Text

Proposed Tech Specs Figure 2.2-1 Re Peripheral Axial Shape Index Yi Vs Fraction of Rated Thermal Power
	ML20086K760
Person / Time
Site:	Calvert Cliffs
Issue date:	12/10/1991
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
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ML20086K756	List: ML20086K752; ML20086K760; ML20086K763;
References
	NUDOCS 9112130292
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O d ATl'ACHMENT 1 TECIINICAL SPECIFICATION CIIANGE PAGES 9112130292 911210 ,

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Figure 2.2-1 Peripheral Avial Shape Index, Y yvs Fraction of Rated Thermal Power CALVIET CLIFFS 2-11 faendment No. 21, 25. 48, 71, 130 I

1

4 4 REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION

e. .With one or more CEAhmisaligned from any other CEAs in its !

group by more than-7.5 inches but less than 15 inches.

operation in MODES 1 and 2 may continue, provided that within y one hour the misaligned CEA(s) is either:

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(.$

g p 1. Restored to OPERABLE status within-its above specified alignment requirements, or u w h.

le 2. Declared inoperable. After declaring the CEM inoperable l 7$[z

s. g 5 operation in MODES 1 and 2 may continue for up to 7 days per occurrence with a total accumulated time of 514 days per calendar year provided all of the following conditions

{j 4wqk are met:

3 *% 2 a. The THERMAL POWER' level shall be reduced to 5 70% of s the maximum allowable THERMAL POWER level for the

( .4.! hF .g

'+' existing Reactor Coolant Pump combination within one hour; if negative reactivity insertion is required to 5 g p.Z reduce THERMAL POWER, boration shall be used, j 9' b. Within one hour after reducing the THERMAL POW as

in required by a) above, the remain 4gr of the CEA

--$n)s

I $'e 3 k the group with the inoperabie CEA& shall to within 7.5 inches of the inoperable CE while aligned

'c v 'k maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation,

f. WithoneCEhmisalignedfromanyotherCEhinitsgroupby l 15 inches or more, operation in MODES I and 2 may continue, provided that the misaligned CEhis positioned within rM e A

7.5 inches of the other CEAWin its group in accordance with the time allowance shown in Figure 3.1-3/ The pre-misaligned E Ff value used to determine the allowable time to realign the h CEhfrom Figure 3.1-3 shall be the latest measurement taken l c within 5 days prior to the CEA misalignment. If no l

the measurements ware taken within misalignment, a pre-misaligned Ff of @5shal days prior tp$ be assumed I g. WithoneCEhmisalignedfromanyotherCEhinitsgroupby 15 inches or more at the conclusion of the time allowance, p r' ..rs ... o immediately sta t to implement the following actinns:

eMitfe$

1. If the THERMAL POVER level prior to the misalignment was greater than 50% of RATED THERMAL POWER, THERMAL POWER shall be reduced to less than the greater of: ,

i g, m -~i y q g; y CALVERT CLIFFS - UNIT 1 3/4 1-18 Amendment No. JJ7, 151

i c REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION a) 50% of RATED THERMAL POWER b) 75% of the THERMAL POWER level prior to the misalignment within one hour after exceeding theitime allowanc_eM ermitted %* -

"i;= 3.! L

2. If the THERMAL POWER level prior to the misalignment was S 50%

of RATED THERMAL POWER, maintain THERMAL POWER no higher than the value prior to the misalignment.

If negative reactivity insertion is required to reduce THERMAL POWER, boration- shall be used. Within one hour after establishing the appropriate THERMAL POWER as required above, either:

1. Restore the CEM to within the above specified alignment l requirements, or

2. Declare the CEM inoperable. After declaring the CEA inoperaisle, POWER OPERATION may continue for up to 7 days per occurrence with a total accumulated time of g 14 Jays per calendar year provided the remainder of the CEAWin the group l with the inoperable CEA are aligned to within 7.5 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

h. With more than one CEM inoperable or misaligned from any other CEA in its roup by 15 inches (indicated position) or more, be in at least JT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

i. I thepurposesofperformingtheCEhoperabilitytestof TS 4.1.3.1.2, if the CEA has an inoperable position indication channel, the alternate indication system (pulse ccunter or voltage m dividing network) will be used to monitor position. If a direct position indication (full out reed switch or voltage dividing network) cannot be restored within ten minutes from the commencement of CEA motion, or CEA withdrawal exceeds the surveillance testing insertion by > 7.5 inches, the position of the CEA shall be assumed to have been > 15 inches from its group at the commencement of CEA motion.

