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME r

K.

One channel ino.r: arable. @ - -

NOTE 4-- Onc sdditional An 3.3-18

i_noperablechannelmaybe bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> forsurveillancetestingof othenManntTyj

&-(p;,)i sijg gytk}---- -

T.2-l+c w c-2.g-o19 M/ Place channel in bypass.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A

t2p; E

8151

\\

M RestoNtoLO!!E@ BEE

??L@M status 4 4

E K.23.1 Be in MODE 3.

-12 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> M

K.23.2 Be in MODE 5.

42 1])8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> L.

One ogmorelregujr_ed L.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 3.3-44 chanr.el(s) inoperable.

required state for existing unit condition.

E L.2.1 Be in MODE 3.

7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> M

L.2.2 Be in MODE 4.

13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> 4

i (continued)

MARKUP 0F WOG STS REV 1 (NUREG 1431) 3.3-30 5/15/97

p I

ESFAS Instrumentation 3.3.2 l

4$; %

' f)

ACTIONS (continued) v CONDITION REQUIRED ACTION COMPLETION TIME l

r l

RI One_"trai!Ginoperable?

t,f _._

~,-f _ NOTES = - ; 6 f 3.3-59:-

+ - one scain may bel ypassed b

rog_unctoghoussgor 7,7-I+r l

sunve:114ncefesMgg wc-7.JNii psitdetheathel::;t_ertEts

.ORERABIE

,4-Tyg.gg-f'j C

l.1BCinIMODEE3J Sihones

^

x K2 [eMn~310 DEW.

12ihoucs l

- s l

l 1

l I

l L

l l

l l

MARKUP 0F WOG STS REV 1 (NUREG 1431) 3.3 33 5/15/97 l

a.~

BUNS

- PS BePS m.

3.3.9

... - f 3.3 INSTRLHENTATION g 77v, -/-arn r r[-Me

$ f,7-/,2/

3.3.9 Boron Dilution "- '^^"-- M1 @at. log System OOPS) (BDMS);

ps 1

i gkyjfpBBPS4DMS shall be OPERABLE.

LCO 3.3.9 APPLICABILITY:

MODES 23 bel E P f; 3, 4 and 5.

$ g7 pp 3.3 (ggA

............................N0TE 4,44 The boron dilution flux doublir,g multiplication signal may be 3.3 36 f

blocked in MODES 2 (bel and 3 during reactor startup.

-3.3 88-x) /n-/er/,c/c

& 3:3-PP ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One train inoperable,gR A.1 Restore train to OPERABLE 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

, // f,

- d

. --l31

(

t-- A.l Q 3.5-12 / __

_i=~ L _:D 3 ~E-lU~:- - = =wst n -+s-~==

/n, iff T T Lin.}yM,mwas*"*"*fso0_rcQJage g'

_ ]...

i r

.J on" EEssT A Let*m31!LE!M1Rtor31s 3.3-121 1

ca

,/

E=

.-.g.;... g.n. r.. =, =-

n

-s,.,- n. =.+..

am.,=g B.

Two trains inoperabl Tuspend operations involving immediately 3.3-121 I

positive reactivity e

additions.

& 2.1-/2I f

n_

B.2.1 "cstore ;c,e trai W t-hette 3.3-88 An t-M A S t P Vi 64 v usw

.6..&..,

gwwbug, f!B Required Action and associated Completion Time of Condition A not met.

(continued)

MARKUP OF WOG STS REV 1 (NUREG 1431) 3.3 76 5/15/97

l l

BDNS PS '

l

j. __..

BOPS 3.3.9 i

l ACTIONS (continued) t CONDITION REQUIRED ACTION COMPLETION TIME e A. 2 5 --n a [13t-/2I B.

(continued) g

-eN;wr---ra l

0@ErggtrgedhM!Megange 3.3 121-1 ileukigfliaMtscatdr"is l

OfERAB[E.

= m::

w.w. ;=

l 0

?~~

trth-h3 6If l

Perform SR 3.1.1.1.

I hour 3.3 88 E

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter M

S.2.2.1 Close angggig hour 4Lifools 3.3 88 1E3. l unborated water source A

isolation valves" g gg PP BG N g BGV06011 wNnW B.3.

e*

• n m.

ra dri e et A

StCM wamma 1

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SRI 3~3193 P,erformLCHANNEECHEC}g 121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br />

-3.3 91 l

l SR?,313'.9;2 5 X-3 Bis ~;E BZ,-5 5 NOTE 5 5 1;JTH iZiE5 hi On.lt requi red;tol bej performedsinJMODEiS?

E EE5=hE555E23 55 zt=5=iiEEB1 Vetify;BGV0178ris;; secured l;in:,thelclosed

??(days 3.3 119 position; (continued) l MARKUP OF WOG STS REV 1 (NUREG 1431) 3.3 77 5/15/97 I

CHANGE NUMBER JUSTfFfCATf0N

., e 3.3 127 Not applicable to Callaway.

See Conversion Comparison Table b.; '

(Enclosure 6B).

J 3.3-128 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

3.3 129 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

3.3 130 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

3.3 131 Not applicable to Callaway. See Conversion Comparison Table (Enclosura 68).

3.3 132 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68)_

3.3-133 Not applicable to CalTaway. See Conversion Comparison Table (Enclosure 68).

3.3-134:

Not applicable to CalTaway. See Conversion Comparison Table

-(Enclosure 68),

m

p), 3.3 135 A MODE change restriction has been added to ITS 3.3.1 Condition C per the matrix discussed in CN 102 LS 1 of the 3.0 package (see the LS 1 NSHC in the CTS Section 3/4.0, ITS Section 3.0 package).

3.3-136 The TADOT performed under ITS SR 3.3.2.7 includes verification of r'elay setpoints since the trip actuating devices being tested are the same circuits tested under ITS SR 3.3.5.2.

.1yregr-4 A-IS~

1 l

JUSTIFICATION FOR DIFFERENCES TS 15 5/15/97

,y w.,-

1 l

INSERT 6A-15 m

F

\\

gy 3.3-137 Not applicable to Callaway. See Conversion Comparison Table CA-y,3-g/2 (Enclosure 68).

3.3-138 Not applicable to Callaway. See Conversion Comparison Table CS py_ggg (Enclosure 68).

)

l 3.3-139 Not applicable to Callaway. See Conversion Comparison Table b c -ALL-442 (Enclosure 68).

Changes to RTS and ESFAS AT Functions are made to reflect Callaway CA_y,g_g.7 3.3-140 OL Amendment No.125 dated April 13,1998.

)

1 3.3-141 Changes to ESFAS Feedwater Isolation Functions are made to reflect CA.g, y_g, Callaway OL Amendment No.126 dated April 23,1998 3.3-142 Adds "or trains" to ITS 3.3.1 Condition A, consistent with ITS 3.3.2 and ff_y,y_ g traveler TSTF-135.

J s

3.3-143 The Frequency of ITS SR 3.3.1.15 is revised to reflect traveler TSTF-311. -Q'-2,yq 7 The Applicability of these Turbine Trip Functions begins in MODE 1 at the P-9 Interlock (50% RTP). The STS Frequency, " Prior to reactor startup,"

is inconsistent with the Applicability of these Functions which can be j

tested at power with minimal perturbations to plant systems. These

~

TADOTs are typically performed prior to loading the main turbine, if not performed within the previous 31 days. Both Callaway and Wolf Creek have filed LERs (Callaway LER 97-005-05, ULNRC-03695 dated December 19,1997] regarding this issue. This change was previously approved for Vogtle.

3.3-144 Not applicable to Callaway. See Conversion Comparison Table

[/ 7,7 -/f 4-(Enclosure 68).

3.3-145 In converting from CTS to ITS, information contained within an Action 4/C -7,7-4 /9 Statement that modified the initial required action was converted to a Note. Based on formatting requirements of MUMARC 93-03, " Writer's Guide for Restructured Technical Specifications," the span of a Note is limited to the width of the text it modifies. Two case types currently exist l

within the ITS which require revision in order to meet both the intent of the l

CTS and formatting requirements of NUMARC 93-03. In the first case, l

notes span the width of the Required Action column, out the intent in the CTS is to modify a single Required Action. In the secccc! case, Notes span a single Required Action, but application of the Note within the CTS affects all Required Actions for the associated Condition. The span of affected Required Action Notes has been revised to meet both the intent i

of the CTS and formatting requirements of NUMARC 93-03.

i

2 i

c

/

3 CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431. SECTION 3.3 Page 21 of 21 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.3-136 The TADOT performed under ITS SR 3.3.2.7 includes No - adopted ISTS No. adopted ISTS Yes Yes vertfication of relay setpoints since' the trip actuating format.

format.

devices being tested are the same circuits tested under ITS SR 1.3 5 2.

Ylw ca.,Jr}<en -Ar Snciron 4.c tr cha,,

}/es No -rnrad /

Ato r~ 4 i A/o-x~ A /

23-/31 p, G,J;p,, b -fo E consided wr+ pad 4 44e bctr crs.

cA-2.3-6/2.

TJ,rr c fr e s-ecth cIm,,9e,eder 14' Ale 7.?.H,

{>

37-f17 Alole I,+b re Ove Jem,r, Am,,dmeJs-y' Y*

yer Afo A/o c& e m-hare N-/4 nd"=m*tuAxHS

-s t!,,;+ a

'f, cf_y.y,y3

.if / in lad 91-0B3..

t

'7~hrt j'eefo~e L.p. e,,JJr i.ew I A 7. 1. 2. 12 w A re 4 rr d e 7 3-/39

,-neeofa,, IP men +4 TAboT. SR 22.3.2 f

y' y*

A/,

Zjf*gfoya of a Tabor every D4-b c_Att.m 1 Inred / : S oarr AcHon y/rar-/n yj conhr,,m,,4y,-airuna Hi3 -3, ~4- //,31,-.1 (atfj'e,..,J-4, 4

f g.y_go changes b 2 *I and ESFAs aT~ &c/4nt No A),

A),

le.r CA-3.f-do7,

a,e o,,sle -lo reflec+ Ca ll<way JL An,Ja e,d-No. hs~ daleol 4hr/0.

2.3-/4/

CA,yar h E~rfM feedsu le - Irei.43,, Ka,cJisnc AI, N.

No

}/e<

CA~" o

"~e ^ de la re flec+ Cs//=w OL Ame 4,,e,#

N. /36 dd*d 4/>s/1r.

7X-3.7-pg 7.3-/42 Ad,lr "o< -Ivsinz" / zr.i' Csna&h2,, A, yer fe<

c wirie,+ suffL r T.T 2.3,3 o d o

g 3._jg

~T~~rTf-/35'.

@f*S 6J 8'SW Yet fe.r lN, 2 3-/ g g

g No N,

ar.r CONVERSI0f COMPARISON ABLE -

RE -1431 5/15/ 7 ler lc.r ler__

~

-3. 3-/95-ZA/SER7~ {A-2/

S

[t}C-ff hgh%.

' - !Mk f2hU. k.

~

^~

'7

INSERT 68-21 pq

.Qp' -

3.3-143 Revise SR 3.3.1.15 Frequency per traveler TSTF-311, 7g_yygg7 3.3-144 SR 3.3.7.3 and 3.3.7.4 are deleted for DCPP since there are no actuation

~/O logic or master relays associated with the CRVS pressurization system

- actuation via the CRVS atmosphere intake radiation monitors.

3.3-145 The span of affected Required Action Notes has been revised to C -3.7-d /$

meet both the intent of the CTS and formatting requirements of NU. MARC 93-03.

'+.

n

ADDITIONAL. lNFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.4.1-2 APPLICABILITY: CA,WC REQUEST:

Difference 3.4-40 Comment: WOG-99 has not yet become a TSTF.

FLOG RESPONSE: WOG-99 has been designed TSTF 282 which is currently under NRC review. No changes to the ITS mark-ups were made in the process of assigning this traveler a TSTF number. As explained in Enciosure 6B to Attachment 10, JFD 3.4-40 does not apply to CPSES or DCPP. Those plants are retaining their CTS, as explained under JFDs 3.4 34 and 3.4-51, respectively. Callaway and Wolf Creek continue to pursue the changes proposed by this traveler.

(SUPPLEMENT)

Based on the present status of the generic change process for the STS, it appears that traveler TSTF-282 will not t e approved by the NRC in time to support the initial license amendments for the FLOG plants. In cWer 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 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 NRC.

For Callaway, CTS SR 4.2.5.2.a is retained to require RCS flow be calculated prior to exceeding 75% RTP after each refueling outage, and SR 4.2.5.4 is retained which requires RCS flow be determined by precision heat balance measurement on an 18 month frequency. SR 4.2.5.4 is not tied to the beginning of a cycle. This is acceptable because other indication of RCS flow is available (RCS flow meters) until such time that plant conditions are established which are suitable for a precision heat balance. ITS SR 3.4.1.4 and its Bases are revised (new JFD 3.4-55) to additionally require the RCS flow be calculated prior to exceeding 75% RTP after each refueling.

For Wolf Creek, the Note to ITS SR 3.4.1.4 will be maintained with the 7 day interval based on 1

CTS. CTS SR 4.2.5.1 states that the provisions of Specification 4.0.4 are not applicable to RCS flow rate. Maintaining the ITS note allows performance of the SR in MODE 1 when the plant conditions support performance of the SR. The 7 day intervalis appropriate based on the prerequisites and time to perform the precision heat balance. CTS 4.2.5.4 did not specify a time frame for completing this survei!!ance. Current plant practice is to perform this surveillance as soon as practical after the plant reaches 100% RTP after a refueling outage. Calibration of the instrumentation used for determining steam pressure, feedwater pressure, feedwater temperature, and feedwater venturi Ap in the calorimetric calculations typically takes three shifts (approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />). Following instrument calibrations, data collection for the precision heat balance requires approximately two hours. Once the data has been collected, approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in necessary to complete the calculations associated with the precision heat balance. Therefore, the NUREG time interval of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Wolf Creek is not acceptable and the 7 day intervalis consistent with the intent of the CTS.

l

ATTACHED PAGES:

Att. 8, CTS 3/4.2 -ITS 3.2 Encl. 2 3/4.2-13 Encl. 3A page 10 Encl. 3B page 7 Att.10 CTS 3/4.4 - ITS 3.4 Encl. SA Traveler Status page 2,3.4-2 Encl. SB page B 3.4-5, insert SR 3.4.1.4 Encl. 6A page 6, 8, insert 3.4-55(6A)

Encl. 68 page 5,7, insert 3.4-55(6B) s

l

_ POWER DISTRIBUTION LIMITS l

3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DN8 related parameters shall be maintained within the limits shown on Table 3.2-1:

Reactor Coolant System T,yg, a.

l b.

Pressurizer Pressure, and c.

Reactor Coolant System fotal Flow Rate.

APPLICABILITY: MODE 1.

ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than :i% of RATED THERMAL POWER within the next hours.

OS*-OL - LS-2 (o

SURVEILLANCE REQUIRFMENTS 4.2.5.1 Each of the parameters of Ta'ble 3.2-1 shall be verified to be within their. limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

M U -2 J 'f " 2. 5. 2 TS:

1: elated RCLte+:! eu rate cha!' be determined-to-be i

2e2,5?e* c?".

th r. er ::; :1 t:

-/o - A Pri:r t: Oper:ti n abov: 75 :f P.ATED TiiE"JiAL "0WER-efter-eactt-fuei-f

{

-10: ding, :nd

\\

L.

At leest ei.cc per Z [f fective Tul' P---Days-c2. 3 M t

'1

~

r. --

a. g,:t,

,. Of -/PA 4.2.5.3 The RCS loop flow rate indica s sha e sub ected to a CHANbEi y c

CALIBRATION at least once per 18 m ra s. _

rhr+ renve M^^0 dr4e+; re~ve.rh-; kent)

M5 eea 3,+H

[

4.2.5.4 T

RCS total flow rate shal b Med bdreci:ica '::t bal:W

^., r t...: n t at least once per 18 months.

Within 7 day: Of p;rfaming-t 47/

1-

2. )>

-pre 1 irr Teat balance, the dart u-eatatier used fer determinatien-of-ste -

3. 4.1 precrure, feedeate" te perature, and feede ter ventur4 iD 4" the-calordmetri -

-calculaticas-: hall bc : 1ibr:ted.

06 6

' 2.5.5 The fec&f:ter ventur# ch !' be i nspected for fouling 2nd-cleaned-a w gecerrarj :t le::t en : per 12 eenth:---

05 - 0% LG l

i l

• ~hs silGalated 141Ud-Of "CC total flGW ratC Shall bc 0 Cd-9+ece-tincef4640tr4es--

sf 2.2% for fic

' including C.1*' for feedwatee-verite +-fot44ng}-measurement-

---have b:cn included i-tha--atove4urve4.1.lanca.

O f-O/- LG-I CAL WAY - 'ETT 1 244 -11 mendment No. 15 I

1. ~ M 27f 74 2?"I [

i r

CHANGE NUMBER NStiC DESCRIPTION is found to be outside the required limit. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> are allowed in order to restore the parameter to within the limit. If the parameter is not restored to compliance within the required time, the plant must be shut down.

The revised completion time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is acceptable to i

allow transition to the required plant conditions in an orderly manner without unnecessarily initiating any undue

^

4 plant transients and on the small likelihood of a severe event occurring during the extended time period.

%.1.1 ~2.-

g.k u. 1 05 07

/

Th surv lancp for measu ing RCS flow by precision heat alanc is modpfied to a a footnote hat corres nds'to the te for TS 3.4.1 The footn e requirer that the su eillan be perf ed within 7 ays of ac eving

• RTP. This is re restrictiv in that ties the 1

survei ance to e beginning o a cycle.

his is acce able bec se other indi ation of S flow is av lable (R flow meters) and time provided t tablish ant conditio s suitable or the preci ion heat

/ balance.

his is cons tent with aveler 'J00 In additfin,theTHERMA POWER spec) ied in e

otnote woul be changed om the gene ic value p o ded in NU 1431 to a ant specif'c value of 2 5% RTP.

his ange is acc able beca e it specifi

.a THER POWER in better af eement wit current opera g proc ures for performinf a precision eat balance. C rrent do not specify a power level for this meas re ent.7-f -aD. U hl0 05 08 Not used.

05 09 LG The requirements for inspecting and cleaning the feedwater flow venturi would be moved to licensee controlled documents. These details are not contained in NUREG 1431.

This is an example of moving unnecessary detailed information from the TS and is acceptable.

~

05 10 A

The requirement to verify RCS flow rate within limits

~

M* h2-grior to Oper;ticr cbov 75: "T" C ci ca l fuei ioaomg t

-ed-at leapvery 31Ms would _bgminat_ed froh)

SRs for DNB parameters. This is acceptable based on the requirement to verify RCS total flow rate once every l

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in accordance with SR 3.4.1.3.

In addition. P, l

is verified within limits prior to operatior, above 75% RTP after each fuel loading and every 31 days. The LCOs.

Actions and SRs for F",, and RCS total flow rate are adequate to address any DNB concerns related to these parameters.

DESCRIPTION OF CHANGES TO CURRENT TS 10 5/15/97

'1 un s e t.a.s a tn e but ta di sult th0LL LtJiutLt48 la.3 / -i. d Pd9t / ul /

t TECH SPEC CHANGE APPLICABILITY llUMBER DESchlPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 05-05 The Wolf Creek required actions would be modifled to move No No Yes No LG details regarding identification of the cause for low flow rate to the Bases.

e 05 06 lhe time to reduce power to less than 5t RTP would be Yes Yes Yes Yes i

LS 8 revised from within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

05-07 TM3 w.wiaseiu b.4 7td' Ore"ir=

'h'* i+ be No 6 II'.r t

5;; CN 5 11 *

-Yes-

-ftr5' f d 3.4.f 2

/ !

M pe r ne" m th b ' d;i5 af..,'-ic':M WL"*-

pit MA

" ' " ^ ' ^

gg Q C" ? ^ El-M

/VA 05-08 Not used.

NA NA NA NA I

05 09 The requirements for inspecting and cleaning the feedwater No - Requirement No - Requirement Yes - to USAR Yes - to FSAR LG flow venturi would be moved to licensee controlled not in CTS.

not in CTS.

Chapter 16.

Chapter 16.

documents.

l-05 10 The requirement to verify RCS flow rate within limits prtoc.

Yes No - Requirement No - Requirement Yes 3.4.t -2, }

A 7-P"

b.;75! * ="--

~h h1 inviing =t at not in CTS.

not in CTS.

least every 31 EPFDs would be eliminated from the SRs for i

DN3 parameters.

05-11 The change is specific to Comanche Peak. An action is No Yes No No A

added to clarify that the accident analysis support operation below 851 RTP with a reduced flow rate, and this condition is not affected by the failure of a precision RCS flow measurement to verify that the required flow exists.

