ML17331B195

Proposed Tech Specs 3/4.1.3,increasing Limit for Control Rod Misalignment at or Below 85% Rated Thermal Power

ML17331B195
Person / Time
Site:	Cook
Issue date:	01/17/1994
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331B194	List: ML17331B193 ML17331B195 ML17331B196
References
NUDOCS 9401270037
Download: ML17331B195 (34)

Text

ATTACHMENT 2 TO AEP:NRC:1182 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9401270037 940117 PDR ADOCK 05000315 P PDR CO 0 34 3 V L C 0'SS LI I NG COND IO FO 0 ON ES F~.-,"..':)~gg all indivIdua,l i4I~~~~P~Q4i~+4.alloMch rod ollsdJ Q<~~~3.1.3.1 All full length (shutdown and control)rods shall be OPERABLE aad-countet,':;de'mand poe'dtdon~

o.s"Q(logs;:,in~W dt8~W+~a ACTION: a.With<one or more full,l'ength rods inoperable due to being immovable as a result of excessive friction or mechanical interference or'nown to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.With more than one full length rod inoperable or misaligned from the I+$m be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.g,uo~re~~is~l tgnm6%~c.With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step+~Jg~counter demand position by more than+hour either: 1.The affected rod is restored to OPERABLE status within the above alignment requirements, or 2.The affected rod is declared inoperable and th'e SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that: e~a)A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days;this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, and b)The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and r>See Special Test Exceptions 3.10.2 and 3.10.4 p ere Wc pn~gcf.<D.C.COOK-UNIT 1 3/4 1-18 AMENDMENT NO.7$p 28, 120

o for THERMAL POWER less than or equal to 85X of RATED THERMAL POWER, the allowed rod misalignment is~18 steps, and o for THERMAL POWER greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is~12 steps or as determined from Figure 3.1-4.Figure 3.1-4 permits for an allowed rod misalignment from J13 steps (for APL equal to 101X)to+18 steps (for APL greater or equal to 106X)provided the value'f R (defined in Figure 3.1-4)is greater than or equal to 1.04.

REACTIVITY CONTROL SYSTEMS LIMITINQ CONDITION FOR OPERATION Continued c)A power distribution map is obta4ned from the movable incore detectors and F (Z)and F,"H are verified to be within their limits wiPhin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and d)Either the"THERMAL POWER level is reduced to less than ,or equal to 75%of RATED THERMAL POWER within one hour and wt:thin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85%of RATED THER."1AL POWER, or, e)The remainder of the rods in the group wit thei<,~~,p~<~l~s inoperable rod are aligned to within--of the inoperable rod within one hour while maintaining the rod t sequence and insertion limits as specified in the COLR;the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.

SURVEILLANCE RE UIREMENTS 4,1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.4.1.3.1.2 Each full length rod not fully inserted shall be determined to be OPHVBLE by movement of at least 8 steps in any one direction at least once per 31 days.4.i.3.l,3~i 0.i(0&rcxk e>scilge~+>+

for~<<AE4 POM<grccd~r SC7.K%mid)meZ~~9cqpep sM(k dt~~4'~~J<+~~~M~~~~~~~+'+

APL s~~X i~~Ac&l~A.Z.LZ.COOK NUCLEAR PlANT-UNIT 1 3/4 1-19 AMENDMENT NO f20, 1 46 REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPEPAHLE and capable of dt ldg g ll'dd"dl.ddl~d rex)e)sotlgHRck Peda~3n~rF>~fj~3,).3,1, APPLICABILITY:

MODES 1 and 2.ACTION: Mith a maximum of one rod position indicator channel per group inoperable either: l.Determine the position of the non-indicating rod(s)in-directly by the movable incore detectors at least once'er 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately af:er any motion of the non-indicating rod which exceeds 24 steps in one direc ion since the last determination of the rod's position, or 2.'Reduce THERMAL POWER TO<50" of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.With a maximum of one demand position indicator per bank inoperable either:~~l.Verify that all rod position indicators for the a,,ec.ed bank are OPERABLE and that the most withdrawn rod and the'east withdrawn'rod of the bank are within a maximum of of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or+4.allo~re, m)swig)g~~