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(53J.ONIW) Y33 NDI"lV3B 01 3 nil CALVERT Ct.IFFS - UNIT 1 3/4 1-198 /cendment No. 127 -

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. . TOTAL PLANAR RADIAL PEAKING FACTOR vs N i

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v 1 _- __________._.____._._o

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lgWR DISTRIBLITION LIMITS TOTAL PLANAR RADIAL PEAKING FACTOR F}y 4

LIMITING CONDITION FOR OPEPATION 3.2.2.1 The calculated value of F}yg&i . - _ n F[j .xyv :q;y shall be limited to s 1.70.

APPLICABlU.11: MODE 1*.

ACTION: gpf WithF[y>1.70,within6hourseither:

a. ' duce THE -

POWER o ring t e ombin i of THE POW and T o withi e lim ts f Fig r .2-3a and ithdra he ful - th CEA or be d the Term'S 'dy Sta sertion irr s of Sp icat .1.3. -

b. Be in at least HOT STAND 8Y.

SURVEILLANCE REOUIREMENTS 4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 xy 1 be c c at e expr s i T y + )a x s 1 be .te mine 'e be thi i s li . t a Se lo serva -

a. Prior to operation above 70 percent of RATED THEP3AL POWER In scot g

after each fuel loading, -

l b. At least once per 31 days of accumulated operation in MODE 1,

and l c. Within four hours if the AZIMUTHAL POWER TILT (T q ) is > 0.030.

See Scecial Teit' Exception 3.10.2.

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CALVERT CLIFFS - UNIT 1 3/4 2-6 Amendment No. 72/JJ//8/7J/EE.

151

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INSERT I

. Withdraw and maintsin the' full -length CEAs at or beyond the Long Tem

' Steady-State _ Insertion Limits of Specification 3.1.3.6 and reduce THERMAL

_ POWER as follows:

1. Reduce 'lHERMAL POWER to bring the combination of THERMAL POWER and F,y' within the limits of Figure 3.2-3a, or 2.- Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System (BASSS) as a function of !

Fuy'; or INSERT II

'F,y' shall be calculated as F,y' - F,y using .a full core power distribution mapp;ng' system. F,y' shall be determined to'be-within its limit at the following intervals:

.._rn_______________ _ _ ,

4 i POWER DISTRIBtJTION LIMITS SURVEILLANCE REOUIREMENTS (Continued) 4.2.2.1.3 s 1 be determined each time a calculation is required by using the incore detectors to obtain a power distribution map with all full length CEAh at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This determination shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.

.2. . 4- q hall d e .in .ac ime al tio fF x i T

r ired d th alue us to erm .F y hall th mea r lu o T. q g .;g ; m -m-- cre e,na ,; j;;c g , g CALVERT CLIFFS - UNIT 1 3/4 2-7 Amendment No. 2J/J2/7J, 151

POWER DISTRIBtJTI.ON LIMITS TOTAL PLANAR RADIAL PEAXING FACTOR - FT y LIMITING CONDITION F,9R OPERATION 3.2.2.2 The value of N presently used in Specification 4.2.1.3 shall be in accordance with Figure 3.2-3b.

APPLICABILITY: HODE 1 when operating in accordance with Specification 4.2.1.3.

ACTION:

With the value of N presently used in Specification 4.2.1.3 exceeding the limit shown in Figure 3.2-3b, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a. Reduce the value of N used in Specification ~ 4.2.1.3 to within the limits of Figure 3.2-3b; or

b. Be in at least HOT STANDBY.

SURVEILLANCE REOUTREMENTS 4.2.2.2.1 -The provisions of Specification 4.0.4 are not applicable.

4.2.2.2.2 [y ha b ca u ted y 5 e r si 'n F xy -

(1 d h e dete .ined t wit its 'mit mon :ori F x t lowi i erva

/l a. Prior to operation above 70 percent of RATED THERMAL POWER gg ; after each fuel loading, E b. , At least once per 3 days of accumulated operation in MODE 1.

sha ce determined each time a calculation ?t ,Iis

4. 2.2.2. 3 required usingtheincoredetectorstoob'.ainapowerdistbbutionmap with all full length _CEAhat or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This determination shall be limited to core planes between 15r. and 85Y. of full core height inclusive and shall exclude regions influenced by grid effects.

. .2. .4 q eha e e er. nd 5 t me c icul t o FT - s f

r t. ired d th val of use to ter. 'F x sha i be e rr ur i alu o T. o 1

..:> e ,y .

_ - m re- m,; g i a

CALVERT CLIFFS - UNIT 1 3/4 2-8 Amendment No. U , 151

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

o s INSERT III Fy shall be calculated as Fy - F y using a full core power distribution mapping system. N shall be determined to L . within its limit by monitoring ,

Fy at the following intervals:

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l I

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i 20WEjLDISTRIBUT10K Lljill5 10TAL INTEGRATED RADIAL PEAKING FACT 71 - Ff l (it!ITING(QNDITIONFOROPERATION 3.2.3 Thecalc pa- - d F-1 "T'J g shall be limited to 1(Jg.glated go value of Ffg * ,

t APPLICABILITY: MDDE 1*.