In addition, the parameters to be verified per the LCO are clarified. Failure of the precision flow measurement, when below 85% RTP tollowing a refueling outage does not result i

in the violation of the LC0; it only prohibits power ascension above 85% RTP.

o g.-n the,-egu,rea,,e,d- -lef u h,,a /F no,4h DIAA/A/EL

- ye.r le t.

ler les lCl*-S A-00 ] )

A CALX &enwoNT ef -//,e Ac3 fo,p -Plos, rafe I,.l,'ca }o r it

-lIf27fJX:P 3.l. /0 -fw-i A'e e /o - %y rin,n G+ran,ewla +4,,

/N.,e No,, /0 fe cIn Cela,+ flow -lo&.

CONVERSION COMPARISON TABLE - CURRENT TS 5/15/97 I

'W'"

@M meigut W h eg TRAVFIFR #

STATUS DIFFERENCE f C0ttiEKf5

_)h Incorporated

<;EEBb NA Ap Mai =53*Aul j$ 73YF-RPa LA/J (d 3.4 /3 n

+n,aIIp! Bib T Incorporated cTJ@PD /VA A/g,ppy y j,,ggc 2

i l

In Y Se1-rel ewe

&3.f/>j LNe Anesen+.

4 4

^ en

.g-l l

l 4

MARK.UP OF WOG STS REV 1 (NUREG 1431) 5/15/97

t i

RCS Pressure. Temperature. and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS 1

l SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is 2 2000 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

B-PS-l EZ M Psig.

1 l

l l

SR 3.4.1.2 Verify RCS average temperature is s 581 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> JB PS ;

M *F.

i SR 3.4.1.3 Verify RCS total flow rate is a 2M.000 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> M /? gpm.

B-PS:

Om & M I

SR 3.4.1.4

+ L 0..'-

C

- - y NOTE -

t requ d to perfo nti) M ' Ira TNbnM50

• E"

3.

f v ' ' ' i ' M* ** ' W'

............i...l....

.after M

l y

3, j j

~ /

,Q n_A I _

l Verify by pr;;isier, h;;t belar.;; th;t g months

-B:

l RCS t al flow rate is a 204.000 382Ei3H gpm, B PS e.,sv w. y., s by frecl.rion ked ialance +kof l

l

\\

L

. NOTE

, amn u-W La.3A L A M q Tgge.n4L pow tr _- ~ - L'= j 7fIa ATI-n c

~ ~

t MARK-UP OF WOG STS REV 1 (NUREG 1431) 3.4 2 5/15/97

l RCS Pressure. Temperature, and Flow DNB Liuits l

B 3.4.1

-)

BASES er-foemance of a SURVEILLANCE SR 3.4.1.4 g.,

REQUIREMENTS g,4 f,, /m, (continued)

Heasurement of RCS total flow rat y 4 i.,-,,a ;T : trccision $3,f /-/

- '--iatric heet huncc once every IgnonthQhl I

llows the installed RCS flow instrumeltat1Ni Yifbe "g,9, g z.

ca' ibrated 3EBktG.j and verifies the actual RCS flow rate is greater than or equal to the minimum required RCS flow rate.

7..,w

,., a _rygggy e.;;;..... >. gy x;,, y. ;.; 7...

g 2 f l_j

...r. -. :

M'J 4R'Je %3i]@4XHD 9 Pa%W

WMl#MN @

liMrOd14WtL'tshMr..MM'.6 elikiN 49 3 SE9Jh %LiGh*

i DR35DME'EedE8@lBietift'8tMtREPRitDMLi!$by CEEolilWt%IL"t81MNtI6MZRlib]BtlEHFr)Ye3El.tTLMGCDtWf2

• * = M M"** % h W M & & ' # ^o= 5 V ""' g yyya m _ pe a er 3 y -- Q' p n.

~

1 months reflects the importance of verifyinb, gr yy j

The Frequency o 3 flow after a refueling outage when the core has been altered, which may have caused an alteration of flow resistance.

1 SR is modified by a Note that allows entry into MOD witho ving performed the SR.- and placement of unit in the best conditio r performing the SR. The states that the i g 3,y,j_[I TM SR is not requir performed 24 hears 75t!D5llafter I

s a. 3.q,1,1 2 99& ET RTP. This excep ~

s appropriate since the heat balance requires the to be a inimum of 904-9 8 RTP to I

obtain the st CS flow accuracies anaFassy- - wv==

tWr-uscrensumm: The Surveillance sia rformed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 7Edayslafter reaching 904-95[ RTP.

REFERENCES 1.

FSAR, Scction 15 Q1@feERIb3 l

l l

l l

l l

MARK UP OF NUREG 1431 BASES B 3.4 5 5/15/97 L

O 3.4.1-2 I

INSERT SR 3.4.1.4 i

f~'

This SR is modified by a Note that allows this SR to be performed by RCS flow calibration after each refueling prior to THERMAL POWER exceeding 75% RTP. The determination of RCS flow through a precision heat balance is not required prior to entry into MODE 1 because RCS flow l

indication is available (RCS flow meters), RCS flow is calculated prior to exceeding 75% RTP l

'and the surveillance from the previous cycle is still current The precision heat balance flow rate surveillance is typically performed after reaching full power following a refueling outage and suitable plant conditions are established.

1 l

t I

y l

l 6

i l

l 1

I e

i-

CHANGE NUMBER JUST1FICAT10N but would limit the exception to prior to entering MODE 2.

This change is consistent with traveler 400-00.- 776.2t#,

d) f, f,//g 3.4 36 SR 3.4.13.1 and ACTIONS for LC0 3.4.15 are revised with the addition of a note per traveler TSTF 116,"~;

1.

The note addresses the concern f) f. f,/3-2 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 surveillance provides an exception for operation at less than steady state conditions.

The RCS water inventory balance will only be allowed to be deferred for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after re establishing steady state conditions.

3.4 37 The primary to secondary leakage limits are revised per Callaway OL Amendment No. 116 dated October 1. 1996.

3.4 38 tent with traveler TSTF 105, the details on a by which '

the RCS is verified are moved f 3.4.1.4 to the Bases.

Moving this information lows the use of precision heat balances, elbow taps.

er acc-thods in order to perform this verificat' nd is consistent with the NU ev. 1 philos moving clarifying information and descriptive s out

' @ T.$;/-l Convenion % par-iron'724leho TS to the Bases s g.j., jy Q

.4.11 would re$ A.

Enclorare 3.4-39 The shutdown requirements of ITS quire the plant to reduce T,., to < 500*F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, rather than go to MODE 4, to address che concern of entering [COMS] LC0 3.4.12 Applicability with inoperable PORVs. For consistency, the shutdown requirements of ITS 3.4.16 are al o revised to allow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reduce T_ to < 500*F.

This change is c nsistent with traveler TSTF 113M8 gA-f] 8 2A //'5 m,w-;2?%

3.4-40 onsistent with traveler "C: 00.Vthe Note t'o SR 3.4.1.4 wouM

$ S. 4 / -/2.

mo ~ ied to provide additional time to perform an RCS precis' flo rate surement.

The time allowed would be changed fro 4hourstg 7 days.

's change is acceptable because other ind' ion of RCS flow is available 3.4.1.3, RCS total flow meters) d additional time norr. ally would be quired to establish plan onditions suitable for ti... precision heat (baR ce. Since this ameter does not nor ally change significantly and flow me s can be used in the interim.

there is no need to perform t within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period specified in NUREG 1431 Rev.1. The 7 yp d provides sufficient time to establish steady state p t thermohydr ic conditions and obtain equilibrium xenon.

I. addition, the THERMA WER specified in the Note would be cha d from the generic value in kets (90 RTP) to 95% RTP. Thie hange is acceptable because it specif1 a power level in better reement with current operating procedures for p

1. rming a

/

preci n heat balance.

Current TS do not specify a power level y

g, measurement. [ g,,,q; p g I

t

,s,

,,,3 TN(GM G b) Comparison Table 3.4 41 Not applicat'e to Callaway.

See Conversion (Enclosure 6B).

JUSTIFICATION FOR DIFFERENCES - TS 6

5/15/97 l

CHANGE NUMBER JUSTIFTCATION i

l I

3.4 49 LCO 3.4.12. "[COMS]", 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 $2f./2-/

being credited to meet the LCO. The proposed change adds the word

" required" to the Surveillance to exempt its performance if[ ggg equipmenttobetestepsgp}beingusedtomeettheLCO.VInaddition.y,4,994 an @ editorial change #d!Mb4ade. The LCO requirement presentation was c arified.tfA fie te o :)

3.4.

.6 w 's r 15ed 0 -ep C r

u~~

be t" wit "re ired o be erf rmed" si ce he i

f pe' "

men at e is pprop iate ere cons' t t

't t

S gg1-g w p p m ytp -tra p > w y e,a p y 92. w -1 3.4 50 This change is consistent with current TS SR 4.4.9.3.3.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l

frequency applies to vent pathway (s) that are not locked, sealed. or otherwise secured in the open position. The wording added to ITS SR 3.4.12.5 is also consistent with the format used in similar ITS 3.6 SRs. The 31 day frequency is also revised to be consistent with current TS SR 4.4.9.3.3.

3.4 51 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 6B).

3.4-52 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 6B).

.g.ssa

.rm egr 2.+.r3 k c-3.4-ooq Wo}- ag/rulle de C>lla~y. J'ce Converson 6 3

S?+-s+

% Ale [Encio.ruca U).

b c-3. 4-6s3 x

3 4-M u

3.+.rr (c A)

{Q 3. Y. / -Q AA l

JUSTIFICATION FOPS DIFFERENCES TS 8

5/15/97

Q 3.4.1-2 INSERT 3.4-55(6A).

3.4 55

'ITS 3 4.1.4 and its Bases are revised to additionally require the RCS flow be calculated prior to exceeding 75% RTP after each refueling. Tais is consistent with the CTS. A determination of RCS flow through a precision heat balance is not required prior to entry into MODE 1 because RCS flow indication is available

' (RCS flow meters), RCS flow is calculated prior to exceeding 75% RTP, and the surveillance from the previous cycle is still current.

i e

r i

i i

I

{V v

redr.rrehjp_.)

me d

'~r ver p r.y y u t + y DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBEL DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.4 3 The primary to secondary leakage limits are revised per No No No Yes Callaway OL Amendment No. 116 dated October 1. 1996.

3.4-38 r w h+--t un tr3,e;;,- T;Tr-;cs, um ate,b g, it

-Yee.

4es-W h

7 Q L, ohjd }dx RG Uuw soie is vetiikd Eii ie.;d u

j

.r Ms Me Me $ 8,4N u vra.m a.*. 4.

w v.s 3.4 39 The shutdown requirements of ITS 3.4.11 would require the Yes-/f-Yes Yes go to MODE 4. to address the concern of entering [COMS]

7

,[ r m h $jg plant to reduce T,.,to < 500'F within 12 hcurs, rather than g ZM a

LCO 3.4.12 Applicability with inoperable PORVs. For consistency, the shutdown requirements of ITS 3.4.16 are also revised to allow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reduce T, to < 500*F.

This change is consistent with traveler TSTF-113.

3.4-40 The Note to SR 3.4.1.4 would be modified to specify a No - See CN 3.4-51.

No - See CN 3.4-34.

Yes M 3I~ "

plant-specific reactor power and to provide additional fVo h C#

time to perform an RCS precision flow rate measurement.

3 g-t r 3.4-41 LCO 3.4.1 is revised to reference Tables 3.4.1-1 and Yes - Allowance No No No 3.4.12 for RCS total flow rate limits for DCPP Units 1 added per Amendment and 2 respectively.

60/59.

3.4-42 An exception to SR 3.4.14.1 frequency to leak test Yes No No No PIVs 8802A. 88028 and 8703 has been added. This change is consistent th the OCPP current TS.

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

-Ne-[er 3.4 44 Steam generator levels for MODES 3.

and 5 are specified No No Yes g g g_.7 to ensure SG tubes are covered.

R. u " 27 current TS did not ensure tube coverage.

CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97

CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 Page '7 of -7

[

SECTION 3.4 DIFFERENCE FROH NUREG-1431 APPLICABILITY NUMBER.

DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK l CAllAWAY r D4-b c - ALL-MS 3.4-51 The Note for SR 3.4.1.4 is remov rd. This is consistent Yes No No No with DCPP CTS 4.2.3.5.

DCPP conjuctsameasuredRCStotal flow rate verification on aphonth frequency.

3.4-52 Consistent with traveler ^C 51. b k e oncer$ih-No - See CN 3.4-45.

Yes No - See CN 3.4-45.

No ke CN S 5 accumulator isolation is moved from the Applicability to g

the LCO.

r-euede) E,- c{ar-T-fy odis

/

3'.-l-53

_~L'NSEA'1' 3'. -l -5~3' f2S Yo fer

' It/C.Y.4 zW/

es

.TA-s+

rasexr 1.+-s4 y'g 3 A -srb e) a3.v.i-2j.

r

.3.y - s s w

t i

k h

l CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97:

O 3.4.1-2 INSERT 3.4-55(6B)

TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO COMMANCHE WOLF CREEK CALLAWAY CANYON PEAK 3.4-55 For Callaway ITS 3.4.1.4 and its Bas'es are revised to No - See No - See No - See Yes additionally require the RCS flow be calculated prior CN 3.4-51 CN 3.4-34 CN 3.4-40 to exceeding 75% RTP after each refueling.

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.4.5-2 APPLICABILITY: CA, WC REQUEST:

ITS SR 3.4.5.2 (also SR 3.4.6.2 and SR 3.4.7.2) (Callaway)

Change 1-15M Comment: The sections of the ITS use the phrase "or equivalent" yet the term is not explained in the change or in the ITS Bases. According to the information provided narrow range level is used at the higher temperatures (Modes 3 and 4) and wide range level is used at the lower temperatures (Mode 5). If "or equivalent" means using the wide range at higher temperatures and the narrow range at lower temperatures are the levels specified applicable at the different temperatures? If not, what are the equivalent levels to the values specified in the ITS and how were they determined?

FLOG RESPONSE (original): At Callaway, the top of the highest steam generator (SG) tube is 344 inches above the tube sheet. The wide range instrumentation provides level indication from 7 inches above the tube sheet (0% indication) to the moisture separators (a range of 559 inches). The narrow range instrumentation provides level indication between 438 and 566 inches above the tube sheet for its 0-100% indication (the use of a common upper tap results in 100% level indication on both wide range and narrow range nominally being at the same 566 inches above the tube sheet). A calculation was performed to correlate the top of the highest tube to the wide range scale for MODE 5 conditions (the wide range instrumentation is calibrated for cold conditions), with margins added in for instrument loop errors and readability, resulting in the specified 67% wide range level. A minor error in the calculation was corrected, resulting in the specified 66% wide range level value cited in the attached pages for Callaway.

Since the zero reference for the narrow range level instrumentation is nominally 96 inches above the top of the highest tube, the 4% value specified for MODES 3 and 4 was chosen since it is used throughout the EOPs for heat sink indication and is familiar to the operators. In the main control room there is one Class 1E wide range level indicator per SG and there are four narrow range level indicators per SG, of which three per SG are Class 1E. The "or equivalent" phrase would allow the use of wide range level instrumentation in MODES 3 and 4 in the unlikely event all narrow range level instrumentation were unavailable for a required SG; in MODE 3 this unlikely scenario would result in ITS LCO 3.3.3 non-compliance and would invoke Required Action (s) under PAM Instrumentation. Conversely, the "or equivalent" phrase would allow the use of narrow range levelinstrumentation in MODE 5 if the one wide range level indicator per SG were unavailable. This flexibility is similar to the approach under which Vogtle was licensed wherein their MODES 3-5 RCS specifications required SG water level to be above the highest point of the SG U-tubes. We are specifying water levels that ensure the same, yet allow the use of all available instrumentation. Before the "or equivalent" instrumentation were used in a given MODE, process measurement effects on the alternate instrument's calibrated span would be considered. Due to the unlikely event of either scenario presenting operational limitations, given the reduced RCS loop requirements in MODES 3-5 l

and the instrumentation redundancy, we do not see the need for a pre-determined correlation

[

between the wide range and narrow range level indications; however, we reserve the right to l

exercise that option should the need arise.

l Wolf Creek reviewed this particular comment for applicability to Wolf Creek and concurs with the use of the phrase "or equivalent"in the ITS and ITS Bases. Wolf Creek believes that it is

appropriate to change their plant-specific value to 6% narrow range (including uncertainties) since it is used throughout the Emergency Operating Procedures (EMGs), it has operator awareness because of the EMG familiarity, and ensures an SG water level approximately 100 inches above the top of the highest SG tube. Wolf Creek has done a review of the drawings and design documents and has determined that for MODE 5 conditions (the wide range instrumentation is calibrated for cold conditions),66% wide range level corresponds to the top of the highest tube, with margins added in for instrument loop errors and readability. The need for flexibility to use either narrow range or wide range indication is most evident when placing the SGs in wet layup conditions. The narrow range instruments are "jumpered" to indicate a constant 50% level. This precludes a feedwater isolation signal at approximately 78%. The operators use SG wide range indication to maintain and monitor SG level. Additionally, the narrow range instruments are calibrated for normal operating pressure and temperature conditions while the wide range instruments are calibrated for shutdown conditions.

The Callaway and Wolf Creek ITS Bases have been modified to explain the "or equivalent" phrase.

FLOG RESPONSE (revised): ITS 3.4.5 and ITS 3.4.6 have been revised to refer only to the narrow range SG level indicators (4% for Callaway,6% for WCGS). ITS 3.4.7 has been revised to refer only to the wide range SG level indicators (66%). The "or equivalent" phrase has been deleted. The Bases for ITS 3.4.7 have been revised to reflect that any narrow range level indication above 4% for Callaway (6% for WCGS) would ensure the top cf the SG tubes are covered. This is a valid statement since MODE 5 temperature conditions will not induce a 100 inch level measurement error on the narrow range. Since this is a revised response, all of the required change pages from Reference 5 of the cover letter are attached.

ATTACHED PAGES: 0, CTS 3/4.4 - ITS 3.4, pages, 3/4 4-2,3/4 4-4, and 3/4 4-5 A, page 3 Enclosure SA, pages 3.4-9, 3.4-11, 3.4-12, and 3.4-13 Enclosure SB, pages B 3.4-26, B 3.4-32, B 3.4-33, B 3.4-34, B 3.4-36, B 3.4-37, and B 3.4-38 A, page 7 B, page 5 2

i

l

/ ggVISIO REACTOR COOLANT SYSTEM 2

HOT STANDBY.

9 LIMITING CONDITION FOR OPERATION 3.4.1.2 At least M of the reactor coolant loops listed below shall be

/-/I-18 OPERABLE and at least two of these reactor coolant loops shall be in eperatieg:"

a.

Reactor Coolant Loop A :nd it: :: = : kt:d :t::: ;- e6t

=d

.INTE#T A

l-6l-LG b.

Reactor Coolant Loop B-=d it: nn:i:.t:d :t:= :;=r:t= =d m ete cre? rt ;r 7, c.

Reactor Coolant Loop C :-d 't:

n::i:::d tt:= ;=r:tr =d r=:tr =:hc.t p e.p, and d.

Reactor Coolant Loop D, =d it; :.n::ict:d :ter ;=; rete, end rn:tc.,

. d = t p....,..

~

APPLICABILITY: MODE 3.

ACTION-iredreactorcoolantloop{0,

/-/Y-N-a.

With-h n ;h.. th.... r restore the required loo OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

/EMd b.

With only one reactor coolant loop in operationy -::t :

t'.-

A

/-/I-M hn; t: :; r ti r _ith' 72 he. ; ?

th...,... h..

p,... I..

.m

~7-W g

h!

I ersbole or ZNSW C khU Withvno reactoY'* eooYnt loop in operation,Vsuspend, all operations

/-/9p ou c.

involving a reduction in boron concentration of the Reactor Coolant System)and Jr.:di 4 - initiate corrective action to return-ne-ona j

;r# ;i reactor coolant loop toAoperation.

OfE/Adl.E.t M aarand l

SURVEILLANCE REOUIREMENTS

4. 4.1. 2.1 At least the aDove required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power svailability.

narrow

4. 4.1. 2. 6 e required steam generators.shall be determined OPERABLE by veri fying seco dary side range water leyel.to be greater than or equal to f_jg g f/,

t 'rast on e r12hoprs/

streg) '

e retusret

,.v.a..t.a a

ii in operation

/~ M-d

-d c' =hti-b "i c reactor coolant loops shall be ver f ed

/-4/-/ 6 t= s ; xt at least once pe.r 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

p hiboftraNon oer ? bourfero*p)

&,$=Q renave coolant pumps may beV::=:r;u d-for up tc 1;hourVprovided:

/"dd" "All reac*

1) no operations are permitted that would cause dilution of the Reactor

/-/ dr-'~4 Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F tielow saturation temoerature.