2.Reduce THERMAL POMER to<50" of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.SURV E IL LANC E REOU I R EM EN TS~~14~rM g)l;g~~ry 4.1.3,2 Each rod posiiion indicator'channel shal'1 be dete'rmined.to be OPEPABLE by ver ifying the demand posi.~ion i dication system and the rod l gi~12 hours except during time intervals when the Rod Position tjeviation Monitor is inoperable, h n compare the demand position indication system and the rod positi"n indicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.D: C.COQK-UNIT 1 3/4 1-20 Amendment No.28 POWER DISTRIBUTION LIMITS BASES 3 4.2.2 and 3 4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLFML ENTEiALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factors ensure that 1)the design limits on peak local power density and minimum DNBR are not exceeded and 2)in the event of a LOCA the peak fuel clad temperature'ill not exceed the 2200 F ECCS acceptance 0 criteria limit.Each of these is measurable, but will normally only be determined periodically, as specified in Specifications 4,2.2,1, 4.2.2.2, 4.2.3, 4.2.6.l.and 4.2.6.2.This periodic surveillance is sufficient to ensure that the hot channel factor limits are maintained provided: RE.~lid,~un%%Tan.eS~<X~a.Co carol ro in s ngle gz'p moye ogethpr pith~ip4vi al r d i er on if rin by more ghy+lgspfps fpomAhe rou de and os tion b.Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.c.The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.

d.The axial powez distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.The relaxation in F H as a function of THER.'fAL POWER allows changes in the radial power shape for all permissible rod insertion limits.F>will be maintained within its limits as specified in the COLR, provided condztions (a)through (d)above are maintained.

When an F measurement is taken, both experimental error and manufacturing tolerance must be allowed for.5%is the appropriate allowance for a full core map taken with the incore detector flux mapping system, and 3%is the appropriate allowance for manufacturing tolerance.

When F H is measured, experimental error must be allowed for, and 4%is the appropriate allowance for a full core map taken with the incore detection system.This 4%measurement, uncertainty has been included in the design DNBR limit val'ue.The specified limit for F"H also contains an additional 4%allowance for uncertainties.

The total allowance is based on the following considerations:

COOK NUCLEAR PIANT-UNIT 1 B 3/4 2-4~i/Q fili ANEHDMEHT No.7g, f29, 146 Control rods in a single group move together with no individual rod insertion differing by more than~18 steps from the group demand position (allowed rod misalignment) for power levels less than or equal to 85X of RATED THERMAL POWER.For power levels greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is from+12 to J18 steps, which is dependent on the Allowable Power Level and the ratio of FN~limit at 100X of RATED THERMAL POWER to maximum measured F~as indicated in Figure 3.1-4.

REACTIVITY CONTROL SYS E S 3 4 1 3 OV BL CONTROL SSEMBLIES LIMITING CONDITIO FOR OPERATION~gg J(;PJtviJaal iAJIca:t4 M Pok~~Ivl t4 O.lkock M~ISc 1'IcJyhq~Ct 3.1.3.1 All full length (shutdown and control)rods shall be OPERABLE and.positioned-wi<hin~2-s-tep~dmaeed-posi.-eicnr) of their group step counter demand positiony g,g~)to~s, 9~JL+c3 ACTION: a~With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />'~With more than one full length rod inoperable or misaligned from the (Xndi~d-poskt~m~

be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.aJ(O~cab~iS~tIgWVn~~

With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand position by more than~@Jl~d'.'.poc~~POWER OPERATION may continue provided that within one mt~ll~~hour either: 1.The affected rod is restored to OPERABLE status within the above alignment requirements, or 2.The affected rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3'.1.1 is satisfied.

POWER OPERATION may then continue provided that: a)A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days;this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, and b)The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and~vE~F'AQF 9)4 l-l9::See Special Test Exceptions 3.10.2 and 3.10.3 D.C.COOK'-UNIT 2 3/4 1-18 AMENDMENT NO.78>]P7 I f 8 o for THERMAL POWER less than or equal to 85K of RATED THERMAL POWER, the allowed rod misalignment is~18 steps, and o for THERMAL POWER greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is J12 steps or as determined from Figure 3.1-4.Figure 3.1-4 permits for an allowed rod misalignment from J13 steps (for APL equal to 101X)to J18 steps (for APL greater or equal to 106X)provided the value of R (defined in Figure 3,1-4)is greater than or equal to 1.04.