EllDB: g,7o WithFf> within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a. Be in at least HOT STANDBY. or

b. Reduce THE L POWER t ring the ybinatio fTIiE POWER '

adF[towitinthe imi of F gure 3.2.3 , wi hdra th ful

, len h .As+ t or . yond t e ng Te St dy St te imits Speci cation 3.1. 6, and i .ert new vt of Ff , BASSS;

c. d ce 1HE L WER br ng th combi att

/

of T IEPy WER >

a Fftowi n it:: 11. s of F1 r- .b3c nd ithdra the ull length E + to or be end the L g Term S ady Sta inser ion imits f 5 acific tion 3. . 6. Th IERMAl POWE pged limit ermined f o Figure 2 3c sha the be d to 1

I)t estab s a revise pper THE OWER le e limit o 9 e 3.2 4 (tru cate Figure 3.'- at the lowable fr ctto ,

o TED THE POWER termin d b Figur 3. 3c) nd subs cent ope ation shal be aintair 'd thin he reduce

.accep le o .ra ion region f Figure 3. 4.

SURVEILLANCE REOULREMENTS t ^'

4.2.3.1 The provisich of Specification 4.0A are not applicable.

4.2.3.2 c1 _ r w ir u dar w

T[shallb;c.icui;;;dtjP:-::prc;;icthe w j t e b cu oe 14r o o r[!!: M,(;317 4 ; 7 ;;1 ):,-g r1 '

a. Prior to operation above 70 percent of RATED TiliRMAL POWER InsePt after each fuel loading,

~b. At least once per 31 days of accumulated operation in MODE 1, C_%- and

c. Within four hours if the AZIMUTHAL POWER TILT (T q ) is > 0.030.

See Special Test Excention 3.10.2.

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l CALVERT CLIFFS - UNIT 1 3/4 2-9 Amendment No. 72/U/U//j!/71/

88. 151 l: . .

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, INSERT IV Withdraw and maintain the full le.19th CEAs at or beyond the Long Term Steady State Insertion Limits of Specificm*lon 3.1.3.6 and reduce THERKAL POWER as follows:

1. Reduce THERKAL POWER to bring the combination of THERHAL POWER and F,'

within the limits of Figure 3.2-3c, or

2. Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System (BASSS) ar a function of F,'.

When the THERMAL POWER is determined from figure 3.2-3c, it shall be used to establish a revised upper THERMAL POWER LEVEL limit on Figure 3.2-4 (i.e.,

Figure 3.2-4 shall be truncated at the allowable fraction of RATED THERMAL POWER determined by Figure 3.2-3c). Subsequent operation shall be maintained within the reduced acceptable operation region of Figure 3.2 4.

INSERT V F,' shall be calculated as F,' - F, using a full core power distribution mapping syster. F,' shall be determined to be within its limit at the following intervals:

- - - , - - ,, _ v

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

HRY.Elt. LANCE REQUIREMENTS fContinued) 4.2.3.3 f r.sh 1 be dstermin:d each time a calculationdis required by using t e incore detectors to obtain a power distribution map with all

~

fulllengthCEA$atorabovetheLongTernSteadyStateInsertionLimit for the existing Reactor Coolant Pump combination.

4.2. . T s 1 b d in d a ime a a lati n o 'i e e the ue o Tq , ed t dete er ur va a ne sha be 2o q-Evc!udia; the ::c,ter CEA 6; ; ige'c ;0,1 l

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l CALVERT CLIFFS - UNIT 1 3/4 2-10 Amendment No. JJ # /, 151 I

- . _ _ ..___ .._______._._.___-______.m...

a -i I

RE ACTIVITY CONTROL SYSTEMS ,

1ASES Overpower margin is provided to protect the core in the event of a large misalignment ( 3.,15 inches) of a CEA. However, this misalignment would cause distortion of the core power distribution. The reactor prote not detect the degradation in radial peaking factors and ,ctive since systeminwould variatkas other system parameters (e.g., preisure and coolant temperature) may not be ,

suffielent to cause trips, it is por.sible that the reactor could be operating with l ;

process variables less conservativs than those assumed in generating LCO r.nd LSSS setpoints. The ACTION statement asseisted with i large CEA misalignment requires prompt action to reglgn the CEA to avoid eacessive ,

margin degradation. If the CEA is not realigned within the given time constraints, action is specified which will preserve margin, including reductions :

in THERhtAL POWER.