/~OY~~b "h: I;= ici ~ a t D x;;.i s pc.;ifi s tien 2.~.C.4

/

T reae4so-cco/arr/ fu - l4$ g CALLAWAY - UNIT 1

'/4 4-2 sLll nd Ia.rhrhof WHA o5 He reco-olA c.r cold ley n

-}eiy e,.-Ince :G.~14 PF~ un le e-ecc/g wder -lemfern-face & e e4.cleam or-

\\

i.e G So* f a h ve eoe4 & He c f co/d

/es h i y a ra-lu -a r.W

! -v

.? ~I 3 t ng 3

,9

~

a

'~

REACTOR COOLANT SYSTEM s

5.5

• SURVEILLANCE REOUIREMENTS

4. 4.1. 3.1 The required reactor coolant pump (s) and/or RHR pumps, if not in operation,.shall be determined OPERABLE once per 7 days by verifying correct breaker alignments'and indicated power availability.

"narrant I

-s 4.4.1. 3. 2 ine - ired steam generator (s) shall be determined OPERABLE by verifying secondary ide *wheekrange water level to be greater than or equal to

[~6'N y, g,7 r

479.1.3.3 A '. least one reactor co lant or RHR loop shall be verified in operation-eed-e.cc 'atir.; ca.;ter

,;1:.rt-at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

/-g/-/_G

_/

f J

e

-i l

i d

=

\\

l CAU AWAY - UNIf 1 3/4 4-4 I

..d..-

1 0-REACTOR COOLANT SYSTEM y",,

COLD SHUTDOWN - LOOPS FILLED LIMI1ING CON 01T10N FOR OPERAT10N At least one residual heat removal (RHR) loop shall be OPERABLE and

/-4 /-2 S

3. 4.1. 4.1 in operation and either:

One additional RHR loep shall be OPERABLE #, or a.

b.

The secondary side' at" 1avel of at least two_ steam generators an-MW of th_e wide range.

/-/3-M shall be greater j

NM APPLICABILITY: MODE 5 w th rea ACTION:

With one of the RHR loops inoperable and with le s than the required a.

steam generator level, immediately initiate corrective action to return the inoperable RHR loop to OPERABLE status or restore the re uired team generator level as soon as possible.

KHf igerej/s or With no RH loop in operation, suspend all operations involving a

/-/4-/ '/

8 reguiP V

b.

reduction in boren concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.

j OfEC4/l2.r/nlur N SURVEILLANCE REOUIREMENTS t

4.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 Ecurs.

4. 4.1. 4.1. 2 At least one RHR loop shall be determined to be in operation-aM- /-4/-/ G

': tin; ::ctr :;;;;nt at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(Wb $JGU A gj_

1. 0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.

1. 1. A reactor coolant pump shall not be startegunless the secondary water temperature of each steam generator is less than 50*F above each of the

,,- 8 Asur er,ed Reactor Coolant Syst emperatur s.

"TheRHRpumpmafo' eve old legNr up. to

-f urVprovided (1) no operations /~84"N

/- / (p-A are permitted that would cause dilution of the Reactor Coolant System coron ure is maintained at least 10"F concentration, and (2) core outlet temper belnw saturation temperature.

l~b?~lS

1. "2~/\\//EA*7" 8

~

N RC.Ccold wf4f a e v M-e.6_7 # [ ' !~

~M CALLAWAY - UN11 1 3/4 4-5

/

./

CHANGE MREEE 82iG DESCRIPTION n.~

1 12 M

The Actions are changed to separate the required actions for only one required RHR loop OPERABLE and no required RHR loops OPERABLE. These revised Actions are consistent with the Actions which are required under this LC0 in i

NUREG 1431 Rev. 1, and are more conservative than current required Actions.

1 13 H

An additional restriction is placed on the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowance to remove all RHR pumps from operation. This restriction precludes further draining of the RCS which is an acceptable,' conservative action. This change is in conformance with NUREG 1431 Rev. 1.

1 14 LS 22 and Action b are revised to require oops OPERABLE w1 s in opera n the rod control system is capable of al and one loop in

/

operation whe od control syst a able of

/

rod wal. This change is consistent with 31/

.v. 1.

ZNS W 2h-3'A d? 3.+.f--l 1 15 M

A steam generator (SG) level corresponding to 10% of the wide range does not cover all of the SG tubes. To qualify as a valid heat sink, the tubes must be covered. This is a more restrictive change. [Four percent of the narrow range span is specified at the higher temperatures of H0 DES 3 and 4 whereas474 of the wide range span is S 5.f.F2 specified for MODE 5.

th values ensure SG tubes re covered. The E0Ps cite he 4% narrow range level to ensure heat sink adequ y.]

b$ *le 1-16 A

Consistent with the intent of traveler TSTF 153, this change revises the note that permits up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> "deenergization" of RCP/RHR pumps. The revised wording clarifies the intent of the note to allow the pumps to be

" removed from operation" instead of "deenergized", thus permitting other means of removing tha pumps from service.

With this change the pumps are not recuired to be deenergized to use the note (e.g., the pumps may be isolated, etc.). The change is considered to be administrative because from the standpoint of providing an exception to the LCO requirements (to maintain the operability and operation of the pumps), the revised wording is equivalent.

Not applicable to Callaway. See Conversion Comparison f,

1 17 Table (Enclosure 3B).

1-18 Not used.

I m

-.wm y.

RCS Loops -H0DE 3 3.4.5 e

n

,n,.,

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.5.2 Verify steam generator secondary side 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

_ A3.4 44 water levels are 2 iM e

g y,4 g 2 for required RCS loops.

SR 3.4.5.3 Verify correct breaker alignment and indicated 7 days i

power are available to the required pump that 1s not in operation.

l 4

s.

7 MARK UP OF WOG STS REV 1 (NUREG 1431) 3.4 9 5/15/97

g

.m._g%-#*e.m=.,-W-de 4h e-

=*-

RCS Loops -MODE 4 3.4.6 m.i ACTIONS (continued)

COEITION REQUIRED ACTION COMPLETION TIE C.

T.; r;;; ired = leei, 0.1 0; ir, = 5.

24 bur; a3.4 02:

1747 1;.

M Ta r; wired =

14 ; 1, 4 701;.

F. Required RGS-er-Rie lG.1 Suspend all' operations Immediately 03.4 02P loops inoperable.

. involving a reduction of RCS boron

. GL

~

concentration.

No RCS or RHR loop in E

operation.

p.2 Initiate action to Immediately restore one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1

i l

SR 3.4.6.2 Verify SG secondary side water 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.4 44--

levels are :t +74 for g.g,4,g:.2 required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated 7 days power are available to the required pump that

.~

is not in operation.

i

. MARK UP OF WOG STS REV 1 (NUREG 1431) 3.4 11 5/15/97 l

RCS Loops -HODE 5. Loops Filled

,r 3.4.7 y

a wn, 4

v, 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops-HODE 5. Loops Filled LCO 3.4.7 One residual heat removal (RIR) loop shall be OPERABLE and in

[

operation, and either:

a.

One additional RHR loop shall be OPERABLE: or j

b.

The secondary side water level of at least - steam 3BL generators (SGs) shall be 2 r3;4-44 I

f--2 e,

...................................d

............... -.... n..

1.

The RIR pump of the loop in operation may be t.: ei Tited M 43.4 01.:d for s 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:

a.

No operations are permitted that would cause reduction of the RCS i

boron concentration; and 1

1 0

b.

Core outlet temperature is maintained at least 10*F below

~

saturation temperature.

2.

One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHR loop is OPERABLE and j

in operation.

7ED:

1 3.

No reactor coolant pump shall be started with one-eMmwe 3 RCS cold leg temperatures-s eMaf M unless the secondary side water r B.PS s

}

temperature of each SG is s E*F above each of the RCS cold leg

B' l

temperatures.

j 4.

All RHR loops may be removed from operation during planned heatup to H00E 4 when at least one RCS loop is in operation.

I i

APPLICABILITY:

H00E 5 with RCS loops filled.

4 3

.D 4J'

..~

MARK UP OF WOG STS REV 1 (NUREG 1431) 3.4 12 5/15/97

-e me, aw--*-Ag-_,

RCS Loops -MODE 5, Loops Filled 3.4.7 j.

.~n ACTIONS 1

CONDITION REQUIRED ACTION COMPLETION TIME I

A.

One RHR loop inoperable.

A.1 Initiate action to restore Immediately a second R E loop to 81 0 OPERABLE status.

Required SGs secondary QR side water levels not within limits.

A.2 Initiate action to restore Ismediately required SG secondary side I

water levels to within limits.

1 B.

Required Rm loops B.1 Suspend all operations Insediately inoperable.

involving a reduction of RCS boron concentration.

Ei ale No RE loop in operation.

B.2 Initiate action to restore Inmediately one RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREEKTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.7.2 Verify SG secondary' side water level 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

-3.4 44 is a W4 inr uired SGs.

44 %

A 3.4. f-2 SR 3.4.7.3 Verify correct breaker alignment and indicated 7 days power are available to the required RHR pump that is not in operation.

MARK UP OF WOG STS REV 1 (NUREG 1431) 3.4 13 5/15/97

_. _. _. _. _ ~. _. _. _

_ _ _ ~. _... _

l' RCS Loops HODE 3

,~-

B 3.4.5

i. y,,

BASES ACTIONS D.1. D.2. and D.3 (continued)

If twe RCS loops are inoperable or no RCS loop is in operation, except as during conditions permitted by the Note in c

section, all CRDHs t

t M i craigi;;d by opening the RTB or de energizing HG

• • t Q}fra A 3 W *^~l j

All operations involving a reduction of RCS boron concentration N gg,/

i must be suspended, and action to restore one of the RCS loops to OPERABLE status and operation must be initiated. Boron dilution i

j requires forced circulation for proper mixing, and l

g-.ir.; tk =; er i.ar;;zir.; tM = ;;t; i.

removes the possibility of an inadvertent rod withdrawal. The 1mmediate Completion Time reflects the importance of maintaining operation for heat removal. The action to restore must be l

continued until one loop is restored to OPERABLE status and j

y operation.

l l

SURVEILUNCE SR 3.4.5.1 REQUIREENTS This SR requires verification every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the required loops are in operation. Verification includet flow rate.

temperature, and 5 pump status monitoring, which help ensure that forced flow is providing heat removal. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient considering other indications and alanas available'to the operator in the control room to monitor RCS loop performance.

SR 3.4.5.2 SR 3.4.5.2 requires verification of SG OPERABILITY. SG OPERABILITY is verified by ensuring that the secondary side narrow range water level is a m 6 for requir RCS loops. If the SG secondary side narrow range water level 1 6 8M~2

<M he tubes may become uncovered and the associated loo say not capable of providing the heat sink for removal of the decay hea. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adequate in view of other ndications available in the control room to alert the operato to a loss of SG level.

^

(contin MARK UP OF NUREG 1431 BASES B 3.4 26 5/15/97

~.

INSERT B 3 6

Q 3.4.5-2 1

~ -

,i

.,a

. jfj!

i

. The wide range levelinstrum tion m

t.,ed in MODE 3 in the event all narrow range

'levelinstrumentation wer available for a req '

steam generator.

{

f i

h&LETEb r

i 4

ww l

I l

l l'

RCS Loops H00E 4 B 3.4.6 L;<n BASES (continued)

SURVEILLANCE SR 3.4.6.1 REQUIREMENTS This SR requires verification every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that one RCS or RHR loop is in operation. Verification 3 includes flow rate.

temperature, or pump status monitoring, which help ensure that forced flow is providing heat removal. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient considering other indications and alarms available to the operator in the control room to monitor RCS and RHR loop performance.

SR 3.4.6.2 SR 3.4.6.2 requires verification of SG OPERABILITY. SG OPERABILITY is varified by ensuring that the secondary side narrow range water level is :t M gg If the SG secondary side narrow range water level is

<MM tubes may become uncovered and the associated loop may not be capable of providing the heat sink necessary for removal o1 decay heat. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adequate )n view of other indications available in the control room to llert the operator to the loss of SG 1evel.

ff}

Q.T.W4

' SR ' 3.4.6.3 Verification that the required pump is OPERABLE ensures that an additional RCS or Rm pump can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation.

Verification is performed by verifying proper breaker alignment and power available to the required pump. The Frequency of 7 days is considered reasonable in view of other administrative controls available and has been shown to be acceptable by operating experience.

REFERENCES None-E v.c: M ~ ~ M wm O-MARK UP OF NUREG 1431 BASES B 3.4 32 5/15/97

.. ~.....

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

. _.m 1

INSERT B 3.4-Q 3.4.5-2 n;.

..ar a i

W.

The wide range levelinstrume tion be used in MODE 4 in the event all narrow range i

I levelinstrumentation wer available for a uired steam generator.

j:

l bFLET&b l

k S

6 4

I

\\

I

l RCS Loops - MODE 5, Loops Filled

,.4, B 3.4.7

@)

B 3.4 REACTOR C00UNT SYSTEM (RCS)

B 3.4.7 RCS Loops - MODE 5,- Loops Filled BASES BACKGROUlO In MODE 5 with the RCS loops filled, the primary function of the reactor coolant is the removal of decay heat and transfer 3 this heat either to the steam generator (SG) secondary side coolant or the component cooling water via the residual heat removal (RM) heat exchangers. While the principal means for decay heat removal is via the Rm System, the SGs are specified as a backup means for redundancy. Even though the SGs cannot produce steam in this MODE, they are capable of being a heat sink due to their large contained volume of secodry water. As long as the SG secondary side water is at a lower temperature than the reactor coolant.

heat transfer will occur. The rate of heat transfer is directly proportional to the temperature difference. The seconaary function of the reactor coolant is to act as a carrier for soluble neutron poison, boric acid.

In MODE 5 with RCS loops filled, the reactor coolent is circulated by means of two RR loops connected to the RCS, each loop containing an Rm heat exchanger, an RE pump, and appropriate flow and temperature instrumentation for control, protection, and indication. One RR pump circulates the water through the RCS at a sufficient rate to prevent boric acid stratification The number of loops in operation can vary to suit the operational needs. The intent of this LCO is to provide forced flow from at least one RR loop for decay heat removal and transport. The flow provided by one Rm loop is adequate for decay heat removal.

The other intent of this LCO is to require that a second path be available to provide redundancy for heat removal.

The LCO provides for redundant paths of decay heat removal capability. The first path can be an RHR loop that must be OPERABLE and in operation. The second path can be another OPERABLE RHR loop or maintaining two SGs with secondary side water levels above We to provide an alternate method for decay heat removal 44%

$ 2492 (contin MARK UP OF NUREG 1431 BASES B 3.4 33 5/15/97

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

RCS Loops HODE 5. Loops Fillea B 3.4.7 1

+ +.

BASES (continued) i APPLICABLE In MODE 5. RCS circulation is considered in the determination of SAFETY ANALYSES the time available for mitigation of the accidental boron dilution event.

"e.'"n ic~ps previi tt.is circul;tica.

~

j r..

i 4

)

\\

i 1

h l

J 4

4 i

RCS Loops - H0DE 5 (Loops Filled) Fev;.t;; iirt.ified ir, tra =0 l

,.c

__,._x,__

~.,.,.._....___.__,___x__....v......-....n.n...,

...m 3

1 I

r 6(o%

+92 ]

1 LCO The purpose of this.

is requ re that at least one of the R m loops te OPERABLE and in operation with an additional RE loop OPERAE or two SGs with secondary side '

water 3

level 2 &#

One RHR loop provides sufficient forced circu ation o per rm W safety functions of the reactor j

coolant under these conditions. An additional Rm loop is i

required to be OPERABLE to

. single failure considerations.

However, if the standby Rm 1 is not OPERABLE, an acceptable alternate method is two SGs th their secondary side 1

water levels a 17 $. Sho d the operating RHR loop fail, the

}

SGs could be us to remve he decay heat

- o l

M gg rwer f.T.+-2+

e.T.+.92 Note 1 permits all RHR pumps to be i crersi;cd <.,#

s 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period. The purpose of the Note is sJ t..;

j to permit tests

~

..c.m o..

, s.O

+m x<-

M,.. _ _ isi; red te v;11detc v;rieus e cidcat er.elyscs mm v.

.~

m_

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...,mu_

_1._._1..._.eo s i. 2.._m_

2._,__

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.. ysi, vi

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j pregre.;;, is tre v;11detier. ;f red drey ti;;e; irir,; ;;1d 3

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A L.._ A. A.L _

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(continued) i j

MARX UP 0F NUREG 1431 BASES B 3.4 34 5/15/97 4 -

v ~-

~

.s a

w

--.*.p

-.4

--e#

+.

INSERT B 3.4-34 Q 3.4.5-2

. (C';'.

O e

ion be u in M 5 if t l

As riv~n r R.Laa e, ay namw c.ye level inkcahn love

}

n 4% wrll euun +4a J'c hlar are covemt.

\\

i

-%D

~l

_ ~ - - - -

-. ~ _.

RCS Loops MODE 5. Loops Filled B 3.4.7 BASES LCO Rm pumps are OPERABLE if they are capable of being powered and (continued) are able to provide flow if required. An OPERABLE SG can perform as a heat sink 7

when it has an adequate water level and is OPERABLE in accordance with the Steam Generator Tube Surveillance Program.

i APPLICABILITY In MODE 5 with RCS loops filled, this LCO requires forced circulation of the reactor coolant to remove decay heat from the core and to provide proper boron mixing. One loop of R R provides sufficient circulation for these purposes. However, one additional RR loop is required to be OPERA 8LE, or the secondary side water level of at least SGs is required

t 2, Q 3.+,F2 Ope t on in other MODES is covered by:

LCO 3.4.4, "RCS Loops MODES 1 and 2":

LCO 3.4.5, "RCS Loops MODE 3";

LCO 3.4.6, "RCS Loops MODE 4':

~

LCO 3.4.8 "RCS Loops MODE 5. Loops Not Filled *:

LCO 3.9.5, " Residual Heat Removal (RM) and Coolant Circulation - High Water Level" (MODE 6); and LCO 3.9.6 " Residual Heat Removal (RM) and Coolant Circulation - Low Water Level" (MODE 6).

ACTIONS A.1 and A.2

, fat,%

& 3.+.92 If one RM loop is inoperable and the required SGs have secondary side water levels < FM redundancy for heat removal is lost. Action must be initiated immediately to restore a second RR loop to OPERABLE status or to restore the required SG secondary side water levels. Either Required Action A.1 or Required Action A.2 stil restore redundant heat removal paths.

The immediate Completion Time reflects the importance of maintaining the availability of two paths for heat removal.

j B.1 and B.2 If no RM loop is in operation, except during conditions permitted by Notel 1 M, or if no loop is OPERABLE, all (continued)

MARK UP OF NUREG 1431 BASES B 3.4 36 5/15/97

~

i RCS Loops H00E 5, Loops Filled B 3.4.7 BASES ACTIONS B.1 and B.2 (continued)

. operations involving a reduction of RCS boron concentration must be suspended and action to restore one Rm loop to OPERABLE status and operation must be initiated. To prevent M boron dilution, forced circulation is required to provide proper mixing. ;ri pr;;;rv; tt.e ;rigir, t; critic;11ty ir, tt.i; t.,p; ;f ;p;retter.. The immediate Completion Times reflect the importance of maintaining operation for heat removal.

SLRVEILLANCE SR 3.4.7.1 REQUIREENTS This SR requires verification every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the required loop is in operation. Verification includes flow rate, camperature, or ptmp status monitoring, which help ensure that forced flow is providing heat removal. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient considering other indications and alarms available to the operator in the control room to monitor RHR loop performance.

SR 3.4.7.2 g g e/,

Verifying that at least two SGs are OPERABLE by ens i

secondar side necrow rangewaterlevelsarez&#

$ 34:6-2 ensures an alternate decay heat removal method 3 in the event that the second Rm loop is not OPERABLE.

If both RM loops are OPERABLE, this Surveillance is not The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> FrequeWey is considered adequate in view of othe indications available in the control room to alert the oper or to the loss of SG let al.

r^l M T S 2.+-17 Q 2 +. C - D-SR 3.4.7.3 Verification that a second Rm pump is OPERABLE ensures that an additional pump can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation.

Verification is performed by verifying proper breaker alignment and power available to the RHR pump. If secondary side.

M water level is a W g in at least two SGs, this

$ 345-2 4"4 (continued)

MARK UP OF NUREG 1431 BASES B 3.4 37 5/16/97

.~.

~-

INSERT B 3.4-37 Q 3.4.5-2 j

t.... -

so) s he owr lev

.stru ntatio lay b sed ir OD if th ne wi red

)

cator ste geneJKor wer nava' le.

