Text

Proposed Tech Specs Eliminating 3.3.3.2 & Relocating Limitations on Use of Incore Instrument Sys to Ccnpp Usfar
	ML20059H705
Person / Time
Site:	Calvert Cliffs
Issue date:	11/03/1993
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20059H702	List: ML20059H698; ML20059H705;
References
	NUDOCS 9311100179
	Download: ML20059H705 (21)
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ATTACHMENT (1)

UNIT 1 TECIINICAL SPECIFICATION REVISED PAGES TABLE OF CONTENTS IV ,

3/42-2 3/42-6 3/42-11 3/4 2-12 3/4 3-31 3/4 3-32 3/4 3-33 ,

BASES 3/4 3-2 ,

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1, TABLE OF CONTENTS-h :

F LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS E

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,SECTION PAGE--

3/4.3 INSTRUMENTATION i

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3/4.3.1

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REACTOR PROTECTIVE INSTRUMENTATION ......... 3/4'3-1 t

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM i INSTRUMENTATION . . . . . . . . . . . . . . . . . . . 3/4 3 i q

3/4.3.3 MONITORING' INSTRUMENTATION ,

Radiation Monitoring Instrumentation ........ 3/4 3 !

Incere Octectcr: .................. 3/4 3-31 l Seismic Instrumentation . . . . . . . . . . . . . . . -3/4 3-33 i Meteorological Instrumentation ........... 3/4 3-36 l Remote Shutdown Instrumentation . . . . . . . . . . . .3/4 3-39 l

-Post-Accident Instrumentation . . . . . . . . . . . . 3/4 3-42 Fire Detection . Instrumentation . . . . . . . . . . . . 3/4 3-46 Radioactive Gaseous Effluent Monitoring 3 Instrumentation . . . . . . . . . . . . . . . . . . .

3/4 3-51 . !

Radioactive Liquid Effluent Monitoring i Instrumentation . . . . . . . . . . . . . . . . . . . 3/4 3-56' q

g 3/4.4 REACTOR COOLANT SYSTEM '

t 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP And POWER OPERATION . . . . . . . . . . . . .

~

3/4 4 -

HOT STANDBY . . . . . . . . . . . . . . . . . . . . . 3/4 4-2 i Shutdown ~ . . . . . . . . . . . . . .s. ....... 3/4 4-4 q 3/4.4.2 SAFETY VALVES . . . . . . . . . . . . . . . . . . .. 3/4 4 :l 3/4.4.3 RELIEF VALVES . . . . . . . . . . . . . . . ... . . . 3/4 4-7 j 3/4.4.4 PRESSURIZER . . . . . . . . . . . . . . . . . . . . . 3/4 4-8' Ll q

3/4.4.S STEAM GENERATORS .................. '3/4L4-9; :

3/4.4.6 S

REACTOR COOLANT SYSTEM LEAXAGc Leakage Detection Systems . . . . . . . . . ... . . . 3/4 4-16 Reactor Coolant System Leakage ........... .

3/4 4-18 j 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . . . . . . 3/4 4-20 ;

3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . '3/4'4-23 !

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i 1

CALVERT CLIFFS - UNIT 1- IV Amendment No. -W3-.

e 3/4.2 POWER DISTRIBUTION LIMITS !

SURVEILLANCE REQUIREMENTS (Continued)

c. Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the limits of Figure 3.2.1-2, where 100 percent ,

of the allowable power represents the maximum THERMAL POWER '

allowed by the following expression:

MxN where:

1. M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.

2. N is the maximum allowable fraction of RATED THERMAL POWER as detennined by the F], curve of Figure 3.2.1-3.

4.2.1.4 Incore Detector Monitoring System - The Incore Detector Monitoring System may be used for monitoring the core power distribution by verifying ,

that the incore detector Local Power Density alanns:

a. Are adjusted to satisfy the requirements of the core power distrib3(ion map which shall be upriated at least once per <

31 dayWof accumulated operation in MODE 1.