For a single CEA mtulignment, the time allowance to sedign the CEA (Figure 3.1-3) is permitted fnr the ro11ewine tensons: ;

k [or as n(etermised by BAsss)

J. The margin rR-ninions which support the , power distribution LCOs for DNTR are based on a steady-state F/ as specified in Technical Specification 3.2.3.

.2. When the actual F7 is less than the Technical Specification value, additional margin exists. ;

3. This additional- margin can be credited to offset the increase in F[

with time that will occur following a CEA miulignment pue to xenon redistribution, g affat t3e t(me fjmif gefermine/ }y MSSS The requirement to reduce power level after the time limit of Figure 3.1-3 is reached offsets the continuing increase in F[ that can occur due to xenon redistribution. A power reduction is not required below 50% power. Below 30%

power there is sufficient conservatism in the DNB power distribution LCOs to completely offset any, crr any addititmal, senen redistribution effects.

The ACTION statements applicable to miuligned or inoperable- CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA. Conformance with these alignment nquirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and J SSS serpoints. However, catended operation with CEAs significantly inserted in the core may lead to perturbations in 1) local burnup,

2) peaking factors, and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSSS setpoinu determination. Therefore, time limits have been imposed on operation -

with inoperable CEAs to preclude auch adverse conditions from developing.

l CALVERT CLITTS - UNIT 1 B 3/4 1 4 Amendment No. H 57,127

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1. m . . .uu u UNACCEPTABLE h OPERATION M N REGION 4 3

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. 2 REGION o

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cm en Figure 3.2-3c TOTAL INTEGRATED RADIAL PEAKING FACTOR vs ALLOWABLE FRACTION OF RATED THERMAL POWER s.

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

a. Cold Leg Temperature

b. Pressurizer Pressure

c. Reactor Coolant System Total Flow Rat 6

d. AXIAL SHAFE INDEX, cere inca APPLICABILITY: MODE 1. TNEANAl. POWEA ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its limit by measurement at least once per 18 months.

f. 2. r. 3 Th 8efter Avia/ SAapt Sclet. tion Systdm (84s55) may he used for konitorin3 THEAi,o PCWSA as a pusstjon of AfIAL SffAPE INDEx. BAsss monitoting shall be limitel to TEA ts.sertions orths lead bank 615 %.

CALVERT CLIFFS-UNIT 1 Amendment No. 39.E4 71 I

O TABLE 3.~d-1 c DNB PARAMETERS M

4

" LIMITS C

4 four Reactor Three Reactor Two Reactor Two Reactor +

Coolant Pu=ps C'olant o Pumps Coolant Pumps Coolant Pumps

[

z Parameter Operating Operating Operating-Same Loop Operating-Opposite Loop Cold Leg Temperature 5,548'F Pressurizer Pressure > 2200 psia

l Reactor Coolant System Total Flow Rate > 370,000 gpm AXIAL SHAPE INDEX,T#ovut FCWER '

M

~

7

Limit not applicable during either a THEPEAL POWER raq increase in excess of 5% of RATED THERFAL POWER

% per minate or a THERMAL POWER step increase of greater than 10% of RATED THEPNJ. POWER.

- These values left blank pending KRC approval of ECCS analyses for operation with less than

~

i four reacter coolant pumps operating. :

THERMAL FCi"ER

- - The AXI AL SHAPE INDEX. Cr ("c.ar shall be maintained within the limits established by the Better i Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of = 55% when BASSS is k OPERABLE. or within the limits of FIGURE 3.2-4 for CEA insertions specified by FIGURE 3.1-2, a

E c5 h

Y M (9 %~

1 PLANT SYSTEMS ,

i BASES (Continued) l Loss of Feedwater: 0 gpm Auxiliary feedwater Flow Feedline Break: 0 m Auxiliary feedwater Flow Main Steam Line Break: 3 gpm Auxiliary Feedwater Flow (This eing the maximum flow through the AFW tryo suction line, with one unit requiring '

flow, prior to pump cavitation due to I lowHPSH.)

At 10 minutes af ter an Auxiliary Feedwater Actuation Signal the operator is a:sumed to be available to increase or decrease auxiliary feedwater flow to that required by existing plant conditions.

4 l

CALVERT CLIFFS - UNIT 1 B 3/4 7-2a Amendment No. 8 g

DESIGV FEATURES DESIGN PRESSURE AND TEMPERATURE

' 5.2.2 The reactor containment building is designed and shall be main-tained for a msximum interna 1' pressure of 50 psig and a temperature of 276'F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fubl assemblies with each fuel assembly containing a maximum of 176 fuel rods Eachclad with Zircaloy contain a maximum total weight of 3000 i, rams uranium.

Relbad fuel shall be similar in physical desigloading shall have a raa the initial core

. loading and.shall have a maximum enrichment of weight percent U-235.

