Text

Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio
	ML20202D125
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Site:	Wolf Creek
Issue date:	02/04/1998
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
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Attachm:nt IV to ET 98-0007

. Pcgs'l of-7

+

h ATTACHMDIT IV PROPOSED TECHNICAL SPECIFICATION CHANGES CURRENT TECHNICAL SPECIFICATIONS ~

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Attachment IV to ET 98-0007 Page 2 of 7

' POWER' DISTRIBUTION LIMITS -

3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION

3 u

3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY: MODE 1, above 50% of RATED THERMAL POWER *.

.A.CTION:

A a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 tmt-r] -

less then er equel te 1.C3.

C:lculat: th: QUADRT,NT POWER TILT RATIO at leest ence per he- -'

ther:

q a) The QUADRANT P R reduced to within its limit, or-a p _ MAL POWER is reduced to less than 50% of R AL r mn.

2. Within 2 h: r: either-er) Reduce the QUA0 RANT POWER TILT RATIO te withir it:

-limit, er w

h -+)-- Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in 1.00 men 2.houc excess of!1 and similarly redu : th: P:wcr R:ng: Meutrer

fu ca.ch o uADRAWT flux iligh 77ip U tpOint; WitH C th0 30Xt d heur .

power rn.T RATIO (de.termin>h6n,onvi, a yg7j fj thet the quAggAg7 p0g; g 7IL7 gA7;c ;, ,, t;,;,, , t, ; ;,,,; L -

in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THE POWE less than 50% of RATED THERMAL POWER with e next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months an uce the Power-Range Neutron F igh Trip Setpoints to less n or equal to 55% TED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , d L . Identify and correct t ause of ut-of-limit condition prior to increas ERMAL POWER; subse -

POWER OPERATION above 50% o ED THERMAL POWER mdy proceed p ded that the QUAD A oiler TILT RATIO is verified within its lim t least per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable a er greater RATED TllER"AL POWER.

See Special Test Exception Specification 3.10.2.

WOLF CREEK - UNIT 1 3/4 2-11

Attachment IV to ET 98-0007 Page 3 of 7 POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued)

_).

b With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due misalignment of either a shutdown or control rod:

Calculate the QUADRANT POWER TILT RATIU at least once per hour until either:

a The QUADRANT POWER TILT R$TIO is reduced to wit n j[{ its limit, or b) ERMAL POWER is reduced to less than 50% o RATED THERMAL P0 R.

2. Reduce THE AL POWER at least 3% from RATED ERMAL POWER for M each 1% of i icated QUADRANT POWER TILT R 10 in excess of 1, within 30 m utes;

3. Verify that the Q DRANT POWER TILT RA 0 is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months afte exceeding the li it or reduce THERMAL POWER to less than 5 of RATED THE L POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the ower Range eutron Flux-High trip Setpoints to less than o equal 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; a

4. Identify and correct the cau of the out-of-limit conditicn prior to increasing THERMAL 0 ; subsequent PCWER OPERATION above 50% of RATED THERMA POWER ay proceed provided that the QUADRANT POWER TILT RATI is verif d within its limit at least once per hour for 12 h rs or until rified acceptable at 95%

or greater RATED THER L POWER.

c. With the QUADRANT POWER ILT RATIO determined exceed 1.09 due to causes other than the 1salignment of either a s utdown or control rod:

1. Calculate th QUADRANT POWER TILT RATIO at leas once per hour until eithe 4 a) The UADRANT POWER TILT RATIO ie- reduced to wit 'n i limit, or b) HERMAL POWER is reduced to less than 50% of RATED T RMAL POWER.

i WOLF CREEK - UNIT 1 3/4 2-12

Attachment IV to ET 98-0007 Page 4 of 7 POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) educe THERMAL POWER to less than 50% of RATED THERMAL APf w1 hours'and reduce the Power Range Neutron _utt-High Trip Setp to less than or equal to 55% ED THERMAL POWER within the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and E 3. Identify and correct the cap f he out-of-limit condition prior to increasing TH AMAT. POWERt POWER (; sunsOPERATION above 50% of RATJ ERMAL POWER may procee ed that the at least QUADRANT once p P0 ER11LT RATIO is verified within itsour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until veri JATTD THERMAL POWER.

h/. The provisions of Specification 3.0.4 are not applicable.