W b. Have their alann setpoint adjusted to less than or ecual tn the i limits shown on Figure 3 ].2.1-1.when the following factors are ,

p. riately included in tne setting of these alarms:

1. A measuremend calculational uncertainty fa + of 1.062,"

2. An engineering uncertaintyp e of 1.03, 3 .a t uncertainty factor o . Q2 due to axial I.Alinearhedat fuel enstf ion and thermal expansion, and 3

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4. A THERMAL POWER measurement uncertainty factor of 1.02.

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For Tele-J1 only, when the percentage of OPERABLE incore detector locations (F3Nirings) falls below 75%, this surveill[an ,

shall be performed at.least onci m 15 days of accumulated operation in MODE 1.

(**g N

For Unit 1 Cycle 11 only, Jw en-ttre percentage of OPERABLE incore t

x cetector locationsje.grsTrings) falls below 75%, the measurement-

\ calculatiopl-unfertainty factor on linear heat rate shall be increasch <

by 1&ffrom 1.062 to 1.072) prior to comparison with the Technical :

4p,ecification limits. -

CALVERT CLIFFS - UNIT 1 3/4 2-2 Amendment No.--150 I

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3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.2 TOTAL PLANAR RADI AL PEAKING FACTOR - FI, LIMITING CONDITION FOR OPERATION 3.2.2.1 The calculated value of FI, shall be limited to 51.70 $ '

APPLICABILITY: MODE 1*.

ACTION: With P,> 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a. Withdraw and maintain 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 THERMAL POWER to bring the combination of THERMAL POWER and FI, within the limits of Figure 3.2.2-1, or i

2. Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System '

r (BASSS) as a function of FI,; or

b. Be in at least HOT STANDBY.

g;g SURVEILLANCE REQUIREMENTS 4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 using a full core power distribution ,FI shall beFl,calculated system. as FI, = F,d to be within its limit at the shall be determine following intervals:

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

b. At least once per 31 days of accumulated operation in T H0DE 1, and

c. Within four hour 3 if the AZIMUTHAL POWER TILT (T,) is > 0.030.

c e 11 only, when the percentage of 0 ELMWcTre _

detector locatioMrtr. r-strin fa 4, the calculated

/ value of F], shall be s. y 1% pri spans.on_yith the . 'j; t'

'se pj

^

See Special Test Exception 3.10.2. !

entag ,

detector locations e.g., ,

SE'Tiiis surveillance 7c -

N shall be perfomld__at-least- ce per 15 days of accumulci.ed operatipt/

m-MODE ~i. p,J 1 CALVERT CLIFFS - UNIT 1 3/4 2-6 Amendment No. 480--

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3/4.2- POWER ~ DISTRIBUTION LIMITS !

'3/4.2.3

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TOTAL INTEGRATED RADIAL PEAKING FACTOR - F! l I

LIMITING CONDITION FOR OPERATION 1 3.2.3 The calculated value of F, shall be limited to < 1.70

'$ ~,

APPLICABILITY: MODE 1*.

t ACTION: With FJ > 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either: 1

a. Be in at least HOT STANDBY, or b.

Withdraw and maintain the' full length CEAs at or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6 and [

reduce THERMAL POWER as follows: ,

1. Reduce THERMAL POWER to bring the combination of THERMAL !

POWER and F, within the limits of Figure 3.2.3-1, or - l

2. Reduce THERMAL POWER to less than or equal to the limit I established by the Better Axial Shape Selection System ,

(BASSS) as a function of F. r 1 When the THERMAL POWER. is determined from Figure 3.2.3-1, it

$$jl$ shall be used to establish a revised upper THERMAL POWER LEVEL' :

limit on Figure 3.2.3-2 (i.e., Figure 3.2.3-2 shall be truncated i at the allowable fraction of RATED THERMAL' POWER determined by !