,e 5.3.2 4.3T Except for special test as authorized by the NRC, all fuel assemblies under previously control element approved assemblies'shall by the NRC. be sleeved with a sleeve design ER3 ELEMEffT ASSEMBLIES

5. 3. 3 The reactor core shall contain 77 full length and no part length control element assemblies.

L 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMDERATURE '

5.4.1 The reactor coolant system is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 4.2 of the FSAR with allowance for nonnal degradation pursucat of the applicable Surveillance Requirements,

b. For a pressure of 2500' psia', and c.

for a temperature of 650*F, except for the pressurizer which is 700*F.

I CALVERT CLIFFS - UNIT 1 Amendment No. 22. M. 71 5-4

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3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORAUON CONTRDL SHUIDOWN MARGIN - T > 2000F avu LifilTING COHJllTION FOR OPERATION _ , _ - _ _._ -

3.1.1.1 The SHUTD0VN KARGIN shall be equal to or greater then the limit line of Figure 3.1-lb.

APPLICABILITY: MODES 1, P*, 3, and 4.

ACTION:

With the SHUTDOWN MARDIN less than the limit line of figure 3.1-lb immediately initiate and continue beration at 1 40 gpm of 2300 h p beric acid solution or equivalent until the required SHUTDOWN MARCIN is restored.

1Eyil1 LANCE REDMLRMMIS _

4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be equal to or greater than the limit of Figure 3.1-lb:

a. Within ene hour after detection of an inoperable CEkshand at leastonceper12hourstherenfterwhiletheCEA(sf6is inoperable. If the inoperable CEA is immovable or untrippable, the above requi*ed SHUTDOWN MARGIN shall be increased by an amount at least equaldo the withdrawn worth of the immovable or untrippable CEA(sfl2

b. When in HODES 1 orI 2 , a W east once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by veritying that CEA group withdrawaWis within the Transient Insertion l Limits of Specification 3.1.3.6.

c. When in MODE 28#, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving reactor critical &ybyverifyingthatthepredictedcriticalCEA posittorF is within the limits of Specification 3.1.3.6. l

d. Prior to initial operation above SY. RATED TiiERMAL IWER af ter each fuel loading, & consideration of the factors of e below, with the CEA group p at the Transient Insertion Limits cf l Specification 3.1.3.6.

Adherence to Technical Specification 3.1.3.6 as specified in Surveillance Requirements 4.1.1.1.1 assures that there is sufficient available shutdown margin to match the shutdown margin requirements of the safety analyses.

- See Special Test Exception 3.10.1.

I With K ff With K,,fy r 1 1.0e ,< l.0 _

+ w !ucty y unto rr duc y r p 104 l CALVERT Cliffs - UNIT 1 3/4 1-1 Amendment No. 2J/J2//E////EE/

19/1179.151 i

REACTIVITY CONTROL SYSTIES T

SHUTDOWN MRGIN - T ,,, s 200 F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MRGIN shall be 2 3.0% A k/k.

APPLICABillTY: MODE 5

a. Pressurizer level 2 90 inches from bottom of the pressurizer,

b. Pressurizer level < 90 inches from bottom of the pressurizer i and all sources of non borated water 188 gpm.

ACTION:

a. With the SHUTDOWN MRGIN < 3.0% 6 k/k, imediately initiate and continue boration at 2 40 gpm of 2300 ppm boric acid solution or equivalent until the required SHUTDOWN MRGIN is restored.

b. With the pressurizer drained to 1 90 inches and all sources of non borated water > 88 gpm, immediately suspend all operations involving positive reactivity changes while the SHUTDOWN MRGIN is increased to compensate for the additional sources of non borated water or reduce the sources of non borated water to 1 88 gpm. ;

SVMLllt ANCE RE0VIREMENTS 4.1.1.2 The SHUTDOWN MRGIN shall be determined to be 2 3.0% 6 k/k,:

a. Within one hour after detection of an inoperable C (shandat least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafterghile the CEA(s is inoperable. If the inoperable CEActis immovable or untrippable, the above required SHUIDOWN MRGIN shall be increased by an amount at least eqe to the withdrawn worth of the immovable or untrippable CEA(s l

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1. Reactor coolant system boron concentration,

2. CEA position,

3. Reactor coolant system average temperature,

4. Fuel burnuri based on gross thermal energy generation, 5, Xenon concentration, and

6. Samarium concentration.

4.1.1.2.2 With the pressurizer drained to 5 90 inches determine:

1. Within one hour and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter that the level in the reactor coolant system is above the bottom of the hot leg noztles, and

b. Within one hour and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter that the sources of non-borated water are s 88 gpm or the shutdown margin has compensated for the additional sources.