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION Continued c)A power distribution map J,s obtained from the movable incore detectors and F (Z)and F'are verified to be within their.limits within 73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br />, ant d)e)Either the THERMAL POWER level is reduced to less than or equal to 75%of RATED THERMAL POWER within one hour and'within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85$of RATED THERMAL POWER, or The remainder of the rods in the group,th<phe~

(+zz~<~/-

inoperable.

rod are aligned to within'f the inoperable rod within one hour while maintaining the rod sequence and insertion limits as specified in the COLR;the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 duding subsequent operation.

SURVEILLANCE RE UIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once pei 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.4'.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 8 steps in any one direction at least once per 31 days.COOK NUCLEAR PLANT-UNIT 2 3/4 1-19 AMENDMENT NO 10yl07yl22

'I

~'I Q~~~r I I~~I~~y~~I~1~~~~~~~~~~~~~~y~~~~~~~0~~~~~~4~~~~~~~~~~~~~~~~~~~1~~~r~~~~0~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~r~~~\~~~I~~~r~'I.~S~~~~~~~~I~~r~~~0'I 0 r~0~

POWER DISTRIBUTION LIMITS BASES 3 4.2.2 and 3 4.'2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ERDVQZY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factor ensure that.1)the design limits on peak local pover density and minimum DNBR are not exceeded and 2)in the event of a LOCA the peak fuel clad temperature vill not exceed the 2200 F ECCS acceptance 0 criteria'limit; Each of these ia measurable but vi'll normally only be determined peziodfcally as specified in Specifications 4.2.2.1, 4.2.2.2, 4.2.3, 4.2.6.1 and 4.2.6.2.This periodic surveillance ia sufficient to ensure that the limits are mafntained provided: RCPCMe ulTED A&acH<b~m a.C6 o rW n ngeg P eye e nd4d 1 j i e ff g o+p mi epa r 6 e d a 4o.b.Control rod groups are sequenced vith overlapping groups as described in Specification 3.1.3.6, c.The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained.

d.The axial pover diatributfon, expressed in terms of AXIAL FLUX DIFFERENCE, ia maintained vfthin the limits.F, vill be aaintafned vfthin its limits as specified in the COLR provided conditions a.thzough d.above are mafntained.

The zelaxation of F as a function of THERMAL POWER allovs changes in the radial pover shape fPz all permissible rod insertion liaits.The form of this relaxation for DNBR limits is discussed fn Section 2.1.1 of this basis.When an F measurement ia taken, both experfaental error and aanu-factuzing tolerance aust be alloved for.5%ia the approprfate allovance on F for a full core map taken vith the incore detector flux mapping system and 3P in th>>appropriate allovance for manufacturing tolerance.

COOK NUCLEAR PLANT-UNIT 2.B 3/4 2 4~~Np.8()722, 0 l I, P Control rods in a single group move together with no individual rod insertion differing by more than J 18 steps from the group demand position (allowed rod misalignment) for power levels'ess than or equal to 85X of RATED THERMAL POWER.For power levels greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is from J12 to~18 steps, which is dependent on the Allowable Power Level and the ratio of FN~limit at 100K of RATED THERMAL POWER to maximum measured FN~as indicated in Figure 3.1-4.

ATTACHMENT 3 TO AEP'NRC'1182 PROPOSED TECHNICAL SPECIFICATION PAGES REACTIVITY CONTROL SYSTEMS 3 4 1 3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3'.3.1 All full length (shutdown and control)rods shall be OPERABLE with all individual indicated rod positions within the allowed rod misalignment of their group step counter demand position as follows: o for THERMAL POWER less than or equal to 85K of RATED THERMAL POWER, the allowed rod misalignment is~18 steps, and o for THERMAL POWER greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is~12 steps or as determined from Figure 3.1-4.Figure 3.1-4 permits for an allowed rod misalignment from~13 steps (for APL equal to 101X)to J18 steps (for APL greater or equal to 106X)provided the value of R (defined in Figure 3.1-4)is greater than or equal to 1.04.APPLICABILITY:

MODES 1*and 2*ACTION: a.With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.With more than one full length rod inoperable or misaligned from the group step counter demand position by more than the allowed rod misalignment, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.c.With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand position by more than the allowed rod misalignment, POWER OPERATION may continue provided that within one hour either: 1.The affected rod is restored to OPERABLE status within the above alignment requirements, or 2.The affected rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that: a)A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days;this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, and*See Special Test Exceptions 3.10.2 and 3.10.4 COOK NUCLEAR PLANT-UNIT 1 3/4 1-18 AMENDMENT NO.45, Q8, 420