Figure 3.2.3-1). Subsequent operation shall be maintained within '

the reduced acceptable operation region of Figure 3.2.3-2. 1 s

1 I

SURYEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4'are not applicable. j 4.2.3.2 F, shall be calculated as F; = F, using a full core power ' !

distribution mapping system. 'F, shall be detemined to be within its limit '

at the following intervals

a. Prior to operation above 70 percent'of RATED THERMAL POWER after each fuel loading, l

y

- N i cle 11 only, when the percentage of OPERA E inenre detector locat ons ., alls elow--Wr- -tF~caTcul ated -

value of F, shall be- prior tu wgardsca.aith the Y _

hs j See Spectal~ Test Exception 3.10.2. 1 CALVERT CLIFFS - UNIT I' 3/4 2-11 ' Amendment No. 400-- ,

.j

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 7

b. At least once per 31 day of accumulated operation in H0DE 4 1, and ,

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

4.2.3.3 P, shall be determined each time a calculation is required by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination.

Quf#

For Unit I + e percenta BLE incore I detector locations (e.g., strin s 1 75%, this surveillance i shall be performed at

)\ nce per 15 days of acc eration j

. a.

I" "

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CALVERT CLIFFS - UNIT 1- 3/4 2-12 Amendment No. 460

, . . . = - . .- ,- -. - .

3

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/4.3 INSTRUMENTATION l

-l 3/ 3.3 MONITORING' INSTRUMENTATION -i l

Incore Detectors j

-I LIMITING NDITION FOR OPERATION i 3.3.3.2 The ncore Detection System shall be OPERABLE with at eEst one ;

OPERABLE detec r segment in each core quadrant on each of t four axial .(

elevations cont 'ning incore detectors and as. further speci ed below: -l

a. For moni ring the AZIMUTHAL POWER TILT:' 'l At least tw quadrant symetric incore dete or segment groups at !

each of the .ur axial elevations. containi g incore detectors in ;

the outer 184 uel assemblies with suffi ent OPERABLE detector ,

segments in the p detector groups to co,pute at least-two AZIMUTHAL POWER T LT values at each of the four axial elevations i containing incore etectors. :

b. For' recalibration of he Excore N tron Flux Detector System:

1. At least 75%** of al incor detector segments, _l j i

2. A minimum of 9 OPERABL ncore detector segments at each' l g detector segment level nd

3. A minimum of 2_ OPE LE de ctor segments in the inner j 109 fuel assembli and 2 0 RABLE segments in the' outer j

108 fuel assembl'es at each s ment level.

c. For monitoring th UNRODDED PLANAR DIAL PEAKING FACTOR, the' ;

UNRODDED INTEG ED RADIAL PEAKING FA OR, or the linear heat _i rate:

l i

For Unit Cycle 11 only, the following req irements shall be substitut for Limiting Condition for Operation 3. 3.2.a:

At east eight quadrant symetric incore detector segment groups .j c ntaining incore detectors in the outer 184 fuel a semblies with

ufficient OPERABLE detector. segments in these detec r groups to.- !

compute at least one AZIMUTHAL POWER TILT value at each f the four axial elevations containing .incore detectors. and at east two ,

AZIMUTHAL POWER TILT values at three axial elevations c taining. )

incore detectors. _

For Unit 1 Cycle 11 only, the following requirement -shal be [ v substituted for Limiting Condition for Operation 3.3.3.2.b.1: :

At least 60% of all incore detector segments.

CALVERT . CLIFFS -' UNIT 1 3/4 3-31 Amendment No. 4M-

3/4.3 INSTRUMENTATION L ITING CONDITION FOR OPERATION (Continued) [

1. At least 75%~ of all incore detector locations, ;

2. A minimum of 9 OPERABLE incore detector segments at ach detector segment level, and

3. A minimum of 2 OPERABLE detector segments in th inner 09 fuel assemblies and 2 OPERABLE segments in he outer 8 fuel assemblies at each segment level. OPERABLE in ore detector segment shall consist of an PERABLE rhodium det tor constituting one of the segments n a fixed detec or string. An OPERABLE incore detec r location shall consis of a string in which at least t ree of the four incore tector segments are OPERABLE An OPERABLE quadrant s . tric incore detector s ment group shall consist of a minimum of three OPE LE rhodium incore d tector segments in 90 symetric fuel assemblies.