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l CA!.VCRT CLIFTS - UNIT 1 3/4 1-3 Amendment No. /E/JJ 151 i

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REACTIVITY CONTR0t SYSTDiS 3.4.1.3 MOVABLE CONTROL ASSEMBLIES LIMIIIE_IONDIT10N 00fLOMM110N 3.1.3.1 TheCEAMotionInhibitandallshutdownandregulatingCEAh shall be OPERABLE with each CEA of a given group positioned within 7.5 inches (indicated position) of all other CEAs in its group.

APPLICABILITY: MODES l' and 2*

ACTION:

a. With one or more CEAh ;nsperable due to being imovable as a l result of excessive friction or mechanical interference or known to be untrippable, be in at least HOT STANDDY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . .

b. With the CEA Motion Inhibit inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

1. Restore the CEA Motion Inhibit to OPEPABLE status, or

2. Place and maintain the CEA drive system mode switch in either the 'Off" or any ' Manual Mode' position and illya withdraw all CEAs in groups 3 and 4 and withdraw thw CEA W in group 5 to less than 5% insertion, or

3. Be in at least HOT STANDBY.

c. WithoneCEAinoperab1hduetocausesotherthanaddressedby ACTION a, above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES I and 2 may continue for up to 7 days per occurrence with a total accumulated time of 114 days per calendar year.

d. WithoneCEAinoperabihduetocausesotherthanaddressedby ACTION a, above, but within its above specified alignment requirements and either fully withdrawn or within the Long Term Steady State Insertion limits if in CEA group 5, operation in MODES 1 and 2 may continue.

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See Special lest Exceptions 3.10.2 and 3.10.4.

" 4:Wd i ng t M -t er-C U de r is C., dh - M . j CALVERT Cliffs - UNIT 1 3/4 1-17 Amendment No. J//.151

REAC'TIVITY CONTROL SYSTEMS M VEILLANCE REOUIREMEKIS 4.1.3.1.1 The position of each CEhshall be determined to be within 7.5 inches (indicated position) of all other CEAs in its group M ". east once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Deviation Circuit and/or CEA Motion Inhibit are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ;

4.1.3.1.2 Each CEhnot fully inserted shall be determined to be OPERABLE by inserting it at least 7.5 inches at least once per 31 days.

4.1.3.1.3 The CEA Hotion Inhibit shall be demonstrated OPERABLE at least

'once per 31 days by a functional test which verifies that the circuit maintains the CEA group overlap and sequencing requirements of Specification 3.1.3.6 and that the circuit also prevents :.ny CEA from being misaligned fro w 11-other CEAs in its group by more than 7.5 inches (indicated position) W n rv-s ef h;_;t,; cen;m ;> S7 n,, ;3h p ,j l

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t CALVERT CLIFFS - UNIT 1 3/4 1-19A Amendment No. ///, 151

REACTIVITY CONTROL SYSTEMS

, POSITION INDICATOR CHANNELS LINITING CONDITION FOR OPRA110N 3.1.3.3 At least two of the following three CEA position indirAor channels shall be OPERABLE for eaer, shutdown and regul_ating CEW.

a. CEA voltage divider reed switch position indicator channel, capable-of determining the absolute CEA position within i 1.75 inches;

b. CEA ' full Out' or ' full In' reed switch position indicator channel, only if the CEA is fully withdrawn or fully inserted, as verified by actuation of the applicable position indicator; and

c. CEA pulse counting position indicator channel.

APPLICABILITY: MODES 1 and 2.

MILQH: a

a. With a maximum of one CErdper group having its voltage divider reed switch position indicator channel or its pulse counting position indicator channel inoperable and the CEA(s) with the inoserable position indicator channel partially inserted, eitler:

1. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a) Restore the inoperabic position indicator channel to OPERABLE status, or b) Be in at least HOT STANDBY, or c) Reduce TliERMAL POWER to 170i.' of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination; if negative reactivity insertion is required to reduce THEPML POWER, boration shall be used. Operation at or below this reduced T11EPJ4AL POWER level may continue provided that within d e next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1) w with the inoperable position The indicator CEAisgroup fu (s]lly withdrawn while maintaining the withdrawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn position, the " full Out' limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully withdrawn. Subsequent to fully withdrawing this CEA group (s), the THERMAL POWER level may be returned to a level consistent with all other applicable specifications and operation may continue per Specification 3.1.3.3 above; or

2) The CEA group (shwith the inoperable position l indicator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THEPML POWER level required by Specification 3.1.3.6 and when this CEA group reaches its fully

-i I u 'd m; th: -= t~ C M Min; Cy&E -j CALVERT CllffS - UNIT 1 3/4 1 21 Amendment No. 72/77/EH99/

J#E, '* 151

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EEAGTIVITY CONTROL SYSTEMS E01 U. ION INDICATOR C1 M ELS LIMU1FGCONDIT10NFOROPERATION inserted position, the ' full In" limit of the CEA with the inoperable indicator is actuated and verifies this CEA to be fully inserted.