SURVEILLf.NCE REQUIREMENTS _

4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the-limit above 50% rF RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and

b. Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT P0'WER TILT RATIO shall be determined to be within the limit when hbove 75% of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

WOLF CREEK - UNIT 1 3/4 2-13

_ - - - - _ _ _ _ _ _- - - - - - _ . _ _ J

Attachment IV to ET 98-0007-tPage 5 of 7 em 4 -

POWER DISTRIBUTION LIMITS: -

c. BASES' ~4

-DUADRANT POWU' TILT RATIO '(Continued)

. ... ..... . .me a11 vw...w iv_r........................___.,

than l. han-l.09 Wincation and I

orrection of a droppe .9-does not correct M .'is provided-aar' gin Ph' rod in the event such ACTIO i on F (X,Y,Z) is-gred,ucing the maximum allowed powe. /

.. p y .. .. [

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable,-the moveable-incore detectors are used.to confirm that -

the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitorin flux map or two sets of.four symmetric thimbles.gThe is'done withof two sets a four full incore symmetric thimbles is a uniqua set of eight detector locations. These

. locations are.C-8, E-5,_E-11, H-3, H-13, L-5, L-11, N-8.

3/4.2.5 'ONB PARAMETERS The limits on the Reactor Coolant System T and the pressurizer-pressure assure that each of the-parameters arelaintained within the normal steady-state envelope of operation assumed in the transient and accident-analyses. The limits are consistent with the initial USAR assumptions and 4 have been. analytically demonstrated adequate to maintain a DNBR above the safety analysis limit DNBR specified in the CORE.0PERATING LIMITS REPORT (COLR) throughout each analyzed transient. The indicated T value of.

590.5'F and the indicated pressurizer pressure value of 222Pps19 correspond to analytical limits of 593.0*F and 2205 psig respectively, with allowance for measurement uncertainty.

The 12-hour periodic surveillance of-these parameters through i;...rument readout-is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

Fuel rod bowing reduces the value of DNB ratio. ' Credit is available to offset this reduction-in the generic margin. The generic margins completely offset any. rod bow penalties. This is the margin between the correlation DNBR p' limit and.the safety analysis limit DNBR. These limits are specified in the COLR.

The applicable values of rod bow penalties are-referenced in the USAR.

When RCS flow rate and F no additional allowances are necessary

.,(X,Y), perprior Specification 3.2.3, with to comparison are measured, the limits in the COLR. Measurement uncertainties of 2.5% for RCS-total flow rate and 4%

for F,,(X,Y) have been allowed for in determination of tiie design DNBR value.

1-WOLF CREEK - UNIT 1 B 3/4 2-3 Amendment No.. H ,H ,69,72

Attachment IV to ET 98-0007-Page 6 of 7 CURRENT TECHNICAL SPECIFICATION (CTS) AND CTS BASES INSERTS INSERT At

2. Determine the QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and

3. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions . im a THERMAL POWER reduction required by ACTION a.l., and once per 7 days thereafter:

a) Confirm that the Heat Flux Hot Channel Factor Fo(Z), is within its limit by performing Surveillance Rcquirement 4.2.2.2, and b) Confirm that Nuclear Enthalpy Rise Hot Channel Factor, F5m, is within its limit by performing Surveillance Requirement 4.2.3.1, and

4. Reduce the Power Range Neutron Flux-High Trip Setpoints 2 3% for each 1% of QUADRANT POWER TILT RATIO > 1.00 within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each QUADRANT POWER TILT RATIO determination, and

5. Prior to increasing THERMAL POWER and Power Range Neatron Flux-High Trip Setpoints above the limits of ACTION a.l. and a.4., reevaluate the safety analyses and confirm that the results remain valid for the e duration of operation under this condition, and

6. Prior to increasing THERMAL POWER above the limit of ACTION a.l.,

normalize excore detectors to restore QUADRANT POWER TILT RATIO to within limit, r.nd

7. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions not to exceed 48 hourr after increasing THERMAL POWER above the limit of ACTION a.l.**:

a) Confirm that the Heat Flux Hot Channel Factor Fo(Z), is within its limit by performing Surveillance Requirement 4.2.2.2, and b) Confirm that Nuclear Enthalpy Rise Hot Channel Factor, F5g, is within its limit by performing Surveillance Requirement 4.2.3.1.

b. If the requirements of a.l., a.2., a.3., a.4., a.5., a.6., or a.7. above are not met, reduce THERMAL POWER to s 50% of RTP within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

- ACTION a.7. must be completed when ACTION a.6. is performed.