APPLICABILITY: Wher. the Incor Detection , stem is used for:

a. Monitoring the AZIMUTHA POWE TILT,

b. Recalibration of the Excor eutron Flux Detection System, or AL4

c. Monitoring the UNRODDED RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RAD AL PEAK NG FACTOR, or the linear heat rate.

ACTION: With the Incore Det : tion System ino erable, do not use the system for the above applicable m itoring or calibra on functions. The provisions of Specificati i s 3.0.3 and 3.0.4 are not applicable.

/

For Unit 1 Cycle 11 only, the following requirement shall he i substituted for Limiting Condition for Operation 3.3.3.2.c.1: !

At least 60% of all incore detector locations, '

CALVERT CLIFFS - UNIT I 3/4 3-32 Amendment No. -MO-W- ?

\, 3/4.3 INSTRUMENTATION

\(URVEILLANCEREQUIREMENTS /*

4.3. 2 The Incore Detection System shall be demonstrated OPERABLE:

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior its use and at least once per 7 days thereafter when requir d for:

1. Monitoring the AZIMUTHAL POWER TILT. i

2. calibration of the Excore Neutron Flux Det tion System.

3. Mon oring the UNRODDED PLANAR RADIAL PEAK NG FACTOR, the :

UNROD(ED INTEGRATED RADIAL PEAKING FACT R, or the linear i heat ra e.

b. At least once er REFUELING INTERVAL by performance of a CHANNEL !

CALIBRATION ope tion which exempts t neutron detectors but ,

includes all elec ronic components. he neutron detectors shall ,

be calibrated prio to installatio in the reactor core.

i Whis

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i CALVERT CLIFFS - UNIT 1 3/4 3-33 Amendment No.-180 l

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H y 3/4.3- INSTRUMENTATION BASES l

The OPERABILITY of the nc l

Metector_s r wi ecified minimum

! complement of equipment ensur em i t this system accu obtained from use of '

th re.

resent the spatial neutron.f ux f f

% ;of d

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-3/4.3.3.3 Seismic Instrumentation I i

The OPERABILITY of the seismic instrumentation ensures that sufficient ' -!

capability is available to promptly determine the magnitude of a. seismic l event and evaluate the response of those features important to safety. ~!

This capability is required to permit comparison of the measured response to that- used in the design basis for the facility and is consistent with -!

the recomendations of Regulatory Guide 1.12. " Instrumentation for i Earthquakes," April 1974. !

i 3/4.3.3.4 Meteorolooical Instrumentation '

The OPERABILITY of the meteorological instrumentation ensures that i sufficient. meteorological data is available for estimating potential I radiation coses to the public as a result of routine or accidental release !

of radioactive materials to the atmosphere. This capability is required to !

19 8 evaluate the need for initiating protective measures to protect' the health -

and safety of the public and is consistent with the recommendations!of' #

-Regulatory Guide 1.23 "Onsite Meteorological Programs," February 1972, as i supplemented by Supplement 1 to NUREG-0737.

i 3/4.3.3.5 Remote Shutdown Instrumentation

.f, k

The OPERABILITY of the remote shutdown instrumentation ensures that -!

sufficient capability is available to pemit shutdown and maintenance of. .

HOT STANDBY of the facility from locations outside of the Control Room.