Subsequent operation shall be within the limits of Specification 3.1.3.6, and may continue per Specification 3.1.3.3 above.

2. or, if the failure existed before entry into MODE 2 or occurs pr r to an "all CEAs out" configuration, the CEA groups (s with inoperable position indicator channel must ,

be moved to the " Full Out' position and verified to be fully withdrawn via a ' full Out" indicator. These actions must be completed within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of entry into MODE 2 and prior to exceeding 70% of the maximum allocble THERMAL.

POWER level for the existing Reactor Coolant Pump combination. The provisions of Specification 3.0.4 are not applicable. Once these actions are completed, operation may continue per Specification 3.l.3.3 above.

b. WithmorethanoneCEhpergrouphavin its CEA pulse counting l position indicator channel and either ( ) the " full Out" or

' Full In" position indicator, or (2) the voltage divider position indicator channel inoperable, operation in H0 DES I and 2 may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided that for the affected CEAs, either:

1. The CEA voltage divider reed switch position indicator channels are OPERABLE, or

2. The CEA ' Full Out" or ' Full In" reed switch position indicator channels are OPERABLE, with the CEA fully withdrawn or fully inserted as verified by actuation of the applicable position indicator.

SURVELLLANCE RERVlR[ME!{IS 4.1.3.3.1 Each required CEhposition indication channel shall be !

deterniined to be OPERABLE by determining CEA positions as follows at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , by:

a. Verifying the CEA pulse counting position indicator channels and the CCA voltage divider reed switch position indicator channels agree within 4.b inches, or

b. Verifying the CEA pulse counting position indicator channels and the CEA " full Out" or

full In" reed switch position indicator channels agree within 4.5 inches, or

c. Verifying the CEA voltage divider reed switch position indicator channels and the CEA ' full Out" or " full In" reed switch position indicator channels agree within 4.5 inches.

4.1.3.3.2 During time intervals when the deviatigacircuit is inoperable, the above verification of required CEfc/ position indicator l channels shall be made at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

T t e d w; d: = t:r CC',Jm os c3 s1 10. '

CALVERT Cliffs - UNIT 1 3/4 1-22 Amendment No. fE/D /EM PE, 151

CEA DROP TIME LIMITING CDNDJJJON FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEhdrop time, from a fully withdrawn position, shall be i 3.1 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with:

a. T ayg 1 5150F, and

b. All reactor coolant pumps opurating.

APPLICABILITY: MODES I and 2.

ACTION:

a. With the drop time of ar.y full length CEMdetermined to exceed the above limit, restore the CEA drop time to within the above ,

limit prior to proceeding to MODE 1 or 2.

b. With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combinati(,n operating at the time of CEA drop time determination.

$11RVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAhshall be demonstrated through measurement prior to reactor criticality:

a. For all CEAs following each removal of the reactor vessel head,

b. For specifically affected individual CEAs following any maintenance on or modification to the CEA drivs system which could affect the drop time of those specific CEAs, and

c. At least once per refueling interval.

l D:1 & ; it: cc.,t w CEA duch; Cyu u 10.]

I CALVERT Cliffs - UNIT 1 3/4 1-23 Amendment No. J2/JS/EE/JJ9, 151 h

REACTIVITY CORTROL SYST mi SHtfiDOWN CEA INSERTION LIMIT LIMITING CONDITION FOR_DPEIMHON 3.1.3.5 All shutdown CEAs shall be withdrawn to at least 129.6 inches.

APPLICABILITY: Pe00ES I and 2*f.

ACTION:

With a maximum of one shutdown CEA withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, to less than 129.0 inches, within one hour either:

a. Withdraw the CEA to at least 129.0 inches, or

b. Declare the CEA inoperable and apply Specification 3.1.3.1.

g';%yElllANCE RE0ttlEEMENTS 4.1.3.5 Each shutdown CEA shall be determined to be withdrawn to at least 129.0 inches: -

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a. Within 15 minutes prior to withdrawal of any CEAhin regulating groups during an approach to reactor criticality, and

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

See Special Test Exception 3.10.2.

With Ko rr> 1.0 r+ & ~i"S m u:2 cente: CU, drin; Cycic -10 l l CALVERT CLIFFS - UNIT 1 3/4 1-24 Amendment No. /E,151

REACTIVITY CONTROL SYSTEMS BLGULATING CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating CEMgroups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1-2 (regulating CEAs are considered to be fully withdrawn in accordance with Figure 3.1-2 when withdrawn to at least 129.0 inches) with CEA insortion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits restricted to:

a. 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval,

b. s 5 Effective Full Power Days per 30 Effective full Power Day interval, and

c. I 14 Effective Full Power Days per calendar year.