/

^

W As rhwn in deSennea 3, an, narno.v rage /eva/ inhcosn sLove 4% writ enrura f(a J's +ukt m cwem/.

.-. :. ?

l 4

I l

I l

l 4

r l

RCS Loops H00E 5 Loops Filled B 3.4.7

..u-,,

BASES l

SURVEILLANCE SR 3.4.7.3 (continued)

REQUIREMENTS Surveillance is not needed. The Frequency of 7 days is considered reasonable in view of other administrative controls l

available and has been shown to be acceptable by operating l

experience.

j REFERENCES None-E s.

rb8-et.

sk Liu Baok.J%m Gervrahe,

/

s E8801 (A,8,q b)."

Q3.ss%2

+f*

[

l a

t i

MARK UP OF NUREG 1431 BASES B 3.4 38 5/15/97

89-

.genk..a-mae.!!mm-CHANGE NUMER JUSTIFICATION t9 3.4 42 Not applicable to Callaway. See Conversion Comparison Table Rh (Enclosure 68).

41 3.4 43 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

Steam generator level r MODES 3. 4. and 5 are specified to e Aure SG O*iss tubes are covered.

2111 ; current TS did not ensure tube

$ 7. f. 5'-Q l** ? S, verage.

0,}e u$

~

BITS 3.4.12 has been revised to move the No:e for Required Action B.1 3.4 45 regarding CCP pump swap operatio and theFApplicability St fer g 7,f:/2-Q rger/Ty" accumulator isolation to the L

. M d " " W '- t =;1 r E 01 O f.y.n

.:; 1.,-/lant specific time allowances for exceeding the LCO's number

'7'48#8 Ne M *ws of [ECCS] pumps capable of injecting into the RCS are incorporated [. as

> 58#M MMO discussed in CN 3.418]. Ne "ater d:tri' ri+"iti:::

t..

j

[ za gir.: t tt LT r: ;; :itt;d. u m rc :;; :;ri:tt'"

i w

w ' = 2t:t d =d:7 tu '_'"

LC4 te /**v'Y Aff,,

J.4 46.

Consistent with current TS 3/4.1.1.4, " Minimum Temperature for

{

Criticality," ITS LCO 3.4.2 and its Condition A and SR 3.4.2.1 are modified to refer to " operating" RCS loops. Adopting the current TS wording is acceptable since valid T,, measurements are not obtainable p, 9 for a non operating loop.

Qfy 3.4 47 ISTS SR 3.4.11.1 contains a Note which exempts the cycling of the block valve when. it is closed in accordance with Required Actions of Conditions B or E of LCO 3.4.11.

However. Required Action A.1 also directs closure of the block valve when one or more PORVs are inoperable and capable of being manually cycled. The SR Note should also exempt performance when the block valve is closed in accordance with Required Action A.1 as the block valve should not be opened when the PORV is inoperable. This change is consistent with NUREG 1430 and NUREG 1432 inasmuch as the block valve cycling is exempted under Canditions A, B. and E. {in:: ;-rr-te tb bb k v;h:':) i:

8 M.N-+

_......_,,,.wir;d ktier. A.1. *lfie Note to SR 3.4.11.1 will be 4 y gag revised to not require the surveillance performance if the block 4

g valve (s) is closed perC=ditier

• Sinc p; ;r t; tk block =h:3) j gg t r _ v;d in R viced Mtie,; ".2..,d C.O. tre arveil k ne== :t 5:

j

=+

mu= t% rdi ; ch=;; 're " ;t" t: "perf: xd" d-th: Ste, tre.cidi ;; Of 5" ~;.4.11.1 m, evned to eccc.--_ --d;t; tt,; C=diti:n-B-M E er--ti:n fThis change is consistent with traveler S96-eh7~#7F-g*

L.rNNAT-M '7A i

3.4 48 A note is added to ITS 3.4.8 ACTIONS indicating that entry into MODE 5 j

Loops Not Filled from MODE 5 Loops Filled is not permitted while LCO 3.4.8 is not met. The addition of this note is based on the performance of a plant specific LCO 3.0.4 matrix (see CN 102 LS 1 of i

the CTS 3/4.0 package). ;Q/Kg7-6A-78 g MJ--/

JUSTIFICATION FOR DIFFERENCES TS 7

5/15/97

v g 4 ;g 3 q g CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 Page 5 of 7

-mc&dJ

.ke h.pfaw

,f'f=.*v^e-}o SECT 10N 3.4 su e aeJi.e w aj.p n Pr.s y u.e.+ M DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBEF:

DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.4-3 The primary to secondary leakage limits are revised per No No No Yes Callaway OL Amendment No. 116 dated October 1. 1996.

3.4-38 cm %

n ;,3s y m ;c3, a a ;;n y,th;

-yes

-yee-

-yes-

-ye,.

M h A*Y'l~

ii.i..

u 0

3.4 39 The shutdown requirements of ITS 3.4.11 would require the

-Ves.-Mg -

Yes Yes plant to reduce T to < 500*F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, rather than g ryy g go to H0DE 4. to address the concern of entering [COMS]

7

[yg

$ 79,77_y m

p LCO 3.4.12 Applicability with inoperable PORVs. For 78M.

consistency. the shutdown requirements of ITS 3.4.16 are also revised to allow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reduce T, to < 500*F.

This change is consistent with traveler TSTF-113.

3.4 40 The Ncte to SR 3.4.1.4 woulti be modified to specify a No - See CN 3.4-51.

No - See CN 3.4-34 Yes Yes-M3Y" plant specific reactor power and to provide additior.al fv o h C Af r

time to perform an RCS precision flow rate measurement.

3.V-T T 3.4-41 LCO 3.4.1 is revised to reference Tables 3.4.1-1 and Yes - Allowance No No No 3.4.1-2 for RCS total flow rate limits for DCPP Units 1 added per Amendment and 2 respectively.

60/59.

3.4 42 An exception to SR 3.4.14.1 frequency to leak test Yes No No No PIVs 8802A. 88028 and 8703 has been added. This change is j

consistent with the DCPP current TS.

I 1

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

M 3.4 44 Steam generator levels for H0 DES 4 an - are specified No No

-Ne -[ef Yes to ensure SG tubes are covered The i;?! n; cur nt TS g g*g 7 did not ensure tube coverage.

CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97 J

4

]

ADDITIONAL INFORMATION COVER SHEET i

ADDITIONAL INFORMATION NO: Q 3.4.11-3 APPLICABILITY: CA, CP, DC, WC P

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.

i FLOG RESPONSE (original): TSTF-113 Rev. 4 revises the shutdown requirements of ITS l

3.4.11 to allow the plant to reduce T., to <500 F within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, rather than MODE 4, to i

address the concem of entering LCO 3.4.12 Applicability with one or more inoperable PORVs.

. The shutdown requirements of ITS 3.4.16 are also revised, for consistency, to allow 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reduce T., to < 500 F. ITS 3.4.11 Condition B and C Bases changes have been made to i

the Callaway submittal to reflect Rev. 4 of the traveler; no changes are required for any other plants'submittals. The FLUG continues to pursue the changes proposed by this traveler.

i I

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 3

4 i

of these initiallicense amendments, an attemate approach has been developed by CPSES l

j and DCPP which relies on the CTS, plant-specific information, and/or the NUREG but does not rely upon the traveler. This altemate approach is hereby providsd as an interim submittal to allow issuance of the initial license amendments for CPSES and DCPP. The changes which l

rely upon the traveler can be processed in subsequent license amendments following approval 4

1 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 368 F. Required Actions in STS 3.4.11 for one or both PORVs inoperable would bring the plant to MODE 4 (350 F). This could involve entering the COMS/LTOP LCO Applicability (ITS 3.4.12) with no 1

means to mitigate a cold overpressure event since RHR is just being aligned for shutdown cooling during this time frame.

Callaway and WCGS propose to terminate the shutdown tracks in ITS 3.4.11 at an RCS T.,

< 500 F, rather than 350 F. At T., < 500 F, 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 valves or ARVs) have a set pressure of 1125 psig. Operation in MODE 3 with RCS T., < 500 F renders the offsite release of radioactivity in the event of an SGTR extremely unlikely given: 1) the difference between the initial SG pressure for this RCS T., and the ASD/ARV set pressure; 2) the secondary side 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 Callawr.y corresponding to 15% tube plugging) and ignores the steam dump to condenser to intentionally drive the seconday side pressure above the ASD/ARV lift setting to evaluate offsite doses. When consideration is given to the extremely low probability of lifting the ASDs/ARVs after an actual SGTR with RCS T., < 500 F versus the real potential for entering COMS/LTOP LCO

r'

=

I

.- Applicability with no mitigation pathway, Callaway and WCGS maintain that the proposed change results in an enhancement to net plant safety.

l l

l ATTACHED PAGES:

None s

l i

i i

l l

I' l

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 (supplemental): 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 conference call with the NRC staff on November 19,1998.

ATTACHED PAGES: 0, CTS 3/4.4 - ITS 3.4 Enclosure SA, Traveler Status Sheet A, page 8 i

I l

TRAVELER #

STATUS DIEFERENCE #

CO M NTS h

Incorporated 6 A/A RG4 dh]

& 3,4,l g lif Y:~l3YF-272

-Afg n

su,

$ O Y YO h

h & Myn V a NRe A

}Ne Anesan+.

In H rd d -A < L t /a ns e $24,1yj

f s,,

4 MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97

CHANGE NUMBER JUSTIFTCATION I

3.4 49 LC0 3.4.12. "[COMS]", 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 $3'f./2-/

being credited to meet the LCO. The proposed change adds the word pgg

" required" to the Surveillance to exempt its performance iff

@ editorial change #4Eb4}ade. equipment to be teste 4

i The LC0 requirement presentation was an

- ciarified.t A e

Le od 3.4.

.6wsr ised o ep Ce f

y r

u~'

be t" wit "re ired o be erf rmed" si ce he f

men at e is pprop iate ere cons' t t _itt t S

j, y

g f ff y W}T&'F1$~0h &3W~l N

1 3.4 50 This enang t with current TS SR 4.4.9.3.3.

The 12 hou frequency applies to vent pathway (s) that are not locked, sealed, or otherwise secured in the open position. The wording added to ITS SR 3.4.12.5 is also consistent with the format used in similar ITS 3.6 SRs. The 31 day frequency is also revised to be consistent with current TS SR 4.4.9.3.3.

3.4 51 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 6B).

3.4 52

~

Not applicable to Callaway. See Conversion Cemparison Table i

cv (Enclosure 6B).

g. +.ss zwar 2.+-ss 10 c-M-007 NJ a,7 edle de C,//ay. See Csnyavir,, (%,,,,.,.,,n 0 Ir 3+-s+

7~alle [ Enclosure 69).

b c-3. 4-6s3 3.4-rf u

3,+ -rr (c, A) bG3Y/~N JUSTIFICATION FOR DIFFERENCES TS 8

5/15/97

l INSERT 3.4-49A Q 3.4.12-1 i

This change is consistent with the current TS which does not require this surveillance unless the vents are being used for overpressure protection.

INSERT 3.4-49B i

The CTS surveillance that converts to SR 3.4.12.8 requires that the testing be performed within 31 days prior to entering a condition in which the PORV is required to be operable. In other words, the CTS requires that the PORV actuation channel meet the requirement (i.e., be capable of successfully passing the SR) and that the SR be successfully performed prior to entering a condition in which the PORV is required to be operable. The STS note for SR 3.4.12.8 allows that the SR does not need to be met (i.e., be capable of being successfully performed) until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering a condition in which the PORV is required to be operable. Since the SR does not need to be met, neither does it need to be performed until sometime during the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The licensees agree that the SR does not need to be performed until the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed by the STS and submitted a less-restrictive DOC (9,

LS) and NSHC (LS-20) to describe and justify the change. The licensees do not agree that it is acceptable to allow that the SR not be met upon entering the applicability of the LCO and

...-y therefore retain this CTS requirement. In order to retain the CTS requirement that the SR be met upon entering a condition in which the PORV is required, the words in the ITS SR 3.4.12.8 note are changed from "Not required to be met... " to "Not required to be performed.

l l

l l

l

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: WC 3.4-0010 APPLICABILITY: CA REQUEST (original): Move the CTS list of Pressure Isolation Valves to the Background Bases for ITS 3.4.14.

REQUEST (supplement): Insert B 3.4-90 has been revised to correct the function descriptions for BBV0001, BBV0022, BBV0040, BBV0059, and EM8815 to replace " BIT" with " Boron Injection Header." The BIT was retired in a previous plant modification. All other changes in the original submittal of WC 3.4-0010 for Callaway remain the same.

ATTACHED PAGES. 0, CTS 3/4.4 - ITS 3.4 8, insert B 3.4-90

)

__.____.m_

R

== 3.4-1 (y c - y. +-go 8

- =gn=:C=TanEMmE=.= 3.

v IV ER7~ f ?.+-10 l

Z VA L'.* E VALVE HAxIMux NUMBER SIZE (in.)

FUNCTION ALLOWABLE l

LEAKAGE (qcm)

[

BB8948A 10-RCS Loop 1 Cold Leg SI Accu Chck l

BB8948B 10 5.0 RCS Locp 2. Cold Leg SI Accu chck BB8948C 10 5.0 RCS Loop 3 Cold Leg SI Accu Chck 3889480 10 5.0 RCS Loop 4 Cold Leg SI Accu Chck BB8949A 6

5.0 RCS Loop 1 Hot Leg SI/RHR Pump Chck 3.0 BB8949B 6

RCS Loop 2 Hot Leg SI/RHR Pump Chek l

BB8949C 6

3.0 RCS Loop 3 Mot Leg SI/RHR Pump Chek BB89490 6

3.0 RCS Loop 4 Not Leg SI/RHR Pump Chck i

t 3.0 BBV0001 1.5 RCS Loop 1 Cold Lag SI/

Chck 0.75

/

BBV0022 1.5 RCS Loop 2 Cold Leg SI/

g;nex 1

BBV0040 1.5 RCS Loop 3 Cold Leg SI/

h;ncK 0.75 0.75

(

BBV0059 1.5 RCS Loop 4 Cold Leg SI/s.l.agcncX 1

0.75 BBPV8702A 12 RCS Loop 1 Mot Leg to RHR rumps ISO 5.0 BSPV8702B 12 RCS Loop 4 Not Leg to RHR Pumps ISO EJ8841A 6

5.0 RHR TRNS SIS Hot Leg Loop 2 Recire 3.0 EJ8841B 6

RHR TRNS SIS Hot Leg Loop 3 Recirc l

EJHV8701A 12 RER Pump A Suction ISO 3.0 EJHV8701B 12 RHR Pump B Suction ISO 5.0 5.0 EMV0001 2

SI Pump A Disch to Hot Leg Loop 2 ck 1.0 EXV0002

'2 SI Pump A Disch to Hot Lag Loop 3 hck 1.0 EMV0003 2

SI Pump B Disch to Hot Lag Loop 1 hek 1.0 l

EMV0004 2

SI Pump B Disch to Hot Lag Loop 4 hck 1.0 l

i l

EM8815 3

CS Cut Check 1.5 EPV0010 2

SI sps to RCS Cold Leg Loop 1 Chek 1.0 l

EPV0020 2

SI 1 mps to RCS Cold Leg Loop 2 Chek 1.0 EPV0030 2

SI ; Maps to RCS Cold Leg Loop 3 Chck 1.0 EPV0040 2

SI

h. imps to RCS Cold Leg Loop 4 Chck 1.0 EP8818A 6

Pumps to RCS Cold Leg Loop 1 C hek 3.0 EP8818B 6

Pumps te RCS Cold Leg Loop 2 Chek 3.0 EP8818C 6

Pumps to RCS Cold Leg Loop 3 Ghek 3.0

)

EP8818D 6-Pumps to RCS Cold Leg Loop 4 Ghck 3. 0-EP8956A 10 SI Accu TX A Cut Upstream Chek l

5.0 EP89568 10 SI Accu Tk B Cut Upstream Chck 5.0 EP8956C 10 S

Accu TX C Cut Upstream Chek 5.0 EP89560 10 S:

Accu TX D Cut Upstream Chek 5.0 Q,_ npaa f

6a, rv.

- f 4-

-]

l i

c

,, -, - ~,,

l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.7.G-1 APPLICABILITY: DC, CP, WC, CA REQUEST:

ITS 3.7.X Bases General There have been a number of instances that the specific changes to the STS Bases are not properly identified with redline or strikeout marks.

Comment: Perform an audit of all STS Bases markups and identify instances where j

additions and/or deletions of Bases were not properly identified in the original submittal.

1 l

FLOG RESPONSE:

(Original) The submitted ITS Bases markups for Section 3.7 have been compared to the STS Bases. Some differences that were identified were in accordance with the markup methodologies (e.g., deletion of brackets and reviewer's notes). Most of the differences were editorial in nature and would not have affected the review. Examples of

'l editorial changes are:

1)

Capitalizing a letter with only a " redline" but not striking out the lower case letter that is replaced.

2)

Changing a verb from singular to plural by adding an "s" without " redlining" the "s".

3)

Deleting instead of striking-out the A, B, C, etc. following a specification title (e.g.,

SR3.6.6.A.7).

4)

Changing a bracketed reference (in the reference section) with only a " redline" for the new reference but failing to include the strike-out of the old reference.

5) in some instances the brackets were retained (and struck-out) but the unchanged text within the brackets was not redlined.

6)

Not redlining a title of a bracketed section. The methodology calls for the section title to be redlined when an entire section was bracketed.

7)

Additional text not contained in the STS Bases was added to the ITS Bases by the lead FLOG member during the development of the submittal. Once it was determined to not be applicable, the text was then struck-out and remains in the ITS Bases mark-up.

The pages requiring changes because they are not consistent with the markup methodology are attached.

FLOG SUPPLEMENTAL RESPONSE:

The attached page shows the correction to unstrike the word "and" to include it as part of the text to Bases LCO 3.7.2. This change makes the text correct. The change is applicable to Callaway only and not to Commanche Peak, Diablo Canyon, or Wolf Creek.

ATTACHED PAGES:

Encl. 5B B 3.7-10 1

MSIVs B 3.7.2 3

rs BASES APPLICABLE a.

An HELB inside containment.

In order to maximize the mass SAFETY ANALYSES and energy release into containment, the analysis assumes (continued) that the MSIV in the affected steam' generator remains open. For this accident scenario, steam is discharged into containment from all steam generators until the remaining MSIVs close. After MSIV closure, steam is discharged into containment only from the affected steam generator and from the residual steam in the main steam header downstream of the closed MSIVs in the unaffected i

loops. Closure of the MSIVs isolates the break from the unaffected steam generators.

b.

A break outside of containment and upstream from the MSIVs is not a containment pressurization concern. The uncontrolled blowdown of more than one steam generator must be prevented to limit the potential for uncontrolled RCS cooldown and positive reactivity addition. Closure of the MSIVs isolates the break and limits the blowdown to a single steam generator, c.

A break downstream of the MSIVs will be isolated by the closure of the MSIVs.

d.

Following a steam generator tube rupture, closure of the HSIVs isolates the ruptured steam generator from the intact steam generators to minimize radiological releases.

e.

The MSIVs are also utilized during other events such as a feedwater line break. This event is less limiting se E far as MSIV OPERABILITY is concerned.

The HSIVs satisfy Criterion 3 of th; OC "elicy Str. tar.t

=w.

~ ~.

h;;

fg3,y,g_g]

LCO This LCO requires that in the steam lines be OPERABLE.

The HSIVs ate.f.ons dered OPERABLE when the isolation times are withinlimit7 end bey e+ese on an isolation actua on signal.

1310 This LCO provides assurance that the HSIVs will perform their design safety function to mitigate the consequences of accidents that could result in offsite exposures comparable to the (continued) l HARK UP 0F NUREG 1431 BASES B 3.7 10 5/15/97 1

i

I ADDITIONAL INFORMATION COVER SHEET l

ADDITIONAL INFORMATION NO: O 3.7.1-4 APPLICABILITY: DC, CP, WC, CA REQUEST:

CTS 3.7.1.1 Action a l

ITS 3.7.1 Action A.1 and A.2 and Table 3.7.1-1 DOC 01-04-LS3 JFD 3.7-01 1

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:

(ORIGINA'.) 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 Allowable 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 SUPPLEMENTAL RESPONSE:

AmerenUE's original response to NRC RAI Question 3.7.1-4 from ITS Section 3.7 indicated the adoption of traveler TSTF-235, with modifications unique to Callaway. After additional NRC review that the modifications are out of scope, AmorenUE is withdrawing portions of its response to RAI 3.7.1-4 in the October 21,1998 submittal. The attached pages show the revised response and are a replacement to those submitted in the October 21,1998 transmittal. These revisions are applicable only to Callaway and do not impact Comanche Peak, Diablo Canyon, or Wolf Creek.