This capability is required in the event Control Room habitability is lost j and is consistent with General Design Criteria 19 of 10 CFR Part 50.

t 3/4.3.3.6 Post-Arcident Instrumentation

I The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available.on selected plant. parameters to monitor !

i and assess these variables' following an accident. This capability is consistent with the recomendations-of Regulatory Guine 1.97,

" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and j NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

i t

CALVERT CLIFFS - UNIT I B 3/4 3-2 Amendment No. -ifr9- j j -

mgu r

B f r '-

ATTACHMENT (2) 1ll 6.

UNIT 2 TECHNICAL SPECIFICATION REVISED PAGES )

5 TABLE OF CONTENTS IV -1 3/42 -

3/42-6 3/42-7 3/4 2 j 3/4 2-12 j

-t 3/4 3-31 3

3/4 3-32' ,i 3/4 3-33 BASES 3/43-2 J I-

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. TABLE OF CONTENTS -;

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LIMITING CONDITIONS FOR OPERATION.AND SURVEILLANCE REQUIREMENTS SECTION PAGE- !

-3/4.3 INSTRUMENTATION l i

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION l . . . . . . . .. l3/4 3-1 i i

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM:

INSTRUMENTATION . . . . . . . . . . . .. . . . . . . . 3/4 3-11 ,

t 3/4.3.3 MONITORING INSTRUMENTATION 1 Radiation Monitoring Instrumentation - . . . . . . . 3/4 3-27 t Irccra Detect:rs ................. 3/4 3-31 l' 'l Seismic ~ Instrumentation . . . . . . . . 1 . . .. . 3/4 3 ;

Meteorological. Instrumentation .......... 3/4 3-36 !

Remote Shutdown Instrumentation . . . . . . . . . . 3/4 3-39 ,

Post-Accident Instrumentation . . . . . . . . . . . .

3/4 3-42 ,

Fire Detection Instrumentation .......... -3/4 3-46 Radioactive Gaseous Effluent Monitoring Instrumentation ~. . . . . . . . . . . . . . . . . . 3/4 3-50 Radioactive Liquid Effluent Monitoring '

Instrumentation . . . . . . . . . . . . . . .-... . 3/4 3 ';

i 3/4.4 REACTOR COOLANT SYSTEM 1

1956

. 3/4.4.1- COOLANT LOOPS AND 'C00LANT CIRCULATION :

STARTUP and POWER OPERATION . . . . . . . . . . . .- 3/4.4 !

HOT STANDBY . . . . . . . . . . . . . . . . . . ... . 3/4 4-2 J Shutdown ...................... 3/4 4 3/4.4.2 SAFETY VALVES . . . . . . . . . . . . . . . . . . . 3/4 4-6 i i

3/4.4.3 RELIEF VALVES . . . . . . . . . . . . . . . . . . . 3/4 4-7; 'l 3/4.4.4 PRESSURIZER . . . . . . . . . . . . . . ... . . . . 3/4 4-8 3/4.4.S STEAM GENERATORS . . . . . . . . . . . . . . .-. . 3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems . . . . . . . . . . . . . 3/4 4-16 :

Reactor Coolant. System Leakage .......... 3/4 4-18 i

3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . . . . . 3/4 4-20 -

3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . . ... 3/4 4-23 :

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CALVERT CLIFFS.- UNIT 2 IV ' Amencment ' No. 4bHF- l l'

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, q 3/4.2' POWER DISTRIBUTION LIMITSL

.i SURVEILLANCE REQUIREMENTS (Continued)' j i

c. Verifying at least once per 31 days that the AXIAL SHAPE-INDEX is -

maintained within the limits of Figure 3.2.1-2, where.100 percent' .i of the allowable. power represents the maximum THERMAL POWER allowed by the following expression: }j; I

MxN '

where: !

1. M is the maximum allowable THERMAL POWER level for the ;

existing Reactor Coolant Pump combination. '

t

2. N is the maximum allowable fraction of RATED THERMAL POWER as detemined by the FI, curve of Figure 3.2.1-3. ll 4.2.1.4 Incore Detector Monitorino System - The Incore Detector Monitoring.