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION Continued b)The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c)A power distribution map is obtained from the movable incore detectors and F<(Z)and F~are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and d)Either the THERMAL POWER level is reduced to less than or equal to 75X of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85X of RATED THERMAL POWER, or e)The remainder of the rods in the group with the inoperable rod are aligned to within the allowed rod misalignment of the inoperable rod within one hour while maintaining the rod sequence and insertion limits as specified in the COLR;the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.

SURVEILLANCE RE UIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 bourse'.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 8 steps in any one direction at least once per 31 days.4.1.3.1.3 The allowed rod misalignment for THERMAL POWER greater than 85X of RATED THERMAL POWER shall be determined in conjunction with the measurement of APL as defined in Specification 4.2.6.2.COOK NUCLEAR PLANT-UNIT 1 3/4 1-19 AMENDMENT NO.~, 446 ALLOWED ROD MISALIGNMENT ABOVE S5%RTP FIGURE 3.i-4 20 STEPS 19 18 17 16 15 14 13 Applicable W ereR=when R cmn-J AH t-N>1.04 NO%ATP 12 100 101 102 103 104 105 106 107 108 APL COOK NUCLEAR PLANT-UNIT 1 3/4 1-19b Amendment No.

REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3'.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the rod positions within the allowed rod misalignment specified in Specification 3.1.3.1.APPLICABILITY:

MODES 1 and 2.ACTION'.With a maximum of one rod position indicator channel per group inoperable either: 1.Determine the position of the non-indicating rod(s)indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.Reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.b.With a maximum of one demand position indicator per bank inoperable either: Verify that all rod position indicators for the affected bank are OPERABLE and that-the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of the allowed rod misalignment of each other, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.Reduce THERMAL POWER to less th'an 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.SURVEILLANCE RE UIREMENTS 4.1.3.2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within the allowed rod misalignment at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indicator, channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.COOK NUCLEAR PLANT-UNIT 1 3/4 1-20 AMENDMENT NO.~

I'~

POWER DISTRIBUTION LIMITS BASES 3 4.2 2 and 3 4 2 3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factors ensure that 1)the design limits on peak local power density and minimum DNBR are not exceeded and 2)in the event of a LOCA the peak fuel clad temperature will not exceed the 2200'F ECCS acceptance criteria limit.Each of these is measurable, but will normally only be determined periodically, as specified in Specifications 4.2.2.1, 4.2.2.2, 4.2.3, 4.2.6.1 and 4.2.6.2.This periodic surveillance is sufficient to ensure that the hot channel factor limits are maintained provided: Control rods in a single group move together with no individual rod insertion differing by more than~18 steps from the group demand position (allowed rod misalignment) for power levels less than or equal to 85X of RATED THERMAL POWER.For power levels greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is from J12 to~18 steps, which is dependent on the Allowable Power Level and the ratio of F~limit at 100X of RATED THERMAL POWER to maximum measured F~as indicated in Figure 3.1-4.b.Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.c.The control rod inserti.on limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.

d.The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.The relaxation in F~as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.F~will be maintained within its limits as specified in the COLR, provided conditions (a)through (d)above are maintained.

When an F<measurement is taken, both experimental error and manufacturing tolerance must be allowed for.5X is the appropriate allowance for a full core map taken with the incore detector flux mapping system, and 3X is the appropriate allowance for manufacturing tolerance, When F~is measured, experimental error must be allowed for, and 4X is the appropriate allowance for a full core map taken with the incore detection system.This 4X measurement uncertainty has been included in the design DNBR limit value.The specified limit for F~also contains an additional 4X allowance for uncertainties.