FLOG SECOND SUPPLEMENTAL RESPONSE:

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, these revisions supplement a supplemental response submitted in the November 25, 1998 follow-up letter.

ATTACHED PAGES:

Encl. 2 7-1 (Insert A) l Encl. 3A 2

Encl. 38 1

Encl. 4 18,19 Encl. 5A Traveler Status page 3.7-1 l

Encl. 5B B 3.7-4 (Insert 5B-4a)

. f.-

a

..r-

~.

l RE'/IS10y 3/4.7 PLANT SYSTEMS l

2/4.7.1 TURBINE CYCLE l k Q L'1,I-l SAFETY VALVES

\\

t l

LIMITING CONDITION FOR CPERATION r

. ::i' -.

3. 7.1. 1 All main steam line Code safety valves asscciated with each steam generator shall be OPERAELE u th li.'t :e::i.gs 2:.pe.i fi ed ia Ts;' m :.

2.

o).eg-A s

APPLICABILITY: NOCES 1, 2, and 3..

t.o ck mSSd 01- 01-L51.

ACTION:

h bdM Chha e

%o i

(

.x Wit.4 four reacter cociant iceps and associated steam generaters in 4 3,7. l-Y ecerttien anW th or mere main steam line Code safety valves (necera e.g pera n in OES 1,1, and 3 may pmceed pmvided, that ol-04-lg a rw-ithin 4 hcurs, either the inoperable valve is restered to CPERABLE

-g g status :r h; ~;w:r "rg: S tr: 'i= Migh

-f; S:t: f-: i: r:du;; d"e g. cu,-ts E M of tt1or-c

cr 7;ti 2.~ ~_; otherwise, te in at least HOT STANOBY %ithiit v.e C

gg f: ': '--

grs.

g jepe j next 6 hcurs and ing"._. SHUTDOWN within th:

d t.

u-pr:c:i = ; :r :; ui'i =:i a :.:.1 u. = ;;li atic.

r= ;; ^ -

ci-05-A o t-o -%55 s

/

Q S.7.l-5

\\

L se d., b N M on-c L-m c.

% ts to )

^

SURVEILLANCE REOUIREMENTS g 3,9,j _g e 2ddit'e n*

ui :::.n: ::h:- :..= th:n : ui ;d :j ct-o T-A

4. 7.1.1 u

'k

g e. ' 'i mi.a

. :. ~. ~~ ns eA f cs HssV inopwlle. a A. Mm pesh 4 9 pcum.buf :

a,e..I co us 3 o 3.1.1-4 M_04-LS-0

[M SH S"'

eZ (HTt.')

L er enc

.ccp a aan w M, reduu 2ero or NMdd P cu,2, l

CALLaWAY - UNIT 1

./4 7-1 WO~:D~

i.'

s

l..

CTS 3.7.1.1 footnotes and inserts I

a i

I s.y insert A

~

t

)

l e.

f or ndux 7..c.m.d Power ' ' ^~ 2- ^- -'1 wh- %7%

A.!!:rdle.

CN 01-04-LS3

-?

~

l p> -

.r..

.a.m Tab 1e *a.7-1 #. *_'-."..'. - ' # nDCD_W r_ ".._N.. and ge u

l

.u..

7 48p[

edeee the Power Range Neutron Flux Hi;;h Trip Setpoinfts reduced w4.ee

~

,W

- d.r.n = :quac +h- %b."= A!!ced!: ?', RTP :p=!E:d in Table 3.7-1 hin t_.,cnor,34me-uce,r

. Ads. c,..t -~ ?~" 7 ._'.J.~~7f ~~~~ ~ #,

t F

+=

s..... x.

l 4

t;7

~ ~

l

-a$G-Irisert B NEW ~'

in

%. %g,V HoDE 3

~~

~

c -

s

~ ~,.

'~~

c. With one or more steam generators with less than two MSSVs 01-06-M

^

OPERABLE, be in at least+iC4 '~/2GB'cwithin the'next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and

• t e n.*,= rev,* e. h v* m ?2 m av a e with* L(:

f jj m.m.

m

.c..c=. B ours.

/,R l

% c.

' ?*

H O D c 4-

\\

Insert C i

3. -

4.7.1.1@ Verify each required MSSV lift setpoint per Table 3.7-2 in 01-07-A

^

accordance with the Inservice Testing Program. Following testing, lift setting shall be within +/- 1%.

Footnotes A

Only required to be performed in MODES I and 2 01-05-At' 4 M I~6

-ed 'i n M0bE i o t-o4 -I 5-3 v

o 3a.1 -4 e

l

-~-.-.-m CPN!GE

}

NUMBER Eic OEscRIoricN q 3.7.l-4 high trip setpcint be reduced for incperable MSSVs if a g

positive moderator temperature coefficient (KiC) exists at

~ Gn 1

,1 the allowed percent rated thermal pcwer in MCCE 1: and Q,.,

f C,_

3) the pcwer range neutron flux high trip setpcints be raduced tn account for a centrol rod withdrawal at partial

$ ;-f power witn more tnan one MSSV incperable.,Jn addition.

F the comaletion time fer resetting the high TIux trips is

.qp

/, {

revised from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> toy hours and the ACTION is ravised g

4 6.,,

to specifically require an apprcpriate power reduction E

J o

within four hours. This is a relaxation since the CTS y$'

{

' ' require the high neutron flux trip setpoint to be reduced "W

i as required within four hours for inocemble HSSVs W

w 3oh#

recardless of the MTC valuejPending approval of craft N $

f 1 of WCG 83, the cnanges proposed in the travel P

D '

Ih p

hve an modified to retain the current TS rem ement to 4

d o.

' eset the e range reutre.,n flux Figh trip etpoints

?

based en the numce f MSSVs incperable t a maximum

-e Jt 3**I allowable power determi.

in accordan - with calculations cr analysis to account for W.*ingh se NSAL 94-001 and d

O

-r NRC Infennatico,4ctice 94 60. h ver, the completion QN' L:,U E_

time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> proposed by '. -83.

been retained and }

~

• w$

is justified based on the w prcbabilit f an event 1

L cccurring during this '%e and the need to p vide 4sufficient time to set the channels in an orc ly manner

- ~

~$$g sithout inducin transient due to human error.

e Retentien of ne CTS requirement for resetting the re. or g

a

'A trip set ints is acceptable because this requirement is

~

2 e nera enservative than the ACTICNS scecified by either the D

(S S _cr WCG 83. as revised) kA The exception to TS 3.0.4 is no longer needed due to the 01 05 note associated with tne revised surveillance. The exception was allowed to TS 3.0.4 cue to the fac*;;*a*;g"*

Q3.9.1-5 l

acplicable MCCES must be enteree in creer ec pec required surveillance (if the MSSVs are tested in place) and to allow Mcde changes to be mace if the acclicable action wts met. In the CTS. MCCE 1. 2. cr 3 could be In UREg.1431. the surveillance 15 mcdifiec by a

]e-ed. - - -- Octe that specifies nat tne surveillance

~

need eni? ce current price to reaching MCCE 2.

The surveillance note still alicws HCCE changes into the MCCE or APPLICMILIT( of the LCO. i.e.

M0CE 3 for testing purposes.

01 06 M

The new ACTICN adds an explicit recuirement to be in

-}

MCCE 3 in 6 ncurs anc HCCE 4 in 12 hcurs if any steam generator (SG) loco has less than two MSSVs coera'oie.

NUREG 1431 recuires that ne plant only te placec in a DESCRIPTICN CF CHANGES TO CURRENT IS 2

5/15/97

h h

l y

CONVERSIONCOMPNRISONTABLE-CURRENTTS3/4.7 Page 1 of 15 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CAllAWAY I

01 01 Reference to Table 3.7 2 is deleted from the LCO and YES YES YES YES A

relocated to the SR (refer to 01-07-A).

01-02 A note is added to allow separate condition entry for each YES YES YES YES LS-1 HSSV which allows the full four hours for each inoperable MSSV.

01-03 This CPSES spectfic revision relaxes the as-found MSSV lift NO: LA 108/107 YES NO N0 t

LS 2 tolerances from +/- It to +/- 31.

issued 10/1/95 to relax setpoint (refer also to 01 13 LS20).

01-04 Revised ACTIONS for inoperable H55Vs: 1) specifically h

YES YES YES LS-3 requires a power reduction within four hours and yo, %

2) requires the reactor power neutron flux hi set 4,g 3 3 3 f,., _

point to be reduced within M hours.

g g.,.u._

gyg, Jo-05 The ACTION of the CTS which allowed an exception to

-w

.n j

YES YES YES YES v

]%A TS 3.0.4 is deieted due to the note associated with revised N -5 SR 4.7.1.1 which allows a H0DE change into MODE 3. one of the H0 DES of APPLICABILITY of the LCO.

01-06 The new ACTION adds an explicit requirement to be in MODE 3 YES YES YES YES l-in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and H00E 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> if any SG loop has less than two HSSVs 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 YES YES YES YES A

Program. The surveillance directly references Table 3.7-2 for lift points and incorporates the footnote from the table requiring the MSSV as left 11ftpoints to be within

+/- 11 of the nominal setpoint.

01 08 NOT USED.

N/A N/A N/A N/A CONVERSION COMPARISON TABLE - CURRENT TS 5/15/97

IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATICNS NSHC LS 3 10 CFR 50.92 EVALUATION FOR l

TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS The CTS allow continued operation with inoperable MSSVs if the power range neutron l

flux high reactor trip setpoints are reduced. The amount of reduction in the trip b

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 thuskn the 4 M overpressure protection) should a transient requiring their operation occur.

proposed specification, the CTS requirement to reduce the power range high neutron p,1.l-9 l

flux reactor trip setpoint is retained; however, the time to comolete resetting the j

trip setpoints would be changed from four to { hours.

g The CTS require that, if the MSSV cannot be restored to an OPERABLE status within four hours, that 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, A

NUREG-1431 would not require resetting the power range neutron flux high setpoints. gh,o The Westinghouse Owners Group (WOG) has proposed changes to NUREG 1431 P::'r ZC :.; w ;;d th =:b i ;f..b. L that: 1) propose that the completion time T5TF-for resetting the power range neutron flux high trip setpoint to compensate for a positive MTC or a control rod withdrawal event at partial reactor power to be hours, 2) specifies that the power level reductions be per the Westinghouse g

NSAL 94 01 and, 3) deletes the Maxi' mum Allowable 4 3M.14 Nuclear Safety Advisory Letter J t RTP for 5 MSSVs OPERABLE. jewe er, pe ing pr va of dra Rev.

o nan es pc ec 1 In

'+av ler ha been modir-

+o r tai h curr t S

,@e (t eq nt ors e

er en tro ux h' h tri etpoin ba o the Q 30-} Y o

SVs inop ab o

max 1, allo ao wer de erm n _a rda ce (1

ic" at; ns or anal ysis o account

.v Westi ghouse SAL 94-001] Ine allowed Lompienon Time to reduce the Power Range Neutron Flux trip setpoints is reasonable based on operating exoerience to accomplish the required ACTIONS in an orderly The power levels specified per NSAL 94-001 are based on a conservative manner.

algorithm developed by Westinghouse to bound the required relief capacity.

T5'rF-235 43M.l--Y The above changes. are consistent with NUREG 1431 as revised by103:et and NSAL 94 001.

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

Tne Ccamission may make a final cetermination. pursuant to tne procedures in paragrach 50 91. that a prcocsed amendment to an ccerating license for a

\\

fJcility licensed under paragracn 50.21(b) cr paragracn 50 22 or a testing i

facility involves no s1gn1ficant nazards consideraticn. If coeration of cne facility In acccrdance witn tne prcccsed amencment would not:

5/15/97 NO SIGNIFICANT HAZARDS CCNSIDERATION 18

--~---,ae.

.ma-IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS D

NSHC LS 3 (continued) 1.

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

2.

Create the poss1b.

~ of a new or different kind of accident frorn any accident previously evaluated; or 3.

Involve a significant reduction in a margin of safety."

The following evaluation is provided for the NSHC.

1.

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

l 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 probability of an g

accident occurring and requiring MSSV operation during the )E nour Completion Time would be very small. The time extension allows the reactor trip setpoint

'q' reduction to be performed in a more deliberate manner. thereby reducing the potential for inadvertent reactor trips introduced during the setpoint reduction. However, because the accident analysis are unaffected by the proposed change, the consequences of the accident analysis 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.

l 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 unit system or l

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.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

l 3.

Does the change involve a significant reduction in a margin of safety?

NO SIGNIFICANT HAZARDS CONSIDERATION 19 5/15/97

s Zndustry Travelers Applicable to Section 3.7 M VF1FR #

STATUS DIFFERENCE #

C0ffiENTS TSTF 36, Rev. 2 Incorporated 3.7 42,. 0nly applicable to DCPP TSTF 51 Not Incorporated Not Applicable Requires plant specific reanalysis to establish decay time dependence for fuel handling accident.

TSTF 70, Rev. 1 Not Incorporated Not Applicable

-Net NRC approved,-:: Of

- trr! & r cet Off d:te. @- 7 ~7--# # #

TSTF 100 Incorporated 3.7 05 and 3.7 19 NRC approved.

TSTF 101 Incorporated 3.7 29 Mtc approved.

Wee 4S Partially 3.7 01 Retained CTS (Formerly Incorporated requirements for resetting trip setpoints W0e:317, I since requirements are 3s M*k more conservative than

' ' ~

@ J3 7 l d the traveler.

N Incorporated 3.7 34 Not incorporated by DCPP 9 3 9'd'I as current licensing gg.,,,y l G 3.7.1-1 TSTF 139.

Incorporated Not Applicable -

g,// y,,/,

ff

-rg-3.-7-Ogr Rev. 1 Bases change (CEOG 51)

TSTF 140,

$ Incorporated Not Applicable TR J.'7-cc4

,e sm Rev. %. O w{n,a a, &e er, cudu mI;

%;on.

(CEOG 52) f$I-WO946pg7 Incorporated 3.7 57 4 b~7.2-16Gb.7./3..?-%

m Incorporated 3.7 56 Tff F -pS9 0 3.9. 1 - 3 G 3 7'

~

2

$"f rn 1 TR 3.'l-00 I g h b.1-001 TR 3 'I'CUA-MARK-UP OF WOG STS REV 1 (NUREG 1431) 1 5/15/97 I.

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 The EGe MSSVs per;steamsgenetator; shall be OPERABLE c; ;p;;ifi;d in 3 7-01 Tebic :..1 1 ;nd T;bic :.7.1 2.

APPLICABILITY:

MODES 1. 2. and 3.

ACTIONS

~

Separate Conditi entry is owed r each MSSV.

D CONDITION REQUIRED ACTION COMPLETION TIME)

One or more iczuir;d

• .1 Reduce powea TBEREUE20RER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 2 3 J OL 3 to less than or equal to the 6 C S ',;;;r:bi;.

56 q sleG'Cg' PPli;;ble 5fM!iDiiWWW8bTd I

IU i

S btCO Of S

Table 3.7.11 totatroesnonnen

/ jrt yopa bl m!memmess.

OR -

... - N ou 'a Made i O n e ro o te 5 "I.

ook te@<a i cj4.We A.hs toi g m..

-- M

. 3;730k N

H55V i no pura.N8-3

' '+ @ r e-%t#!

^ 'j f

1. Fr%4 s MtdinFr5 g g t C. pMB Wii3EEN!EGI21iliBiii b hNf8 pewa

[

Q~

PUKr#x=---*mneca:r;tmyTn Larrr--,isaesrgscen Q 3,7. l* 9 gemm

\\

C Ck. Required Action and X.1BeinM00E3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met, el!D.

/2 Be in MOCE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Og b

One or more steam generators with seau.

3

-- ' z --:1 :T;r A i

h + mms incey&.

=

(

T 5/15/97 MAPX.UP OF Ji STS REV 1 (NUREG 1431) 3.7 1 A

MSSVs B 3.7.1 BASES ACTIONS A.1 WRf9NM! (continued)

G3,7.).Y a

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

w With one or more MSSVs inoperable, TCduCC p; r.wno av t.t g so that the available MSSV relieving capacity meets Reference 2 requirements for thC sppliCablC '1C"/1. "M".

wrthishk Q Q 3.7.G-I 3

meration with less than all "1 SVs OPERABLE for each steam generator is permissible, if ~

L POWER is propertionally limited to the relief capacity of the remaining MSSVs This is accomp_lished restricti P_

4 3a.1-4 so that the energy ransfer to most limit 1ng eaa generator is not greater than the available relief capacity in that steam generator. Ter s;;plC, if era "00" i; irepCrablC in e,,6 ;ta;, n,.reter, tP4 rCliCf ;ep; City ;f th;t ;ts;

______m__

2_

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_,,__m mu2_

p4 #b t W bWI 4d 6 kWWbbW Wg Wyys W A e sugW bb i J

6. Wg.

IW W5 4dbb b6 4 6 d IC UbbiOO iIs IC iCf CO OC sIf, CirCijg' I WO^5fCI IO I SI SICCE y

$n reter rW;t bC ;i;ilerly ICduCCd by et 1Ce;t S^.

"-is is

______,2_u_;

u..

__2.._2__

,,-o.,

u..

_m

,___m e m.,

m _u ubbVUsuy 5 6 da Ib W WJ 4 kWWh 4 a sy 4 a hais ww 4 VTN4 % WJ Wb 4budb 6.d 4 Mi d I V4 3 COO $C4-'v dbi'v C j inib3 I d CisC.hj IICI 3fCI IC O 3ICWA hbisCI[aICI3 m_

_____2__,..

e m., _,

m_m_,

_____2m..

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.. m me.

4.V Wyyt W A 8 535M bb i g WWM V5 kW bliB 5 buyWb 4 bJ e bVIIe# 5 em bb6 5 b M i be l bi lh IC iCf Cish0CiIf Of

^ ^^^

^^ 3IC^.G yderdidICI.

^

m A

l I

I

/

/

4 3.7. l-y f'

/

/

/

r 1

/

)__

.~.-1 a n-__. _. w - _AmuL.F4r.4 LdUM eF".-

---n-.--u-,

,s p-

--- Alic:IT#

u siatu s.-n.uw --i *uts linu--mm--

rCr CaCh 2I:= ;$adre;r. = a :pCCi r Cd p. a;ur;. thC traCIiCna'

__,2_,

_____m..

,.-.,,s

___u u,.,,,

2__;

1. .4 4VI bdpub i og g6 4 \\b /

dI w W V4 I 4 henge v 4.e

=dh bb 6 EEE i 5 lbW ud

&W3 i WTT d.

)

A

.. s b.

B (continued)

MARX UP CF NUREG 1431 BASES B 3.7 4 5/15/97

O 3.7.1-4 INSERT 58-4a i

B.1 and B.2 In the case of multiple inoperable MSSVs on one or more steam generators, with a reactor power reduction alone there may be insufficient total steam flow capacity provided by the turbine and remaining OPERABLE MSSVs to preclude overpressurization in the event of an increased reactor power due to reactivity insertion, such as in the event of an uncontrolled RCCA bank

)

withdrawal at power. Furthermore, for a single inoperable MSSV on one or more steam generators when the Moderator Temperature Coefficient is positive at any power level the reactor power may increase as a result of an RCS heatup event such that flow capacity of the remaining OPERABLE MSSVs is insufficient. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time for Required Action B.1 is consistent with A.1. an additional 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> is allowed in Required Action B.2 to i

reduce the setpoints. The completion Time of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> is based on a reasonable time to correct the MSSV inoperability, the time required to perform the power reduction, operating experience in resetting all channels of a protective func"nn, and on the low probability of the occurrence of a transient that could result in steam generato, overpressure during this period.

The maximum THERMAL POWER corresponding to the heat removal capacity of the remaining OPERABLE MSSVs is determined via a conservative heat balance calculation as described in

{

l the attachment to Reference 6, with an appropriate allowance for Nuclear Instrumentation System trip channel uncertainties.

Required Action B.2 is modified by a Note, indicating that the Power Range Neutron Flux-High reactor trip setpoint reduction is only required in MODE '.. In MODES 2 and 3 the reactor protection system trips specified in LCO 3.3.1," Reactor Trip System instrumentation," provides l

sufficient protection.

The allowed Completion Times are reasonable based on operating experience to accomplish the Required Actions in an orderly manner without challenging unit systems.

l l

4 i

i 4

T

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

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.7.10-14 APPLICABILITY: DC, WC, CP, CA REQUEST:

CTS 3.7.6 Action b, Modes 1,2,3 & 4; Actica 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) ha s not been approved by the NRC.