System may be used for monitoring the core power distribution by verifying [

that the incore detector Local Power Density alams:

l

a. Are adjusted to satisfy the requirements of the core power 31 daym(of accumulated operation in MODE 1.distritgt fon Mmap wh !!

b. Have their alarm setpoint adjusted to.less than or equal to the j

- limits shown on Figure 3.2.1-1 when.the following factors are -!

appropriately included in the setting of these alarms:

l

1. A measurement-calculational uncertainty factor of 1.062. 4 s

2. An engineering uncertainty. factor of 1.03. M!

J

3. A linear heat rate uncertainty factor of 1.002.due to axial !

fuel'densification and themal expansion, and

4. A THERMAL POWER measurement uncertainty factor'of 1.02. !

5 Unit 2 Cycle 10 only, when the percentage of. OPERABLE inc Y detec ations (e.g.. . strings) falls below 75%, this sur ance- '!

shall be per . at least once per 15 days of accum operation; 4

'y :?

in MODE 1. , d

?

' ,, Xf !

For Unit 2 Cycle 10 only n the perce of . 0PERABLE. incore ,

detector locations . strings) falls below 754, measurement-- j' l calculational -

ainty factor on linear heat rate shall '

eased: :

by 1% . .062 to 1.072) prior to comparison with the Techn1 ' ,

CALVERT CLIFFS - UNIT 2- 3/4'2-2 Amendment.No. 158.-

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i 3/4.2 POWER DISTRIBUTION LIMITS i 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FI, LIMITING CONDITION FOR OPERATION , 1 3.2.2.1 The calculated value of FI, shall be limited to 51.70 f APPLICABILITY: MODE 1*.

ACTION: With FI, > 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a. Withdraw and maintain full length CEAs at or beyond the Long Tenn .

Steady State Insertion Limits of Specification 3.1.3.6 and reduce t

, THERMAL POWER as follows:

1. Reduce THERMAL POWER to bring the combination of THERMAL POWER and FI, within the limits of Figure 3.2.2-1, 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 FI,; or

b. Be in at least HOT STANDBY.

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

4.2.2.1.2 F! shall be calculated by the expression FI = F,, (1+T ) when F y is determined with a non-full Core Power Distribution, Mapping Sy, stem and when detennined with a full Core Power shall be calculated Distribution as FI, = F,,P Mapping System. y shall be determined to be within its limit.

at the following intervals:

a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, M 2 Cycle 10 only, when the percentage of RAB M detector loca trings %, the calculated

.e ine o . o V

See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 2 3/4 2-6 Amendment No. 45&-

?

1 3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 31 day ~

and of accumulated operation in MODE 1, y t

c. Within four hours if the AZIMUTHAL POWER TILT (T,) is > 0.030. '

4.2.2.1.3 Py shall be determined each time a calculation is required by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This detennination shall be ;

limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.

4.2.2.1.4 T shall be determined each time a calculation of Py is made using a non tull Core Power Distribution Happing System and the value of T, used to detennine Py shall be the measured value of T,. ,

3 For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance /4 shall be performed at least once per 15 days of accumulated operation 1 in MODE 1 Y -

CALVERT CLIFFS - UNIT 2 3/4 2-7 Amendment No.-458- l r

I 1

It 3/4'2. . POWER-DISTRIBUTION LIMITS 1 .

3/4.2.3' TOTAL INTEGRATED RADIAL PEAKING FACTOR - F{ .

r-LIMITING CONDITION FOR OPERATION -

3.2.3 The calculated value of P, shall be limited to 51.70 h[

APPLICABILITY: MODE 1*. j ACTION: With F, > 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either: I

\

a. Be in at least HOT STANDBY, or j

b. Withdraw and maintain the full length CEAs at or beyond the Long .[

Term Steady State Insertion Limits of Specification 3.1.3.6 and reduce THERMAL POWER as follows: ;

i

1. Reduce THERMAL POWER to bring the combination of THERMAL POWER and F, within the limits of Figure 3.2.3-1, or -

i'

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 F,.