INSERT B:

With QPTR exceeding 1.02, reducing THERMAL POWER to greater than or equal to 3% below RTP for each 1% by which the OPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power. The 2-hour time allowance after each QPIR determinetion allows sufficient time to identify the cause and correct the tilt, or reduce power as necessary. Any additional changes in the OPTR are detected by requiring a check of the QPTR once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

.- Attachmtnt'IV'to ET 98-0007 Pcg3 7 of-7J 4

. . . e

4. f m

ThhmaximumallowableTHERMALPOWERLlevelinitiallydetermined'byActiona.1 may be affected-by-subsequent determinations of QPTR in Action-a.2. Increases in-QPTR would require a--THERMAL _ POWER reduction'within'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of OP*R

- determination, if necessary.to comply with the decreased maximum a. le.

THERMAL POWER level.- Decreases in QPTR would allow raising the maximuu

' allowable THERMAL 1 POWER level ~ and : increasing-THERMAL POWER up. to the revised limit. -The PowerjRange-Neutron: Flux-High Trip Setpoints are similarly.

affected.

The! peaking factors Fo(Z)l and F*a are of primary:importance.in. ensuring'thate the. power _ distribution-remains consistent with the-initial--conditions-used in

^

theJsafety ana? sis. Performing; surveillance requirements on Pg(Z)- and P"a

- within 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s-after achieving-equilibrium conditions with! THERMAL POWER reduced by Action a.l. ensures thatithese-primary indicators of power.

distribution are within their respective limits.

If the QPTR romains above the 1.02 limit and a reevaluation of the safety-analyses is completed and shows.thatEsafety requirements are met, the excore

detectors are normalized to-restore-QPTR-to.within limit prior to increaring.

THERMAL POWER.

I F- I Q, - _ - _ _ - _ _ - -

Attachmsnt V to ET 98-000)

Pega 1 of 9 ATTACHMENT V PROPOSED TECHNICAL SPECIFICATION CHANGES IMPROVED TECHNICAL SPECIFICATIONS e

r- , i

' Attachment V to ET 98-0007 '

s .Page 2.of 9:- OPTR

. . 3.2.4 3.2-- POER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (0PTR)

LCO 3.2.4: The OF1R shall be s 1.02.

APPLICABILITY: MODE 1 witn THERMAL POWER > 50% RTP.

ACTIONS-COM)1 TION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1'- Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after

t 3% from RTP for each each QPTR lt of QPTR > 1,00. detemination.

M A.2 Determine OPTR. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months M

A.3 Perfom SR 3.2.1.1. SR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 3.2.1,2 and SR 3.2.2.1. achieving equilibrium conditions from a THERMAL POER reduction e;;'M b; av Required Action A.1^

~ M Once per 7 days thereafter M

e (continued)

.WCGS ITS 3.2 10 5/15/97

n Attachment V to ET 98-0007 '

. Page 3 of 9 g 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after W_ Neutron Flux High trip each QMTl setpoints := 3% for each determination 1% of QPTR > 1.00.

__ M A.5 Reevaluate safety Prior to k= analyses and confirm increasing results remain valid THERMAL POWER and for duration of Power Range operation under this Neutron Flux-conditio... High trip -

3_ setpoints above

["i . the limit o L J_ Required Actions A.1 and A.4 8

A.6 -NOTE - -

hPerformRequired Action A.6 only after

=

Required Action A.5 is d Actiari A.7 4.113

r. . R 9 rect. p completed.

a _pu se-c.~. ,

Normalize excore Prior to

( .

Rqnd Ac.han A4 m detectors to 'ini nt: increasing perfor m ed .

" ~~

j -444h _b _

THERMAL PNER rh W % above the limit gg g,,.,9, of Required Action A.1 M

(continued)

WCGS ITS 3.2 11 5/15/97

Attachment V to ET 98-0007 Page 4 of 9 3.2.4 1

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.7 NOTE --

Required Action A.7 must be completed when Required Action A.6 is ,

implemented.

Perform SR 3.2.1.1. SR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 3.2.1.2 and SR 3.2.2.1, achieving equilibrium not to eAtejd 4N4h4n 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing TERMAL PGER above the limit of Required-Action A.1 B.. Required Action and B.1 Reduce THERMAL POWER to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion s 50% RTP Time not met.

WCGS ITS 3.2 12 5/15/97 L

Attachment V to ET 98-0007 Page 5 of 9 QPTR B 3.2.4 BASES (continued)

ACTIONS U With the QPTR exceeding its limit, a power level reduction of 3% RTP for each it by which the OPTR exceeds 1.00 is a conservative tradeoff of total core power with peak lit power.