APPLICABILITY: MODES 1* and 2*f.

ACTION:

a. With the regulating CEhgroups inserted beyond the Transient Insertion Limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either:

1. Restore the regulating CEA groups to within the limits, or

2. Reduce TilERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the CEA group position using Figure 3.1-2.

b. WiththeregulatingCEMgroupsinsertedbetweentheLongTerm Steady State Insertion Limits and the Transient Insertion Limits for intervals > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, except during operations pursuant to the provisions of ACTION items c.

and e. of Specification 3.1.3.1, operation may proceed provided either:

1. The Short Term Steady State Insertion Limits of Figure 3.1-2 are not exceeded, or

2. Any subsequent increase in TiiERMAL POVER is restricted to S 57. of RATED TiiERMAL POWER per hour.

See Special Tast Exceptions 3.10.2 and 3.10.4.

With Ko rr> 1.0.

m W cc-t6r CE? :3 k a:Nd:d 'r:- tt: j:t; r 'n.:t;c af L..L-;_I P!'t ic" & At Cycle 10.

CALVERT CLIFFS - UNIT 1 3/4 1-25 Amendment No. 7E#pE,151 i

. ]LEACTIVITY CONTROL SYSIgg LIMITING CONDITION FOR OPERATION (Continued) _

c. With the regulating CEhgroups inserted between the Long Term Steady State Insertion Limits and the Transient Insertion Limits for intervals > 5 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, except during operations pursuant to the provisions of ACTION iters c. and e. of Specification 3.1.3.1, either:

1. Restore the regulating groups to within the Long Term Steady State Insertion Limits within two hours, or

2. De in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS ___

4.1.3.6 The position of each regulating CEMgroup shall be determined l to be within the Transient Insertion Limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the PDIL Alarm Circuit is inope'rable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The accumulated times during which the regulating CEA groups are inserted beyond the Steady State Insertion Limits but within the Transient Insertion limits shall be detemined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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13 CALVERT CLIFFS - UNIT 1 3/4 1-26 Amendment No.151

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3/4.2 POWER DISTRIBUTION LINITS LINEAR HEAT RATE LIMITING CONDITION FOR OPEPATION 3.2.1 The linear heat rate shall not exceed the limits shown on Figure 3.2-1.

APPLICABILITY: MODE 1.

ACTION:

With the lin. ar heat rate exceeding its limits, as indicated by four or more coincident incore channels or by the AXIAL SHAPE INDEX outside of the power dependent control limits of Figure 3.2-2, within 15 minutes initiate corrective action to reduce the linear heat rate to within the limits and either:

a. Restore the lir. ear heat rate to within its limits within one hoar, or

b. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0tJJREMENTS 4.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.1.2 The linear heat rate shall be determined to be within its limits by continuously monitoring the core power distribution with either the excore detector monitoring system or with the incore detector monitoring system.

4.2.1.3 Ercore Detector Monitorina System - The excore detector monitoring system may be used for nonitoring the core power distribution by:

a. Verifying at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that the full length CEAh are withdrawn to and maintained at or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6.

b. Verifying at least once per 31 days that the AXIAL SHAPE INDEX alarm setpoints are adjusted to within the limits shown on Figure 3.2-2.

{J t v-'"*:gsc ccota C U, & . o g C., c ' c L J CALVERT CLIFFS - UNIT 1 3/4 2-1 Amendment No. JJ/JJ,151

.- - _ . . - . . . ,_r. - _ _

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, , 2LL.10 SPECIAL TEST EXCEPTIONS SHtTTDOWN MARGIN i tIMITIHLCOMlHON FOR OPEMI.]QN 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).

APPLICABILITY: H00E 2.

ACTION:

a. With any full length CEhnot fully inserted and with less than l the above reactivity equivalent available for trip insertion, immediately initiate and continue bsratu,n at 2 40 gpm of 2300 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b. With all full length CEAhinserted and the reactor subcritical by less than the above rea'.tivity equivalent, immediately initiate and continue boration at 2 40 gpm of 2300 ppm boric acid solution or its equ; valent until the SHUTDOWN MARGIN required by Specificatien 3.1.1.1 is restored.

ItRV_LILLANCE RE001RENENTS .

4.10.1.1 The position of each full length CEhrequired either partially or fully withdrawn shall be (.etermined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEM not fuliy inserted shall be demonstrated capable of full insertion when tripped from at least the .407. withdrawn position l within 7 days prior to reducing the SHUTDOWN K% GIN to less than the limits of Specification 3.1.1.1.

Edd Mg - tSc ar ter CU, dw. .n3 Cgic 10y CALVfRT Cliffs - UNIT 1 3/4 10-1 Amendment No. J///E#ff,151

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