When the THERMAL POWER is determined from Figure 3.2;3-1 it [

shall be used to establish a revised upper THERMAL POWER LEVEL

limit on Figure 3.2.3-2 (i.e.. Figure 3.2.3-2 shall-be truncated ,

at the allowable fraction of RATED THERMAL POWER determined by .

Figure 3.2.3-1). Subsequent operation shall be maintained within.- .

the reduced acceptable operation region of Figure 3.2.3-2. j d

SURVEILLANCE REQUIREMENTS j 4.2.3.1 The provisions of Specification 4.0.4 are not applicable. j 4.2.3.2 F, shall be calculated by the expression F, = F, (1+T when F, is !

determined with a non-full Core Power Distribution Mapping Sy$) tem and shall be calculated as P, = F, when determined with a full' Core Power ;

2 Cycle 10 only, when the percent detector oc strings}-fal elow 75%, the calculated g. ;

e d crease Qomparison with the m m _h 1 See Special Test Exception 3.10.2.

i CALVERT CLIFFS - UNIT 2 3/4 2-11 Amendment No. SEP l

?

[ l 3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

Distribution Mapping System. P, shall be determined to be within its limit l at the following intervals:

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

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

and '

I

c. Within four hours if the AZIMUTHAL POWER TILT (T,) is > 0 330.

4.2.3.3 P, shall be determined each time a calculation is required by i using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination.

4.2.3.4 T shall be detennined each time a calculation of P, is made using f'

a non-full, Core Power Distribution Mapping System and the value of T, used

, to determine P, shall be the measured value of T,. '

ECM t

b c

/* For hl , when the percent geafd L detector locations (e.g., s e ow 75%, this surveillance jq' ;

shall be performed J -Je once per 15 ay - mulated operation

>P-s~ / ~. vXy~-

CALVERT CLIFFS - UNIT 2 3/4 2-12 Amendment No.156- i p .

i n -

~

. 3/4.3 INSTRUMENTATION

/4.3.3 MONITORING INSTRUMENTATION ,

Incore Detectors ~

LIMITI CONDITION FOR OPERATION

[ .;

3.3.3.2 e Incore Detection System shall be OPERABLE with' at ast one OPERABLE debector segment in each core quadrant on each of th four axial elevations co taining incore detectors and as further specif ~ d below:

j

l

a. For m itoring the AZIMUTHAL' POWER TILT:*

h At least wo quadrant symmetric incore detec r segment groups at-each of th four axial elevations containi incore detectors in i:3 the outer 14 fuel assemblies with suffic nt OPERABLE detector segments in ese detector groups to com ute at least two AZIMUTHAL POW 1

TILT values at each of he four axial elevations: 1 containing inco, detectors. i

b. For recalibration f the Excore Ne ron Flux Detection System:

3

1. At least 75%'* of 11 incor detector segments, d- *

2. A minimum of 9 OPE LE core detector segments at each- l; detector segment leve and j E 3.

i A minimum of 2 OPE LE etector segments in the inner l 109 fuel assemblie and 2 PERABLE segments in the outer 108 fuel assembli s at ::ac segment level. !

j i

l

.i For Unit Cycle 10 only, the following re uirements shall be.

substitu d for Limiting Condition for Operation 3.3.2.a: .1 A least eight quadrant symmetric incore detecto segment groups ,

-ontaining incore detectors in- the outer 184 fuel ssemblies with 6 i sufficient OPERABLE detector segments'in these dete or groups to !

compute at least one AZIMUTHAL POWER TILT value~at eac. of the four-axial elevations containing ' incore detectors and. at least~ two a AZIMUTHAL POWER TILT values at three axial . elevations ntaining. d incore detectors. !