The Congletion Time is 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each OPTR detemir .clon that is performed pursuant to Required Action A.2. The Completion Time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months allows sufficient time to identify the cause and correct the tilt, or reduce power, as necessary. Note that the- a, power reduction 4tse4 may cause a change in the tilted condition, a

After completion of Required Action A.1, the QPTR alam may still be in its alarmed state. As such, any additional changes in the QPTR are detected by requiring a check of the OPTR orce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. If tb 0"", cf.ir=: t inis;e, G "J. ", M ; te k c h d n widir,63 A 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time is sufficient because any additional change in 0FTR would be relatively slow.

U The peaking factors Pan and Fe(Z) are of primary mortance in ensuring that the power distribution remains consistent with the initial conditions used in the safety analyses. Parforming SR3 m [THERP%L PoWd on Pan and Fo(Z) within th9 Completion Time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after h{ re.4LActiin Pacnleving Ac+ ion equilibrium conditions >f:hir.; par 7;d=ti =

.,.....y ,mvi.W klier. A.1 ensures that these primary di _ _

/ indicators of power distribution are within their respective o 11mits.4A Completion Time of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving

< eauilibrium conditions. takes 1(ito consideration the rate at which j peaking factors are likely to change, and the time required to

{ stabilize the plant and perform a flux map. If these peaking factors are not within their limits, the Required Actions associated with these Surve111ances provide an appropriate response for the abnormal condition. If the OPTR remains above its specified limit, the peaking factor surveillances are required each 7 days thereafter to evaluate Pan and Fa(Z) with

. - - I changes in power distributi_on. Relatively small changes are EquMibrium condWie.ns are. ai.hFeve.d when +td core s's sAffic.idnth staWe.

atthe J M ende.d operAtmg canMtibn> to support h mapp'ig ,

(continued)

WCGS ITS BASES B 3.2-24 5/15/97

Attachment L to ET 98-0008--

Page 6_of;9

+ -

QPTR

. . B 3.2.4' e g3 ACTIONS _ M (continued):

~ expected due to either burnup and-xenon redistribution or correction of the cause for exceeding the QPTR limit.

-M--

A reduction of the Power Range Neutro'i Flux-High trip setpoints -

by a 3% for each 1% by which QPTR exceeds 1.00.;is a conservative -

action for protection against the consequences of severe

- transients with potentially unanalyzed power distributions.

Perfomance of this Required Action results _in earlier trip .

'setpoint reduction than would be required pursuant-to the. l

- Reouired Actions of the Fa"n and Fe(Z) specifications. The ;

Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each QPTR determination is1 sufficient considering the small likelihood of a severe transient in this time period and the preceding prompt ion in THmMAL _

. POWER in accordance with Required Action A.I. _

bar bnp Neuh.n Flm.4lpi Trip setp.,M ix NUy datermihed - h.hqmh: 4 As. tins AA 'I _

2 mM b* *ffar+s4 by s. -

+ .n. 4 erra., -~

y si*silar tm +b#.+ %*, uent mac4 A+.rmi rs

..n. a t.,niemmau_

y en.tevenq.+=rm g .A. g g m ,.a.4.t,gn A,g,, j Although F"u6 and Fo(Z) are of primary importance as initial conditions in the safety analyses, other changes in the power

- distribution may occur as the QPTR limit is exceeded'and may have

.an 1spect on the validity of the safety analysis. A change in the power distribution can affect such reactor. parameters as bank worths and peaking factors for rod malfunction accidents. When the QPTR exceads its. limit, it does not necessarily mean a safety-concern exists. It does mean that there is an indication of a change in the gross radial power distribution that requires an-investigation and evaluation that-is accomplished by examining the incore power distribution. Specifically, the core peaking factors and the quadrant tilt must be evaluated because they are the factors that best characterize the core power distribution.

This re evaluation is required to ensure that, before increasing THERMAL to above the limits of Required Actions A.1 and A.4.' the r or core conditions are consistent with the asstapti in the safety analyses.

Power kc. t4eaQn Fb-4ip -bp es 6h (continued)

WCGS ITS BASES B 3.2-25 5/15/97

Attachment V to ET 98-0007 Page 7 of 9 QPTR B 3.2.4 BASES ACTIONS .M (continued)

If the CPTR remains above the 1.02 limit and a re evaluation of the safety analysis is completed and shows that safety fQ MgD requirements ai s met the excore detectors are normalized to

?