In addition, for CPSES, the Action D condition statement appears to be contradictory because with two inoperable trains, it is not clear how any pressurization occurs.

Comment: Withdraw the changes or adopt the STS.

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 result 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 inoperable CR boundary. The CR boundary inoperability is usually the result of boundary degradation such that either CREFS trains running the system is unable to maintain a pressurization 1

of >.125 inches water gauge at 800 cfm. Action D merely requires repair of the degraded pressure boundary.

FLOG SUPPLEMENTAL RESPONSE:

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:

l Encl. 5A Traveler Status page,3.7-25,3.7-26 I

Encl. 5B B 3.7-67, B 3.7-68, B 3.7-69 l

Also, see attached pages for response to Comment Number 3.7.13.2-2.

l l

Industry Travelers Applicable to Section 3.7 Q

TRAVELER #

STATUS DIFFERENCE #

COMENTS TSTF 36, Rev. 2 Incorporated 3.7 42, Only applicable to DCPP TSTF 51 Not Incorporated Not Applicable Requires plant specific reanalysis to establish j

decay time dependence for fuel handling accident.

TSTF 70 Rev. 1 Not Incorporated Not Applicable

-Net-NRC approved,-c; cf

-trrfe'cr cut cff d:tc. Y-7 ~7-###

TSTF-100 Incorporated 3.7 05 and 3.7 19 NRC approved.

I TSTF 101 Incorporated 3.7 29 NRC approved.

W0043 Partially 3.7 01 Retained CTS (Formerly Incorporated requirements for WB8 GIT resetting trip setpoints since requirements are more conservative than

~

the traveler.

W88Hi+-

Incorporated 3.7 34 Not incorporated by DCPP as current licensing 4

73g,,, g basis.

TSTF 139, Incorporated Not Applicable -

ggc,ffy,y,j, Tg-7 7-oer Rev. 1 Bases change (CE0G 51)

TSTF 140, M Incorpor Not Applicable TR3.7-cq Rev. %. O h(r,duendne ewItalsfe er,W dw 6 he N

bim.

(CEOG 52)

MW99dkrg r

p Incorporated 3.7 57

-Wee 48 Incorporated 3.7 56 1STF -pB9 c

,4 3

Q s,1. I3. 9Q 4 % n-ooi n sa-* I

{\\%.,-oa n sn 1 MARK UP 0F WOG STS REV 1 (NUREG 1431) 1 5/15/97

M GREFG

/[Q 3.7.10

%As n

3.7 PLMT SYSTDtS

~

3.7.10 Control Room Emergency filtretien m System (0."!TO M

' PS s LCO 3.7.10 Two GRE M 5

trains spil be 0PERABLE.

g CZ/)Jeg[_ 6)- *L-)

> 01718"IY, opsy

-APPLICABILITY:

H0 DES 1, 2, 3, 4 M.

81 During movement of irradiated fuel assemblies.

(B PSs "uring L^^C tiX"4T!'"i ACTIONS COM)ITION REQUIRED ACTION COMPLETION TIME A.

One GRE M M tFain' A.1 Restore GRE N train to 7 days

• -m PSa

~

~

inoperable.

OPERABLE status.

5m M

x

-3.7-57x e

f a 32/a-if BE. Required Action and BE.1 Be in H0DE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A ' -

81Q 13.7 57e not met in H0DE 1, 2, 3, or 4.

BQ.2 Be in H0DE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> GB. Required Action and l0%

associated Completion

. le;; in t;xic ges pret;;tica B.PS-Time of Condition A not rc,d; if eate;;. etic tren;fer t; met.ir. -

.s temi; g;; pret;;tien ;;.ed; is

+B:

during movement of ir.eper; tic.

1rradiated fuel B PSe assemblies

r during EORE-AbTERAff0NS.

73 (continued)

..u -

MARK UP OF WOG STS REV 1 (NUREG 1431) 3.7-25 5/15/97

Q 3.7.10-14 ~

INSERT SA-a NOT E.------

The { control room] boundary may be opened intermittently under administrative control.

4 l

l I

d l

1 i-i 4

L i

i I

f..

I k

2 I

J e

4 i'

?

~ _,

I

l d.M'c M

(

3.7.10 4

\\- w /

ACTIONS (continued) i I,

CONDITION REQUIRED ACTION COMPLETION TIME s

.]i GB. (continued)

GB.1 Place OPERABLE GREM Immediately

PS --

train in q.:.<

'c c emergency mode.

DR i

...c.>:..

j

- s.:.

E aB:

4 6523 Suspend movement of Immediately irradiated fuel assemblies.

e'AW__

p...,,..

3.7-57.

g-...

e.

a.... a,. %,.

g.....

a, <..

m

,,.g.;i g

,,s. A

{,

Two GREM trains

< PS -

o -

inoperable

. H';

.: B -

M.s during movement of irradiated fuel

-- B --

I Q 3.9.10-5 (continued) 1Q MARX UP OF WOG STS REV 1 (NUREG 1431) 3.7 26 5/15/97

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

k EREFG M m

B 3.7.10 1

pae.y a

i BASES i

3 l

APPLICABLE The worst case single active failure of a component of the GREFG SAFE 1Y ANALYSES assuming a loss of offsite power, does not impair the j

(continued) ability of the system to perform its design function.

1 i

The GREFG satisfies Criterion 3 of tt.c = = ",licy statement.

LCO Two independent and redundant GREFG trains are required to be OPERABLE to ensure that at least one is available assuming a single failure disables the other train. Total system failure l

could result in exceeding a dose of 5 ren to the control room i

operator in the event of a large radioactive release.

.The GREFG is considered OPERABLE when the individual components necessary to limit operator exposure are OPERABLE in j'

both trains. A GREFG train is OPERABLE when the associated:

i

,['

a.

Fen-+s j

.f OPERABLE:

3 b.

HEPA filters and charcoal adsorbers are not excessively j

l.

restricting flow, and are capable of performing their j

filtration functions; and i

c.

Heater, i.;;bter, ductwork, valves.

l and dampers are OPERABLE, and air circulation can be j

maintained.

In addition, the control room m boundary must be h,Y l

maintained, including the integrity of the walls, floors, i

ceilings, ductwork, and access doors.

i 6

r <... i. '..

'._;ng.o t e' q ' r,.

m...

g ia l4 } d.s

.;r, s

l 1 -. r.

' ' 2 7 : ' t.

?,Q' q.,;.,.,

...;. }.t r.

....r.i, 7 -.J s'/

• s...

,,i..-.0,i, s#'

L ) %',

?.

. '. i m s

..,: w.,,

sy 7'

u.?,

%q t()

..-,.w.

.:..y.

.+ o....:

9

.c.. v.. :.,

w.y

..,.,,. &..s

.. n i..

..n. s nemensamme 1

)

.o t y l

.,u '

j (continued)

MARK UP OF NUREG 1431 BASES B 3.7 67 5/15/97 l

O 3.7.10-14 INSERT SB-a The LCO is modified by a Note allowing the (control room] boundary to be opened intermittently under administrative controls. For entry and exit through doors the administrative control of the opening is performed by the person (s) entering or exiting the area. For other openings these controls consist of stationing a dedicated individual at the opening who is in continuous communication with the control room. This individual will have a method to rapidly close the opening when a need for (control room] isolation is indicated.

I,

GREM x.

B 3.7.10 v...

BASES (continued)

APPLICABILIT(

In H0 DES 1, 2, 3, 4 m, ano during movement of irradiated fuel assemblies GREM gg must be OPERABLE to control operator exposure during and following a DBA.

In M, the GREM ea-is required to cope with the release from the rupture of er, wtsit.c l waste gas

-'i, :

tank.

During movement of irradiated fuel assemblies, the GREM m a must be OPERABLE to cope with the release from a m fuel handling accident.

ACTIONS M

When one GREM a train is inoperable, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE GREM train is adequate to perform the control room protection function. However, the overall reliability is reduced because a single failure in the OPERABLE j

train could result in loss of GREM function.

GREM The 7 day Completion Time is based on the low probability of a D

DBA occurring during this time period, and ability of the 3

,i Ng \\hl I

remaining train to provide the required capability.

@0 4

ifi S.q. \\ 0 5

sp '43 C ' e-

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. Is, /

.o o j i.

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9; _ ' n. f. es < e[ q y. [ 1_ _ _ '; _

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.c

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.c<-

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..M-w., y +'. 6. o. 9..) y u ! 1 g

t00#

((,10-Ik BC.1 and BG.2 In H00E 1, 2, 3 or 4, if the inoperable GREM 333 trainVcannot be restored to OPERABLE status within the required Completion Time, the unit must be placed in a MODE that minimizes accident risk. To achieve this status, the unit must be placed in at (continued)

MARK UP OF NUREG 1431 BASES B 3.7 68 5/15/97

~~ ~

GREFG M f~.

B 3.7.10

?

~

BASES ACTIONS M.1 and 80.2 (continued) least H0DE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in H00E 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. 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.

GB.1. m.2.1. and GD.2.2 during movement of irradiated fuel assemblies, if the inoperable GREFG M train cannot be restored to OPERABLE status within the required Completion Time, action must be taken to immediately place the OPERABLE GREfG M train in the emergency mode. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure would be L

readily detected.

l An alternative to Required Action C.1 is to imediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes risk. This does not preclude the movement of fuel to a safe position.

j

%gired l.;tien t.1 i;; ;difi;d by ; %te ir.dic;tir,; t; f.e;; th;

y;t;;;; in th; texi; p; i; ret;;tica ;;;;d; if ;;Cti; trerafer t; l

t;xic g; i, ret;;ti;; ;;;;;d; i; ire,,;r;bi;.

BE.1 and BE.2

% v.3...,.- x during movement of irr ted fuel assemblies.

with two trains i rable l

_ Q 3,9.ID-lil action musl taken i iv at could result in a release of l

radioactivity that might enter the control room. This places the unit in a condition that minimizes accident risk. This does not preclude the movement of fuel to a safe position.

l JS.$

.s L

(continued) i MARK UP OF NUREG 1431 BASES B 3.7 69 5/15/97 I

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.7.13.2-2 APPLICABILITY: WC, CA REQUEST:

CTS 3.7.7 Action, insert M [New c]; CTS 3.9.13 [new c]

ITS 3.7.13 Action B, C, D, E, and [F]

1 DOC (3.7) 10-20-LS39 DOC (3.9) 12-12-LS26 JFD 3.7-57 These changes are beyond the scope of a convers:on because the industry traveler referenced in this DOC (WOG-86) has not been approved by the NRC.

Comment: Withdraw the changes or adopt the STS.

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 WO186, and these modifications have been incorporated into the ITS. This resulted in changes only to the Bases for the Required Actions for the Emergency Exhaust System, ITS 3.7.13. The FLOG continues to pursue the changes proposed by this traveler.

i in addition, due to the change in traveler status, WOG-86 has been replaced with TSTF-287 in DOC (3.7) 10-20-LS39, DOC (3.9) 12-12-LS-26 (for WCGS only),

NSHC (3.7) LS-39, NSHC (3.9) LS-26 (for WCGS only), and JFD 3.7-57.

Also see the response to Comment Number O 3.7.10-14.

FLOG SUPPLEMENTAL RESPONSE:

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:

Encl. 5A Traveler Status page,3.7-30 Encl. 5B B 3.7-79 l

W

• • '._-wa,ma iwm-1 Industry Travelers Applicable to Section 3.7 Q

_ TRAVF1FR 4 STATUS DIFFERENCE #

C0 K NTS TSTF 36. Rev. 2 Incorporated 3.7-42. Only applicable to DCPP l

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

TSTF 70. Rev. 1 Not Incorporated Not Applicable fi& NRC approved,= Of trr&r ed Off tte. Y-7 N #3' T$TF 100 Incorporated 3.7 05 and 3.7 19 MtC approved.

TSTF 101 Incorporated 3.7 29 IRC approved.

\\'

W08-83 Partially 3.7 01 Retained CTS (Formerly Incorporated requirements for W98:3IT resetting trip setpoints since requirements are more conservative than

~

the traveler.

.q -

,J 418D64-Incorporated 3.7-34 Not incorporated by DCPP as current licensing TSTF 4 l basis.

TSTF 139 Incorporated Not Applicable -

ggc,'yny,j, Tg-y 7-Oes-Rev. 1 Bases change I

(CE0G 51)

TSTF 140 M Incorporated Not Applicable TR 3.7-tc4 Rev. X. O Inco tw d~p lo h Mrduendm om,lde eik (CE0G 52) rion.

g.W00*Wr g Incorporated 3.7 57

\\

Incorporated 3.7 56 W 8'96 TSF F -p83 Rw.I 4 3.7.10-14 M M.1-ooi TR 3.'l-oo I f 3 913 8' b.1-001 TR 3 'I'O A-

.]

MARK-UP OF WOG STS REV 1 (NUREG 1431) 1 5/15/97 b

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

._ \\

s...;v o. w k.3 w w a s,FBAGS-i

.c7 3.7.13

'w, n,a 3.7 PLANT SYSTEMS.

3.7.13 Taal ",uildir,; Air 01 =up Sy:;ta ffBAGS) mummmmmmme

. ps :

EEE 38 LCO 3.7.13 Two FBAGS a traint ebli he OPERAR!F

- PS '

APPLICABILITY:

B 1:.

During movement of irradiated fuel assemblies in the fuel building.

N.

m :;

~

'3.7 44

1 ACTIONS j

s CONDITION REQUIRED ACTION COMPLETION TIME A.

One EE FBAGG train A.1 Restore ~ FBAGE train to 7 days

PSt inoperable ? : e. - - -

OPERABLE status.

3.7 07x g

7. - m g :... :

i,...,....

_.3.7-571 s,... :;c,:,.:..

.q..:..;

. n r ;....

..g...

i 1R5tMRllll15511511 awv.ww (continued)

MARK UP 0F WOG STS REV 1 (NUREG 1431) 3.7 30 5/15/97

._.,, m J

Q 3.7.13.2-2 1

- INSERT SA a

......N OT E------------

The [a'uxiliary or fuel building) boundary may be opened

- intermittently under administrative control.~

1 i

I i

i 1

l t

l I'

I J

i b

's y

_..-..g-

,m,

...s.,,,

_1,>.... :.....--FBAC#r B 3.7.13 my

'l>

BASES (continued)

LC0 Two independent and redundant trains of the fBAEG T : e

..a., e er, p are required to be OPERABLE to ensure that at least one train is available, assuming a single failure that disables the other train, coincident with a loss of offsite power. Total system failure could result in the atmospheric release from the -

fuel her.dling building exceeding m tt; 10 Cm 100 (" f. 5) limits in i

j the event of a fuel handling accident.

J

}

the FBA6s

's

?

o j

is considered OPERABLE when the individual components necessary 4

to control

@sureintre 1

.-...~..., -...ir, are OPERABLE in both trains.

1

)

l l

s An FBAGS

~

train is l

considered OPERABLE when its associated:

a.

Fan is OPERABLE:

j l

b.

HEPA filter and charcoal adsorber are not excessively t

restricting flow, and are capable of performing their filtration function; and c.

Heater, d;;ister, ductwork, velves, and dampers are 3,9,l3,g.h

@ERABE, and a on _

ma aM.

f l

N APPLICABILITY In H00E 1, 2, 3, or 4, the FB M S ? -. m n m"

m is required to be OPERABLE y e 17 m J.?

./-wim to 3

provide fission product removal associated with ECCS leaks due to a LOCA and leakage from containment and annulus.

In H00E 5 or 6, the fBAEs u.:-.mer e is not required to be OPERABLE since the ECCS is not required to be OPERABLE.

4 1

During movement of irradiated fuel in the fuel

- w eg h;ndling i

e m the FBAEG

- w a w.n. ;. m is required to be OPERABLE R g[g ra M +.m m ~V. -- h e ? to alleviate the consequences of a fuel handling accident.

(continued) 3 HARK UP OF NUREG 1431 BASES B 3.7 79 5/15/97 J

i O 3.7.13.2. INSERT 5B-a -

The LCO is modified by a Note allowing the [ auxiliary or fuel building) boundary to be opened

. intermittently under administrative controls. For entry and exit through doors the administrative control of the opening is performed by the person (s) entering or exiting the area. For other openings these controls consist of stationing a dedicated ladividual at the opening who is in continuous communication with the control room. This individual will have a method to rapidly close the opening when a need for [ auxiliary or fuel building] isolation is indicated, s.

1 i

l l

i' i

[

l:

i

l l

ADDITIONAL INFORMATION COVER SHEET l

ADDITIONAL INFORMATION NO: CA 3.7-ED APPLICABILITY: CA REQUEST:

(Original) Various changes that do not impact the technical content of the submittal or other FLOG members.

l Changes are noted with CA 3.7-ED in the margin and noted below:

1)

CTS 3/4.7.1, Turbine Cycle, Safety Valves: the footnote to Table 3.7-1, Inoperable Main Steam Safety Valves versus Allowable Power and Power Range Neutron Flux High Trip Setpoint in Percent of RATED THERMAL POWER, is modified in two places by replacing "% RTP" with " power".

l 2)

ITS LCO 3.7.1, Main Steam Safety Valves (MSSVs): the footnote to Table l

3.7.1-1, OPERABLE Main Steam Safety Valves versus Maximum Allowable i

Power, is modified in two places by replacing "% RTP" with " power".

3)

ITS LCO 3.7.2, MSIVs, Condition D: two items under " Completion Time" should be highlighted.

4)

ITS LCO 3.7.5, Auxiliary Feedwater System: Action "B" (the designation letter B) should not be highlighted.

5)

ITS LCO 3.7.5, Auxiliary Feedwater System, SR 3.7.5.4: The "s" in " NOTES" should be struck through.

6)

ITS LCO 3.7.6, Condeneate Storage Tank, APPLICABILITY: a redlined period should be placed at er.

7)

ITS LCO 3.7.8, Essential Service Water, Action A: Under A.1 Notes, item 1, the period at end should not be struck out, but redlined.

8)

ITS LCO 3.7.9, Ultimate Heat Sink, Action B: under " Completion Time" the "s" after 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> should not be highlighted.

9)

ITS LCO 3.7.11, Control Room Air Conditioning System: Title line should have (CRACS) highlighted.

10)

ITS LCO 3.7.13, Emergency Exhaust System, SR 3.7.13.3: "SR 3.7.13.3" should be highlighted.

11)

ITS LCO 3.7.17, Spent Fuel Assembly Storage: Title should be highlighted.

l 12)

ITS LCO 3.7.17, Spent Fuel Assembly Storage: " Figure 3.7.17-1" should be highlighted.

FLOG SUPPLEMENTAL RESPONSE:

l' The attached page corrects the description associated with DOC 07-16 LS-34. This is an editorial change to correct the statement. This revision is only applicable to Callaway

(

and does not impact Commanch Peak, Diablo Canyon, or Wolf Creek.

ATTACHED PAGES:

Encl. 3A 10 l

CHANGE

~

NUMBER NSliC DESCRIPTION OPERABLE status. This change is considered less restrictive because it provides alternate methods of complying with Technical Specification ACTIONS.

l 07 13 NOT USED.

07-14 NOT USED.

NOT USED.

07 15 l

07 16 LS 34 CTS are revised to add a note to allow separate condition entry for each inoperable [ main feedwater isolation valve (MFIV)]. The CTSs as written permit a single valve to be inoperable but would require entry into 3.0.3 if more than onevalvewere[

r_

This change is acceptable in i

I m0 view of the low probability of an event requiring 3,q gp feedwater isolation while a [MFIV] is inoperable and CA considering the availability of other design features to provide backup for the feedwater isolation function.

Not applicable to Callaway. See Conversion Comparison 07-17 Table (Enclosure 38).

i 08 01 LG The requirement to perform Analog Channel Operational Tests (ACOTs) and Channel Calibrations would be moved to licensee controlled documents to maintain consistency with NUREG 1431 format. This is acceptable because it is an example of relocating details not required to be in TS.

08 02 A

A note is added to the ACTION that references a potential interaction with ITS 3.4.6 dealing with operability of the RHR system in H0DE 4.

The note requi, es that the applicable TS be entered for the RHR t, ain made inoperable by the inoperable [ component cooling water (CCW)] system.

The ACTIONS of the referenced TS (RCS Loops-HODE 4) i require more immediate action tht.n are required by the

[CCW] ACTIONS.

08 03 LG The requirement to perform the 18 month surveillance "during shutdown" to avoid plant transients is moved to the Bases.