For Unit 2 Cycle 10 only, the following requirement 'sha q substituted for Limiting Condition for Operation 3.3.3.2.b.1: be . yl

[

At least 60% of all incere detector segments.

CALVERT CLIFFS - UNIT 2 3/4 3-31 Amendment No. -193-1 O

3/4.3 INSTRUMENTATION 3'

LIMITING CONDITION FOR OPERATION (Continued) l

c. For monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat .

rate:

I. At least 75%* of all incore detector locations, ~?C

. A minimum of 9 OPERABLE incore detector segments a each detector segment level, and

3. minimum of 2 OPERABLE detector segments in e inner 109 el assemblies and 2 OPERABLE segments in the outer 108 fu 1 assemblies at each segment level. ;

An OPERABLE incore etector segment shall consist of p, OPERABLE rhodium >

detector constitutin one of the segments in a fixe detector string.

An OPERABLE incore dete tor location shall consi of a string in which at 'I least three of the four core detector segment are OPERABLE.

An OPERABLE quadrant symmet 'c incore detect segment group shall consist of a minimum of three OPERABL rhodium inc e detector segments in 90 symmetric fuel assemblies.

s APPLICABILITY: When the Incore D tec on System is used for: ;

a. Monitoring the AZIMUTHAL ER TILT,

b. Recalibration of the core h utron Flux Detection System, or

c. Monitoring the UNR DED PLANAR DIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKIN FACTOR, or the linear heat -

rate.

ACTION: With the Into e Detection System inope ble, do not use the system for the above applic le monitoring or calibratio functions. The provisions of Speci 1 cations 3.0.3 and 3.0.4 are n

applicable. ;

I

'I

/ For Unit 2 Cycle 10 only, the following requirement sh 1 be substituted for Limiting Condition for Operation 3.3.3.2.c.I: -

S l

At least 60% of all incore detector locations, g CALVERT CLIFFS - UNIT 2 3/4 3-32 Amendment No.4FA

,3/4.3' INSTRUMENTATION URVEILLANCE REQUIREMENTS

4. 3.2 The Incore Detection System shall be demonstrated OPERABLE:

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use and at least once per 7 days thereafter when require for:

. Monitoring the AZIMUTHAL POWER TILT.

2. Recalibration of the Excore Neutron Flux Detec on System.

3. M itoring the UNRODDED PLANAR RADIAL PEAKIG FACTOR, the UN DDED INTEGRATED RADIAL PEAKING FACTOR, r the linear heat ate. .

b. At least on per REFUELING INTERYAL by p formance of a CHANNEL CALIBRATION eration which exempts the utron detectors but ;

includes all e ectronic components. Th neutron detectors shall be calibrated p dor to installation i the reactor core.

i limitu s !

b b

I CALVERT CLIFFS - UNIT 2 3/4 3-33 Amencment No.-F91- I

'3/4.3 INSTRUMENTATION ,

BASES i

~

ectors The OPERABILITY of t e ctors with the ec444 'I complement of equipment ensures t .. nts obtained from use of y this system accur + . sent the spatial neutron htrihttionof ,

3/4.3.3.3 Seismic Instrumentation The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly detennine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capabliity is required to pennit comparison of the measured response-to that used in the design basis for the facility and is consistent with i the recommendations of Regulatory Guide 1.12. " Instrumentation for '

Earthquakes," April 1974.

3/4.3.3.4 Meteorological Instrumentation The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release -

of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health M8 and safety of the public and is consistent with the recomendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February 1972, as supplemented by Supplement I to NUREG-0737.

3/4.3.3.5 Remote Shutdown Instrumentation The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pennit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the Control Room.

This capability is required in the event Control Room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR Part 50.

3/4.3.3.6 Post-Accident Instrumentation The OPERABILITY of the post-accident instrumentation ensures that sufficient infonnation is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentatfon for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

I

)

l CALVERT CLIFFS - UNIT 2 3 3/4 3-2 Amencment No. -14P l l

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ML20059H705

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