The total allowance is based on the following considerations:

COOK NUCLEAR PLANT-UNIT 1 B 3/4 2-4 AMENDMENT NO.W, 420, 444 REACTIVITY CONTROL SYSTEMS 3 4 1 3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control)rods shall be OPERABLE with all individual indicated rod positions within the allowed rod misalignment of their group step counter demand position as follows: o for THERMAL POWER less than or equal to 85X of RATED THERMAL POWER, the allowed rod misalignment is+18 steps, and o for THERMAL POWER greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is~12 steps or as determined from Figure 3.1-4.Figure 3.1-4 permits for an allowed rod misalignment from~13 steps (for APL equal to 101%)to J18 steps (for APL greater or equal to 106X)provided the value of R (defined in Figure 3.1-4)is greater than or equal to 1.04.APPLICABILITY:

MODES 1*and 2*ACTION: a.With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.b.With more than one full length rod inoperable or misaligned from the group step counter demand position by more than the allowed rod misalignment, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.c.With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand position by more than the allowed rod misalignment, POWER OPERATION may continue provided that within one hour either;1.The affected rod is restored to OPERABLE status within the above alignment requirements, or 2.The affected rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that: a)A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days;this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, and*See Special Test Exceptions 3.10.2 and 3.10.3 COOK NUCLEAR PLANT-UNIT 2 3/4 1-18 AMENDMENT NO.40, Jl 1 V REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION Continued b)The SHUTDOWN MARGIN requirement of Specification 3.1~1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c)A power distribution map is obtained from the movable incore detectors and F<(Z)and F~are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and d)Either the THERMAL POWER level is reduced to less than or equal to 75X of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85X of RATED THERMAL POWER, or e)The remainder of the rods in the group with the inoperable rod are aligned to within the allowed rod misalignment of the inoperable rod within one hour while maintaining the rod sequence and insertion limits as specified in the COLR;the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

SURVEILLANCE RE UIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 8 steps in any one direction at least once per 31 days.4.1.3.1.3 The allowed rod misalignment for THERMAL POWER greater than 85X of RATED'THERMAL POWER shall be determined in conjunction with the measurement of APL as defined in Specification 4.2.6.2.COOK NUCLEAR PLANT-UNIT 2 3/4 1-19 AMENDMENT NO.40, 407-,@RAN ALLOWED ROD MISALIGNMENT ABOVE S5%RTP FIGURE 3.1-4 20 STEPS 18 16 15 14 13 App W 1icable when R LTMTT o FN>1.04 fM%R 12 100 101 102 103 104 105 106 107 108 APL COOK NUCLEAR PLANT" UNIT 2 3/4 1-20a Amendment No.

0'i h 1 J A REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the rod positions within the allowed rod misalignment specified in Specification 3.1.3.1.APPLICABILITY:

MODES 1 and 2.ACTION: a~With a maximum of one rod position indicator channel per group inoperable either: 1.Determine the position of the non-indicating rod(s)indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.Reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.b.With a maximum of one demand position indicator per bank inoperable either: 1.Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of the allowed rod misalignment of each other, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.Reduce THERMAL POWER to less than 50'f RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.SURVEILLANCE RE UIREMENTS 4.1.3.2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within the allowed rod misalignment at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.COOK NUCLEAR PLANT-UNIT 2 3/4 1-21 AMENDMENT NO.40

POWER DISTRIBUTION LIMITS BASES 3 4 2.2 and 3 4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTO The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factor ensure that 1)the design limits on peak local power density and minimum DNBR are not exceeded and 2)in the event of a LOCA the peak fuel clad temperature will not exceed the 2200 F ECCS acceptance criteria limit, Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2.1, 4.2.2.2, 4.2.3, 4.2.6.1 and 4.2.6.2.This periodic surveillance is sufficient to ensure that the limits are maintained provided: Control rods in a single group move together with no individual rod insertion differing by more than~18 steps from the group demand position (allowed rod misalignment) for power levels less than or equal to 85X of RATED THERMAL POWER.For power levels greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is from J12 to~18 steps, which is dependent on the Allowable Power Level and the ratio of F~limit at 100X of RATED THERMAL POWER to maximum measuered F~as indicated in Figure 3.1-4.Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6.The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained.

The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.F~will be maintained within its limits as specified in the COLR provided conditions a.through d.above are maintained.

The relaxation of F~as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.The form of this relaxation for DNBR limits is discussed in Section 2.1.1 of this basis.When an F<measurement is taken, both experimental error and manufacturing tolerance must be allowed for.5X is the appropriate allowance on F<for a full core map taken with the incore detector flux mapping system and 3X if the appropriate allowance for manufacturing tolerance.

COOK NUCLEAR PLANT-UNIT 2 B 3/4 2-4 AMENDMENT NO.8R, 428, 434.

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