08-04 A

A note is added to the [CCW] surveillance that clarifies I

that the system is not made inoperable by the isolation of individual components. This change is in accordance with NUREG-1431. Rev.1. and provides clarification only. ~

DESCRIPTION OF CHANGES TO CURRENT TS 10 5/15/97

ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.9-7 APPLICABILITY: DC, CP, WC, CA REQUEST:

CTS 3.9.4 c 1) Footnote" (Comanche Peak) '

CTS 3.9.4 c 1) Footnote" and 4.9.4.1 Footnote" (Callaway)

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.

l 1

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. 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 j

consistent with traveler TSTF-68, which should justify rapid approval by the NRC. This traveler is of sufficient value in 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 concerned 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 l

9-03-LS-8 is revised to include the following information:

"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 fuel assemblies within containment provided that specified administrative controls were employed. The proposed Note is acceptable based on administrative controls that 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 administrative controls used

]

to establish containment closure for a containment 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 ir,adiated fuelinside contairment provided that administrative controls are in place to quickly close one door and establish containment closure.

The isolation valve, or temporary closure device, serves to limit the consequences of accidents. The proposed change would ensure the isolation valves, or functional 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

. ~

-.-~ - -.

sucn that the results of tha analyses in the Safety Analysis Report remain bounding. In considering the consequences of a design basis fuel handling accidents inside

'j 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 preliminarydose calculation has been completed in accordance with the Reviewer's Note added by WOG-76. This calculation shows sufficient time for closure with acceptable dose consequences.

FLOG SUPPLEMENTAL RESPONSE:

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 initiellicense amendments for the FLOG plants. In order to facilitate the issuance of these initiallicense 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 alternate approach is hereby provided as an interim submittal to allow issuance of the initiallicense amendments. The changes which rely upon the 1

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 ITS 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:

Encl. 2 9-4 Encl. 3A 5

Encl. 38 3

Encl. 4 1,48,49,50 Encl. 5A Traveler Status pages, 3.9-5, 3.9-6 Encl. 5B B 3.9-15, B 3.9-16, B 3.9-17 Encl. 6A 2, 3 Encl. 6B 2

-s 1f.4 J

g i

REFUELING OPERATIONS I

i

,. m 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS

)

%./ LIMITINO CCMCITION FOR OPERATION 1

3.5.4 The containmeni. building penetrations shall be in the following status:

1

)

The equipment door closed and held in place by a minimum of four a.

bolts, e

l 1'

b.

A minimum of one door in the emergency airlock is closed and one door 4- 01 LG i

in the personnel airlock is capable of being closed $f and N's.9 7)

\\

Each penetration providing direct access from the containmen l

c.

i atmosphere to the outside atmosphere shall be either:

gM I

1)

Closed by an isolation valve, blind flange, or manual valve, or q.o9.ts i

2)

Be capable of being closed by an OPERABLE tute-tic containment 4-01-LG j

purge isolation valve.

j APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within i

the containment; I

\\

EllQli:

4 1

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.

$ 30-SURVEILLANCE RE0VIREMENIS _ _ --

i h +w @ _. N.m eu 1aJr.

4.9.4.1 Each of he aFove~ required containmeni ou iding penetration all be determined to be. ither i-it: required tenditi:n r ::p:ble of t,e,nv uluwd by i

e i

n 0"E"f.SLE ut:=ti: cent:in=rt purge irehtien valve witMa 100 heur: prier 4-02.-L5 l

to tr.: : tert et :nd et 1 ::t One: p:r 7 d:y: during C0"E ALTE",ATION" or

===nt of irr:di:ted feel 4-th: contai =nt building by:

2 Verifying the penetratien: tre 4a thei-required cenditien, er l

h b.

T : ting the centtia-ent purge 1:chtier volve: per th :pplic:bl:

22-itene cf " crifbtien i.5.2.L hbbh i s. M. -

P****

a e

a+ w %a,.a,.c.c.w e. m. pR. %.~ta ve:.nm si.-/. p 4-03-LS W,;q ac

_ x.

is m s or i

f.0.t.Z VTity In: tr:p ::tp01.! concen,tra!1:n valuf f:r,C:ntli--':nt, Purge 4-04-TR

.......u....

ce..,..r..,-

a _ _ cege gt,.

n..e e, s, 4.

,r-nc,,

r m..m__._

v =nt of i r:diated fut' with4-th: containant. 9-os -e g.

.v om en m rw" gu t o *3,vT o....................

'-01-Lh

1) Appr:pri:t: per::nn:1 cre :=r: th:t both per: nnel :irlock d: ri cre--

epen,

2) A :p::ified individu:l(s) i: de:!gnated 2nd available t: clete the 21*lecP following a r: quired evacuation of cent:in=nt, :nd

-2) Any Ob:truction(:) (e.g., ::ble: and he:::) th:t eculd prevent cle:ur: Of en Op;n irlock ::n b; quickly r;= ved.

CALLAWAY - UNIT 1 3/4 9-4 Amendment No. M,114

CHANGE NUMBER HSHC DECRIPTION Rev.1 and removes 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 P'" * " <

Insert QSM Los.%1 4 06 LS 23 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38).

4 07 LG The specific administrative controls used to assure personnel airlock closure capability would be moved from the LC0 to the Bases. This change removes 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.

4 08 LG Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38).

4-09 LS 14 LCO 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 Rev. 1.

Merr 0%En 4-10 ds footno stating hat penetr ion flo aths

• hat cvi direct cess fro the contai nt atmo here to out 'de atmos ere may unisolate under g%]

inistr tive con ols.Shi change is onsistent th tr eier 76 and n previo ly approv dm istrati control or perso el air lo s.

s 5 01 R

Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38).

I 6 01 R

Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38).

7 01 R

Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38).

8 01 A

This change, consistent with NUREG-1431 Rev.1, provides technical guidance and clarification that loading i

irradiated fuel assemblies in the core is the specific activity of concern that could increase the reactor decay l

heat load. This is not a technical change because, under these conditions, the only activity that could increase reactor decay heat load is loading irradiated fuel into l

)

the reactor vessel.

N..

CESCRIPTION OF CHANGES TO CURRENT TS 5

5/15/97

=. _ _. -

MN w

=**%,u-m..r.c.

Q 3.9-7 x

NSERT 3A-5a N

~

l A no

's added to LCO 3.9.4.c and the 7-day SR to state that containment penetrations that k provide ' ect access from the containment atmosphere to the outside atmosphere may b open 1

under admi trative controls. The note would allow these penetrations to be unisolat during CORE ALTE lONS and movement of irradiated fuel assemblies within contain t provided that specified adm 'strative controls were employed. The proposed Note is a-ptable based f

on administrative con is that consist of written procedures that require de nated personnel having knowledge of the en status of the valves in question and speci d persons designated 4

and readily available to isola the open penetration in the event of a el handling accident.

These administrative controls pr 'de protection equivalent to th fforded by the administrative controls used to establish containme closure for a contain t personnel airlock. The NRC f

staff has allowed changes to the require nts for airlock at allow both doors of an airlock to be open during CORE ALTERATIONS and ing mo ent of irradiated fuel inside containment provided that administrative controls are in plac quickly close one door and establish containment closure.

The isolation valve, or temporary clos device, serves to it the consequences of accidents.

The proposed change would ensu he isolation valves, or fu

'onal equivalent, will perform 3

their required containment clo e function end will serve to limit th onseqt.ences of a fuel handling accident as desc ' ed in the Safety Analysis Report such that results of the I

analyses in the Safety

• alysis Report rernain bounding. In considering the sequences of a design basis fuel dling accidents inside containment, the assumptions in the lysis take no credit for the c..iment as a bamer to prevent the postulated release of radioactivi For I

f events th ould occur during CORE ALTERATIONS or movement of irradiated fuel l

asse ies, containment closure is considered a defense-in-depth boundary to prevent u ontrolled release of radioactivity.

i y h --

s l

i

\\

i i

i

- ~ _ _ _ _. -..

e,A

.g Lh

\\

\\..

m 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 4-04 Revised Surveillance requirement to allow fc* intreased 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 Hoves SR to verify the trip set point concentration value No - not in CTS No - not in CTS No not in CTS Yes - Moved to FSAR LG for the Containment Purge Monitors is reset during CORE ALTERATIONS or other movement of irradiated fuel in 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 No - not in CTS Yes No - Amendment 95 Yes LG personnel airlock closure capability would be moved from did not put admin the LCO to the Bases, controls in LCO.

4 08 Hoves 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 Yes Yes No - already in CTS Yes LS-14 functional equivalent of a valve c2 blind flange to isolate (Amendment 74)

~

containment penetrations.

p tes-M

-Ye1F N4 h

NA Wes-AgA 4-10 sa t te att h

ra on i LS-20 ro id di t

ces f 1.

.t i. t v

"b 3*i h o sir at sph e y

uniso at j

g a' I istr tiv_ con

(

o 5 01 This change relocates the current TS section dealing with Yes - See Yes - relocated to No - relocated per No - relocated per R

maintaining direct comunication between the control room 1. page TRM Amendment 89 Amendment 103 and the refueling station.

19.

i 6-01 This change relocates the current TS section for the Yes - See Yes - relocated to No - relocated per No - relocated per R

[ Refueling Hachine]. 1, page TRM Amendment 89 Amendment 103 21.

t CONVERSION COMPARISON TABLE - CURRENT TS 5/15/97

.ae.

.pw l

h ENCLOSURE 4 i

m 1

• .. d U NO SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC)

CONTENTS I.

Organization................................................................ 3 II.

Descri pti on of NSHC Eval uations............................................. 4 III.

Generic No Significant Hazards Consideration Determinations "A"

Admi ni st rati ve Cha nges................................................ 6 "R"

Relocated Technical Speci fications.................................... 8 i

"LG" - Less Restrictive (Movi ng Information Out of the Techni cal Speci fi cations)............ 11 "M"

More Restri cti ve Requi rements........................................ 13 l

IV.

Specific No Significant Hazards Consideration Determinations "LS" i

LS 1...........................................................

........... 15 l.

LS 2.......................................................................

18 LS 3....................................................................... 20 1

LS.4.......................................................................,9.3 i

LS 5....................................................................... 25 LS 6....................................................................... 27 LS-7....................................................................... 29 LS 8....................................................................... 31 LS 9............................................................. Not a ppl i ca bl e i

LS 10...................................................................... 34 LS 11...................................................................... 36 LS 12...................................................................... 38 LS 13...................................................................... 40 LS 14...................................................................... 42 LS 15......................................................................

44 l

LS 16....................................................................... 46 l

LS-17.................................................................Not used LS 18.......................................................... Not a ppl i c a bl e g g,r; LS - 19........................................................

1. N ot a ppl i ggb_le LS 2 0........................................................ {fot. UWD LS.21.......................................................................

LS 22......................................................................

54 LS 23........................................................... No t a ppl i c a bl e LS 24...................................................................... 56 LS-25..........

.......................................................... 58 l

i l

NO SIGNIFICANT HAZARDS CONSIDERATION 1

5/15/97 l.

3A IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-20 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS A note is added to

.0 3.9.4.c and the 7 day SR to state that c tainment penetrations that pro ide direct access from the containment mosphere to the outside atmosphere may open under administrative controls The note would allow these penetrations to be nisolated during CORE ALTERATION and movement of irradiated fuel assemblies ithin containment provided th t specified administrative controls were employed. Thi note is in accordance wit traveler WOG-76 to NUREG 1431 Rev. 1.

The propo Note is acceptable sed on administrative controls that consist of writte arocedures that reg re designated personnel having knowledge of the open status of t valves in ques on and specified persons designated and readily available to solate the e n penetration in the event of a fuel handling accident. These admini rative cc rols provide protection equivalent to that afforded by the administrative ontrole used to establish containment closure for a containment personnel airl k.

he NRC staff has allowed changes to the requirements for airlocks that allow doors of an airlock to be open during CORE ALTERATIONS and during movement of ir a iated fuel inside containment provided that administrative controls are in plac to ickly close one door and establish containment closure.

-w This proposed TS change has been ev uated and it h been determined that it involves no significant hazards co sideration. This etermination has been performed in accordance with the riteria set forth in 0 CFR 50.92(c) as quoted below:

"The Cor:rnission may ke a final determination, purs nt to the procedures in 50.91, that a prop ed amendnent to an operating licet e for a facility licensed under 50 21(b) or 50.22 or for a testing facil' y involves no significant haz ds consideration, if operation of the f 111ty in accordance with the prop ed amendnent would not:

1.

Inv ve a significant increase in the probability or co equences of an a ident previously evaluated; or 2.

Create the possibility of a new or different kind of acciden from any l

accident previously evaluated: or i

Involve a significant reduction in a margin of safety. "

The iollowing evaluation is provided for the three categories of the dgnificant h ards consideration standards:

i-1.

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

NO SIGNIFICANT HAZARDS CONSIDERATION 48 5/15/97 t

lQ 5,9 A IV. SPECIFIC NO SlGNIFICANT HAZARDS CONSZDERAT10NS i

^

NSHC LS 20 (continued)

.s l

Th roposed change involves changes to the Technical Specificati requ ements for containment closure which is an accident mitiga 'ng feature.

The ch Jes would not affect the likelihood of occurrence of a accidents previous evaluated. The proposed change does not involve a hardware or plant dest changes. The containment leakage value is not sumed to be an initiator o ny analyzed event. The isolation valve, or t rary closure device, serves to limit the consequences of accidents. T proposed change j

would ensure the isolation valves, or functional equival

t. will perform their required co ainment closure function and will se e to limit the consequences of a f 1 handling accident as described 'n the FSAR such that

~

the results of the an lyses in the FSAR remain boundi 9 In considering the consequences of a desi basis fuel handling accide s inside containment, the assumptions in the analy s take no credit for the containment as a barrier to i

prevent the postulated rel se of radioactivity. For events that would occur during CORE ALTERATIONS or vement of irradiat fuel assemblies, containment closure is considered a defen in depth boun ry to prevent uncontrolled release of radioactivity. Addi ionally, the roposed change does not impose any new safety analyses limits o alter the plant's ability to detect and l

mitigate events. Therefore, this ange es not involve a significant increase in the probability or cons en s of an accident previously evaluated.

2.

Does the change create the po sibi 'ty of a new or different kind of accident from any accident evious1 evaluated?

The proposed change involves re iance on manua actuation of containment l

penetration valves or closure evices rather tha automatic systems or passive devices (blank flanges or el sed valves) to block e unimpeded flow of the containment atmosphere to e environs. The propos change would not necessitate a physical al eration of the plant featur that provide core cooling or suberiticali (no new or different type of quipment will be installed) or changes n parameters governing plant oper tion during CORE ALTERATIONS or mov t of irradiated fuel in containment. Thus, this change does not create the possibility of a new or different kind accident from any accident prev' usly evaluated.

3.

Does thi change involve a significant reduction in a mar 'n of safety?

l The propose change is similar to the use of administrative control to isolate a open containment airlock door. The use of administrative ontrols in this anner has been approved by the NRC staff for plant operations that would t require the containment to maintain a pressure boundary. Thi scen io is applicable during plant shutdown for refueling when CORE ALT TIONS and movement of irradiated fuel assemblies in the containment i

o sur. The accidental damage to the spent fuel during these operation are lassified as fuel handling accidents. The proposed change has been develope N SIGNIFICANT HAZARDS CONSIDERATION 49 5/15/97 i

Q LR A IV. SPECIFIC NO SIGNIF8 CANT HAZARDS CONSIDERATIONS NSHC LS-20 (continued) considering the 1 rtance of the containment bo ary in limiting the consequences of a des basis fuel handling ident. The proposed change allows for protection equ lent to that vided by previously approved methods of containment closur. Consi ing the probability of an event that

+

would challenge the containment ary, the alternative protection provided by this change, and the operati 1r irements to occasionally open these penetrations, the proposed nge is acce ble and any reduction in the margin of safety insigni ' ant.

NO SI CANT HAZARDS CONSIDERATION D NATION 3ased on the abov valuation, it is concluded that the activitie ssociated with NSHC "LS-20" r 1 ting from the conversion to the improved TS format tisfy the no significant azards consideration standards of 10 CFR 50.92(c); and acc ingly, a no signi cant hazards consideration finding is justified.

N0 SIGNIFICANT HAZARDS CONSIDERATION 50 5/15/97

Industry Travelers Applicable to Section 3.9 TRAVFI FR #

STATUS DIFFERENCE #

COMENTS

~TSTF 20 Incorporated 3.9 2 NRC approved.

TSTF 21

/S/ Incorporated Not Applicable

""O :pprej f.j o^g h hTA-3.9.a; ;

.TSTF 23, Rev.-e-Incorporated 3.9 13 Traveler bracketed 3

ITS 3.9.2 and revised the i

Bases for 3.9.3.

Bracketed l

Bases information from the i

traveler that is not

.q_g,9g applicable to a specific L

plant was not incorporated.Ngc l

yp=1.

i

[

TSTF 51 Not Incorporated Not Applicable Requires plant specific reanalysis to establish decay tiu dependence for i

fuel handling accident.

TSTF 68. Rev. 1 Not Incorporated Similar chances (Difference

1. 3.9 1) were incorporated j

into the ITS based on 1

l current licensing basis.

TSTF-92. Rev. 1 Not Incorporated Not Applicable Not NRC approved as of traveler cut off date.

TSTF96,/ev, /

Incorporated 3.9 4 NRC approved.

TSTF 136 Incorporated-Not Applicable Ngcaffaved

-77 3,9.g2

'TSTF 153 Not Incorporated Not Applicable

":t "P.C 5~; c' d :: ef g,y tr:';;'er :? ff dete.g NY##h Incorporated)

G 3.1 '1 l

/

NE Incorporated 3.9 15

/

t NKc nvel NII*ni j

cL

7. t,S~ uno,ecemy wAa,..,s.+ a~ts.r i

were nVited h sm-lt:/

39,rm-h.

3

(

t-l o

MARK UP 0F WOG STS REV 1 (NUREG 1431) 5/15/97 i

=_

e m.

Containment Penetrations 3.9.4 m

..j 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations 1

LCO.3.9.4 The containment penetrations shall be in the following status:

a.

The equipment hatch closed and held in place by gg bolts:

B-b.

One door in each Sthijgbjefgegg air lock closed L+ sw m A

3.9 1 :-

gi M-iiL. w p. O ' m.4. : and c.

Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1.

closed by a manual or automatic isolation valve. blind flange, o-equivalent or 2.

capable of being closed by an OPERABLE Containment Purge end PS.

Rheust Isolation Systc;;;. M 3,g.73

' A,/V,1L.h i

/

=rx*

w-

[q'33-9' APPLICABILITY:

During CORE ALTERATIONS.

During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIMI l

A.

One or more A.1 Suspend CORE ALTERATIONS.

Immediately containment penetrations not in elQ required status.

A.2 Suspend movement of Immediately irradiated fuel

(

assemblies within containment.

MARK UP OF WOG STS REV 1 (NUREG 1431) 3.9-5 5/15/97 i

l l

Containment Penetrations 3.9.4 l

l

',.C. #u 1

SURVEILLANCE REQUIREMENTS l

SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment penetration is 7 days

/3/J fi/

A i

in the required statusEr!--4. -- -

isfirum

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a i

- ~- - mwai,ww m u.--

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i SR 3.9.4.2 Verify each required containment purge end 1_8 months

.B c2.eust [sjifaggi valve actuates to the ps.

isolation position on an actual or simulated actuation signal.

m. g..:

l l

l j

i MARX UP OF WOG STS REV 1 (NUREG 1431) 3.9 6 5/15/97

l Containment Penetrations B 3.9.4 c-Qp BASES l

BACKGROUND er (continued)

M the minipurge system is not used in MODE 6.

All four 0 inch velvcs are sccured in the cic;;d pcsitica.

The other containment penetrations that provide direct access i

\\

from containment atmosphere to side mosnhere must be G 3'3-7 tsolated on_at, least_one sid,e{

Isolation may be eclieve y an JuvwlE 8utoma 1c a on valve, or by a manual isolai;1on valve, blind flange, or equivalent. Equivalent isolation methods must be approved and may include use of a material that can provide a teraporary, atmospheric pressure, ventilation barrier m y

..n. for the other

~g.

c

.. g containment penetrations during fuel movements.

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APPLICABLE During CORE ALTERATIONS or movement of irradiated fuel assemblies SAFETY ANALYSES 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. 2). Tuci h;rdling acciints, analyzcd in !!cfercacc 3, irclui dropping a singic irradiated fuci ass;cily ord handling tcci cr c hcavy objcct cr.tc cther irradiated fuci essc;ilics.

ws..

..ns u v. ~.. r : n 4 + s w in a h w g r 9

._.___. _ __._._ _..gg m gg m

-we.. i.g,R.g.

The requirements of LCO 3.9.7, " Refueling Gevey is.1 Water Level," and the minimum decay time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 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. 3), defines "well within" 10 CFR 100 to be 25% or less of the 10 CFR 100 values. The acceptance limits for offsite radiation exposure will be 25% of 10 CFR 100 values or th; =C staff cpprovcd licensing basis e g.

spccified fraction of 10 C.7100 limits).