'+

m prior to increasing THERMAL POER to D ". above the limit of Required Action A.1. t pecess-of--

j5rmalization is accomplished by measuring curreas for each detector during flux mapping and using this information to normalize the output from each detector (either through calibration of the NI/or through the use of constants in calculations) in sucf5 a manner that the indicated QPTR following normalization is near. l.00. This is done to detect any subsequent significant changes in QPTR. -

ggh) Required Action A.6 is modified No est s hat the u --#rdisted tilt te ..et ellei. d d until after the red $ialuation of 1 '" H_ the safety. analysis has determined that core conditions at RTP dPTR.Wh,"N"'D -

are within the safety analysis assumptions (i.e... Required -

, Action A.5).. "i: " ": i: ntended to prevent any ambiguity about the required _

of_ actions, au. Harss on). -

U C TR ko M L'sh Once the excore detectors are nomalized to " "" "

Hierted-44% (i.e., Required Action A.6 is performed), it is act.eptable to return to full power operation. . However, as an added check that the core power distribution at RTP is consistent with the safety analysis asstaptior.s, Required Action A,7 requires verification that Fa(Z) and Fu" are within their specified limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of achieving equilibrium hEscr '

conditions :^r rent.imi R'" + As an added precaution if-ee.

c;; ;22: i ; st . a;ti ""/ M;.;.;n 24 t. eor;. Lt is 17 a n d g N -1=13. th the peaking factor surveillances must be performed f.aNr inchasnflhERMAL within 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months # ' "M tin ut tb :E st ta gn =: M;=.

I PousR obon.%. limW of These Completion Times are intended to allow adequate time to 41 l increase THERMA 1. POWER to above the limit of Required Action A.1.

N j while not pemitting the core to remain with unconfirmed power F distributions for extended periods of time.

5 Required Action A.7 is modified by a Note that states that the peaking factor surveillances must be completed when the excore (continued)

WCGS ITS BASES B 3.2 26 5/15/97

Attachment V to ET 98-0007 Page 8 of 9 QPTR

, , B 3.2.4 BASES ACTIONS Al (continued) gg g j.

] detectors have been r irma11 zed to 155:te t'; irdicated tilt (i.e., Required Action A.6). The intent of this Note is to have the peaking factor surveillances performed at operating power levels, which can only be accomplished after the excore detectors are normalized to d= =; tilt, nsk<c. QPTR to Mhh hk'.Q ill .

If Required Actions A.1 through A.7 are not completed within their associated Completion Times, the unit must be brought to a MODE or condition in which the requirements do not apply. To achieve this status THERMAL POWER must be reduced to < 50% RTP within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The allowed Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is reasonable, based on operating experience regarding the amount of time required to reach the reduced power level without chailenging plant systems.

SlRVEILLANCE SR 3.2.4.1 REOUIREMENTS SR 3.2.4.1 is modified by two Notes. Note 1 allofs QPTR to be calculated with three power range channels if THERMAL POWER is s: 75% RTP and the input from one Power Range Neutron Flux channel is inoperable. Note 2 allows performance of SR 3.2.4.2 in lieu of SR 3.2.4.1.

This Surveillance verifies that the QPTR. as indicated by the Nuclear Instrumentation System (NIS) excore channels. is within its limits. The Frequency of 7 days takes into account other information and alarms available to the operator in the control room.

For those causes of OPT that occur- quickly (e.g.. a dropped rod),

there typically are other indications of abnormality that prompt a verification of core power tilt.

(continued)

WCGS ITS BASES B 3.2 27 5/15/97

, Attachment V to ET 98-0007 Page 9 c.f 9 INSERT C The maximum allowable THERMAL POWER level initially determined by Required Action A.1 may be affected by subsequent determinations of QPTR. Increases in QPTR would require a THERMAL POWER reduction within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of QPTR determination, if necessary to comply with the decreased maximum allowable o THERMAL POWER level. Decreases in QPTR would allow raising the maximum allowable THERMAL POWER level and increasing THERMAL POWER up to this revised limit.

INSERT D Note 2 states that if Required Action A.6 is performed, then Required Action A 7 shall be performed. Required Action A.6 normalizes the excore detectors to restore QPTR to within limit, which restores compliance with LCO 3.2.4.

Thus, Note 2 prevents exiting the Actions prior to completing flux mapping to verify peaking factors per Required Action A.7.

INSERT E Equilibrium conditions are achieved when the core is sufficiently stable at the intended operating conditions to support flux mapping.

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ML20202D125

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