(continued) l HARK-UP OF NUREG 1431 BASES B 3.9 15 5/15/97 1o

i Containment Penetrations B 3.9.4

[

1 ki h BASES j

APPLICABLE Containment penetrations satisfy Criterion 3 of th; OC I;1 icy i

SAFETY ANALYSES St;t;.~..t. -

(continued) 2 l

LCO-This LCO limits the consequences of a fuel handling accident in

}

containment by limiting the potential escapa paths for fission product radioactivity released within containment. The LCO i

requires any penetration providing direct access from the containment atmosphere to the outside atmosphere to be closed except for the OPERABLE containment purge ;rd ;Jau;;t penetrations For the OPERABLE i

containment purge s.-4 ;J.;.u;t penetrations, this LCO ensures that i

these penetrations are isolable by the Containment Purge end j

Ch;;;;t Isolation Syst.

..~..-,.-....y...~...

j LC0 ;raar; trat tre ;;;t _^.i; pur;; e..d ;%ea;t velv; ci;;ur; tir.c; ;p;;.ifi;-J ir tre = ;;n b; e;.hi;;;d ;..d.

trerefere...;;.t

}

tt; ;;;r-,-ti;;.a u;;;d in th; ;;;fety ;raly;i; to ensure that

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releases through the valves are terminated, such that j

radiological doses are within the acceptance limit. M i

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er i

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APPLICABILITY The containment penetration requirements are applicable during

]

CORE ALTERATIONS or movement of irradiated fuel assemblies within (continued) i MARX UP OF NUREG 1431 BASES B 3.9 16 5/15/97 4

4

Containment Penetrations B 3.9.4 BASES vg APPLICABILITY containment because this is when there is a potential for a fuel (continued) handling accident.

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.t In H00ES 1, 2, 3, and 4, containment penetration requirements are addressed by LC0 3.6.1 m

In H00ES 5 and 6, when e

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 Containment Purge end Exh;ust Isolation System not capable of automatic actuation when the purg end o

exheust valves are open, the unit must be placed in a condition where the isolation function is not needed. This is accomplished by immediately suspending CORE ALTERATIONS and movement of 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 position. The Surveillance on the open purge and cxhaust Ts5I&titM valves will demonstrate that the valves are not blocked from closing. Also the Surveillance will demonstrate that each valve operator has motive power, which will ensure that each valve is capable of being closed by an OPERABLE automatic tion signal g a 1 J j.

containment nyrge and cxhaus@hha?$ -.2 R E Ws I

==b

a. 1 a

-. 1 ' t" hf ld iitg' hr im~

h~

9 33.')

"E

D. nl (continued)

MARX UP 0F NUREG 1431 BASES B 3.9 17 5/15/97

r.4m-m#-.

CHANGE NUMBER DESCRIPTION

"(j#

t e

3.9 8 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

3.9 9 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68).

1 3.9 10 Consistent with the current TS, ITS 3.9.7 Applicability is being revised to delete "During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts." The Applicability is being revised because this requirement is duplicative of a relocated.

technical specification requirement for reactor vessel water level during movement of control rods [(relocated technical specification 3.9.10.2)]. The relocated specification places a lower limit on the amount of water above the top of the fuel assemblies in the reactor i

vessel during movement of control rods. The Bases [(CTS 3/4.9.10)]

state that this ensures the water removes 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly in the event of a fuel handling accident (FHA). However, the movement of untrol rods is not associated with the initial conditions of a FHA, and the Bases do not address any concern regarding inadvertant criticality which could lead to a breach of the fuel rod cladding.

NOT OsED 3.9 11 Tn accor3 with eler WOG 76, LCO is modified o permit aT

[

tration ow pat t provides ect access f containee

)

i op.

to he o 1

a pher ta be u sola under a ~ istra ive cont ol. The 1 owance t have contai t flow ths with ir t F

acces, from the ontainment sphere to t ou ide atmosp g.,g Y

l

, unis ed u r

inistrati ntrols is b on confirma dose $

~

' ca ulat ons faf 1 handl ng a ident whi icate acc ab I

r diologi conseque es to imp nt dmini ative c trol that sure th the flow pe rations wil promptly c sed ollowi a

fuel ha in accident, o rovide a d se in depth roach to accep le do conse nces The a nis tive contr reauirement are defined 3.9-12 A N00E or other specified condition of applicability change restriction has been added to ITS 3.9.6 in the LCO Applicability per the matrix discussed in CN 102 LS 1 of the 3.0 package. This restriction prevents reducing the water level above the reactor vessel flange while the RHR function is degraded. (See the LS 1 NSHC in the CTS Section 3/4.0, ITS Section 3.0 package.)

3.9 13 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 6B).

3.9 14 A MODE change restriction has been added to ITS 3.9.1 in the LCO Applicability per the matrix discussed in CN 1-02 LS 1 of the 3.0 4

package. This restriction prevents a transition from H0DE 5 to MODE 6 JUSTIFICATION FOR DIFFERENCES - TS 2

5/15/97

y l

CHANGE NUleER DESCRIPTION tg%

/G if the boron concentration limit for MODE 6 is not met. (See the LS 1 NSHC in the CTS Section 3/4.0. ITS Section 3.0 package.)

TsrF-2*72 3.9 15 LC0 3.9.1 has been revised in accordance with travelerh100 to clarify that boron concentration limits do not apply to the refueling

[ pool] or other flooded areas when these areas are not connected to the RCS. This change is acceptable because the boron concentration limit is intended to ensure that the reactor remains subcritical in MODE 6.

However, when areas containing boron solution are isolated from the RCS, no potential.for boron dilution exists. Therefore, there is no i

need to place a limit on boron concentration in these areas when they are not connected to the RCS. This change is consistent with the intent of the Specification, as described in the Bases, and eliminates l

restrictions that have no effect on safety.

I 3,% S 4

Tsed 4 A-3b Q 3,9-- 7

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l-JUSTIFICATION FOR DIFFERENCES TS 3

5/15/97

O 3.9-7 INSERT 6A-3b 3.9-16.

ITS LCO 3.9.4 is revised to add a Note consistent with CTS 3.9.4. The Note will allow Penetration P-63 (Service Air valves KA V-039 and KA V-118) and 1

Penetration P-98 (Breathing Air valves KB V-001 and KB V-002) to be unisolated under administrative controls. Amendment No.107, dated July 11,1997, revised CTS 3/4.9.4 to add a new limiting condition of operation to state that Penetration i

P-63 and Penetration P-98 may be opened under administrative control during

)

core alterations and movement of irradiated fuel assemblies within the containment.

l l-I l

i h

i l

-9

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 ine NOTE of ITS 3.9.5 is expanded to incorporate current Yes No - not in CTS No - not in CTS No - not in CTS licensing basis allowing the Rm ounp to be removed from service for less than or equal to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for

{

leak testing of the PJR suction isolation v81ves.

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 Rm flows dependant upon the nunter of hours the reactor has been subcritical.

3.9-10 ITS 3.9.7 Applicability is being revised to delete "During Yes Yes Ye Yes r o e CORE ALTERATIONS. except dur tmlatching of

. t v3 r

a

- Q "f.9-S g h1 1s f afi rng/

at r e

n 3.9-11 In accordance with traveler WOG-76, the LCO is modified to Yes Yes Yes Yes permit a penetration flow path that provides direct access from the containment to the outside atmosphere to be unisolated under administrative controls.

3.9-12 A note is added to the Applicability of LCO 3.9.6 Yes Yes Yes Yes indicating that entry into a MODE or other specified condition in the Applicability is not permitted while the LCO is not met.

3.9 13 In accordance with DCPP current 15. LCO 3.9.2 would not be Yes No No No used.

3.9-14 A note is added to the Applicability of LCD 3.9.1 Yes Yes Yes Yes indicating that entry into H00E 6 from M00E 5 is not permitted while the LCO is not met.

3.9 15 LCD 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 RCS.

3.9-U. &ise;+

[Q33-7l 6

s CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97

O 3.9-7 INSERT 6B-3a TECH SPEC CHANGE

- APPLICABILITY NUMBER DESCRIPTION DIABLO COMMANCHE WOLF CREEK CALLAWAY CANYON PEAK 3.9-16 Wolf Creek ITS LCO 3.9.4 is revised to add a Note No No Yes No consistent with CTS 3.9.4. The Note will allow Penetration P-63 (Service Air valves KA V-039 and i

KA V-118) and Penetration P-98 (Breathing Air valves KB V-001 and KB V-002) to be unisolated under administrative controls.

I t

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l i

i

-2.- :-

i ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 5.5-4 APPLICABILITY: DC, CP, WC, CA REQUEST:

ITS 5.5.4 e and Difference 5.5-13 Comment:

WOG 72 has not yet become a TSTF. Use current ITS.

FLOG RESPONSE (original):

This change to ITS 5.5.4 e was prepared in accordance with 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 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 and expect NRC approval once it is re-submitted for review. We request that the NRC keep this as an open item under the assumption that it 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 alternate 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 traveler by the NRC.

ATTACHED PAGES:

Att.18 CTS 6.0/ITS 5.0 Encl. 2 Page 6-17 Encl. 3A Page 4 Encl. 3B Page 3 Encl. 5A Traveler Status Page and Page 5.0-9 Encl. 6A Page 3 Encl. 6B Page 3

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) e.

Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the l

control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as i

reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following (64.n\\cp. sad-1)

Limitations on the :ptrability/of radioactive liquid and 0 2-05-I\\

gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCH, 2)

Limitations on the concentrations of radioactive material released in l', quid effluents to UNRESTRICTED AREAS conforming tg 10 CcR P:rt 20, Appendix B, T:ble II, Cel= 2 02-14-R 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20,;1% and with the 02' ON methodology and parameters in the ODCM,

Qno7, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS confomtida to Appendix I to 10 CFR Part gg Q Determination of cumulative [:3d:re.!ect:Cdos contributions from radioactive effluents for t1e current c endar quarter anderi,o current calendar year in accordance with th methodology and

g. g f-parameters in the ODCMyt le::t :very 31 d:y:,)

W in o

Y h h.f W he & b W [ N."

Q 5 3-Q toMma W concea b Mon a luer

.n Aep di t B, rm z, c eb m n ~2 h t o C F R. to.1 o ci. 10. 2 4 o l,

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• be CALLAWAY - UNIT 1 6-17 Amendment No. 97 103

CHANGE MEB EC DESCRIPT10N 1

02-04 LG The In Plant Radiation Monitoring Program is based on NUREG-0737. Item III.D.3.3. " Improved Inplant Iodine Instrumentation Under Accident Conditions." The CTS requirement for this program is deleted but the program commitment will be in the FSAR and implementing procedures. Any changes to the programmatic provisions in the FSAR would be controlled by 10 CFR 50.59. Moving this information maintains consistency with NUREG 1431, Rev. 1.

02-05 A

Revises the radioactive effluent controls program to reflect wording in NUREG-1431 and format of the Administrative Controls section. The term " operability" is replaced with " functional capability" to avoid confusion with the TS definition of operability.

02 06 A

Consistent with NUREG 1431. the Radiological Environmental Monitoring Program is deleted. The details and description of the program are duplicative of Offsite Dose Calculation Manual (0DCM) requirements. The program only maintains consistency with the requirements of 10 CFR 50, Appendix I.

The ODCM and regulatory requirements provide sufficient control of these provisions and therefore j 4

(tj0k t)SM removing them from the CTS is acceptable.

02-07

'Revi es Rad'oactiv Efflu nt Con rols Pr gram d se pr 'ection to me orig ~ al in ent of prio to i plemen tion o GL 89 01.

3 89 01 rovid the wo ding or the TS (Se tion

.5.4.e) hich'c mbine the requir ments f r cum ative nd pro cted se. T s requ es a p nt to nake pr jected oses r the arter and ear on a 31 d y basi. It i only ecessar and re sonabl to ma a pro ection or the ext 31 days. A lati e dose roject on is ill re ired f r the curren calend r quar r and ar in cordan e wit the

( 00CM./This c/Tange i consis nt wit travel r WOG 72.

02 08 M

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 NUREr 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

The description of the ODCM (or equivalent programs and procedures) was revised to be consistent with NUREG 1431.

The 00CM description is also revised to reflect new 10 CFR Part 20 requirements.

DESCRIPTION OF CHANGES TO CURRENT TS 4

5/15/97

CONVERSION COMPARISON TABLE - CURRENT TS 6.0 Page 3 of 7 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON-COMANCHE PEAK WOLF CREEK CALLAWAY 02 03 The inplementation procedure requirements related to [the Yes No - Deleted from Yes Yes A

security plan.] the process control programs and the CTS per Amendment radiological environmental and offsite dose calculation 50/36 programs are deleted from the CT5.

02-04 The In-Plant Radiation Monitoring Program is deleted from Yes - move to FSAR No - Deleted from Yes - move to USAR Yes - move to the LG the CTS but the program conmiitment will be in the FSAR and CTS per Amendment 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 " operability" is replaced with " functional capability" to avoid confusion with the TS definition of operability.

02-06 Radiological Environmental Honitoring Program is deleted.

Yes No - Deleted from Yes Yes A

The details and description of the program are duplicative CTS per Amendment of ODCH requirements. The program only maintains 50/36 consistency with the requirements of 10 CFR 50. Appendix I.

s rpm hes'N/A M N/A Y,8 N/A Yg N/A 02-07 f evi es dio tiv EffueptCotr

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orgifalite f

pri r o pro ecti ns o me J

/

i eme tat on o GL 751.

7 rJ OT US cM.

02-08 Revises the procedures section to refer to all programs Yes Yes )

Yes Yes

/

H listed in the program section of the Administrative r-Q 5.5-4 y Controls and ensures implementing procedure control for these programs.

02 09 The description of the ODCH (or equivalent programs and Yes No - changes Yes Yes A

procedures) is revised. The ODCH description is also included in CTS revised to reflect new 10 CFR Part 20 requirements.

02-10 Adds new program called " Technical Requirements Manual No - DCPP does not Yes No - Wolf Creek No - Callaway does l

M (TRM)."

have TRH program does not have TRH not have TRM i

program program 02-11 New program requirements. " Safety Function Determination Yes Yes Yes Yes M

Program" and ~ Bases Control Program' would be added.

CONVFRSTON COMPARISON TARI F - CllRRFNT TS 5/16/97

- ~.

fndustry Travelers Applicable to CTS Section 6.0/ITS 5.0 TRAVELER #

STATUS DIFFERENCE #

COMMENTS TSTF 9 Incorporated B PS NRC Approved (Q 34.l4l TSTF 37. Rev. 1 Incorporated 5.6 2 DCPP only

[

[worpon+tb dntt Revi TSTF 52 Incorporated 5.5 4 ou Q 3 6.. t - G s

TSTF 65 Not Incorporated NA Not NRC approved as of traveler cut off date.

TSTF 106, Not Incorporated NA Retained CTS Rev. 1

% havchTR 5.n-ooc}

TSTF 118 Incorporated 5.5-8

(-TST!119 "ct hcc[perate-d NA tSi S]

i TR 7.C> -od }

TSTF-1$8avi [NotIncorporated ptained CTSg Tgs.o. oogJ

(}6Tf 1g1/

/ yicprporated/ / //A2h

[Q 5. 2-l }

TSTF 152, Incorporated 5.6-4 (9Rc Approve.d NTRS.o-o041 hF/I67// / gncg'rpq(ated / / [6 E7D J. cQ 5.2,-( }

(TSTFT3bg 67, ncy 1])

Incorporated 5.6 b ^

M TR S.o- 003 (f0Gr72/ [ [ Jficpr'porAtet' / / /z6#D Q 5.5-4 gQ WOG.G'; 7 Incorporated 5.5-1 N j Q s.s - 2 ]

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M A

Q 5 2-l MARK UP 0F WOG STS REV 1 (NUREG 1431) 5/15/97

r-1 j

Programs and Manuals 1

5.5 J'

if 4p 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Procram (continued) b.

Limitations on the concentrations of radioactive material released in i

liquid effluents to unrestricted areas, conforming to 10ltiine'sM i2ifitfehiti@EiF@iiFsJd 10 CIR 20. Appendix B, Table 2, Column 2; to 5.5 1-6071001"E;20'240T;]

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 00CH:

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released fre; ced unit to unrestricted areas, conforming to PS 10 CFR 50, Appendix I: f jg p,yg,g e.

. -ter;ination of ;;ulatiV; ond picjcctcd d;;; contribution-

[/5/M)3h, redi;;ctive efflucat; for th; current calcad;r uartcr and current calcader y;;r in ;;cerdance with the acthodelegy and pareatcrs in (the000.",eticestcycry31 days.

G55-4'

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. _ _ _. x. _ i _ ---

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I:

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x

% % d4) ch of g.

Limitations on the dose r resulting rom radioactive material l

released in gaseous effluents to areas beyond the site boundary g

5.5 1

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3m; (continued) i MARX UP 0F WOG STS REV 1 (NUREG 1431) 5.0 9 5/15/97 l

I l

l CHANGE NUMBER JUSTIFICATION

~'

SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test l

frequencies") to provide consistency with current application of these requirements. This is consistent with the use of current TS and alleviates potential confusion in the program descriptions. This change is consistent with traveler TSTF 110.

5.5 9 Not applicable to Callaway Plant. See Conversion Comparison Table (Enclosure 6B).

5.5 10 Section 5.5.12c specifics a surveillance program to ensure that the quantity of radioactivity contained in all outside liquid radwaste tanks that are not surrounded by liners, dikes, or walls is less than the predetermined quantities. This change lists the tanks that the surveillance program is applicable to as is in the current licensing basis. This change is a plant specific requirement consistent with the CTS.

5.5 11 The documents referenced for the testing frequency for the Ventilation Filter Testing Program (VFTP) do not provide frequencies for combined pressure drop tests or the heater power rating test. The current TS frequency is added for these tests.

5.5 12 Not applicable to Callaway Plant. See Conversion Comparison Table (Enclosure 6B).

g gc;gp 5.5 13 i chang revis s Radio tive E fluent Control Progr m dose r jectio s to t origi al inte t of prior to impl nta ion of G 89 01. GL 8 -01 prov ded the wordi for t e STS ( ectio 5.5.4 )

/

ich co ined he req rements for c ulativ and pr jecte dose.

his r ires plant o make roject d dose for th quar er and ear on a 3 day b sis. I is on1 neces ary an reason ble make proje ion f the n xt 31 d ys. A umula ive dos projction s sti i requ ed fo the c rent ca endar arter and yea in accorda e wit the CM.

his is consist nt wit WOG-7.

LT s Tr-- 2.TD 5.5-14 ITS Section 5.5.7 is being revised consistent wi h WCC uD [ ].

The M S.5-2 !

proposed changes to Section 5.5.7 provide an exc ion to the examination requirements in Regulatory Guide 1.14, Revision 1. " Reactor Coolant Pump Flywheel Integrity." The proposed exception to the recomendations 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 i

Elimination."

l JUSTIFICATION FOR DIFFERENCES TS 3

5/15/97

(

fj )

l

's i

CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 3 of 4 i TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 5.5-9 Revises Section 5.5.12c to clarify for Diablo Canyon that Yes No No No tenporary outdoor liquid radwaste tanks are covered under the surveillance program. This 1: consistent with current plant practices.

5.5-10 This change lists the tanks that the surveillance program No - DCPP CLB does No - Not part of Yes Yes in Section 5.5.12c is applicable to as is in the CTS. This not list tanks.

CTS. maintaining change is a plant specific requirement consistent with the ITS wording.

CTS.

5.5-11 The documents referenced for the testing frequency for the No - See CN 5.5-12 Yes Yes Yes Ventilation Filter Testing Program (VFTP) do not provide frequencies for conbined pressure drop tests or the heater power rating tests. The current TS frequency is added for i

these 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 Q 5.5 }

part of the 24 month fuel cycle program for DCPP (see LAR

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N tivf Eff Nt ontr is Progfam/ lose /

(p /A yest'lA JeO/A Ye(M 5.5-13

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! pr jec ons o t or ina int t f TS[pr16r td T5TF 23h y

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[l ntat on GL

01. (

72 y

Section 5.5.7 is being revised cb sistent h h N [ ].

Yes Yes Yes Yes 5.5-14 The proposed changes to Section 5.5.7 proviuc.. wpnon to the examination requirements in Regulatory Guide 1.14.

Revision 1. " Reactor Coolant Pung Flywheel Integrity."

5.5-15 This change provides a time interval of within 31 days No No No Yes following removal in which a laboratory test of a sample obtained from the charcoal adsorber must te tested. This change is consistent with the Callaway CTS.

5.6-1 Revises Section 5.6.4. " Monthly Operating Report." for No Yes No No Comanche Peak to reflect a revised submittal date. This change is consistent with the CTS.

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