Text

Proposed Tech Specs Re cycle-specific Parameter Limits
	ML20011F435
Person / Time
Site:	Millstone
Issue date:	02/21/1990
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20011F434	List: ML20011F433; ML20011F435; ML20011F436;
References
	B13435, NUDOCS 9003060030
	Download: ML20011F435 (36)
	v • d • e

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. i Docket No. 50 423 !

B13435 I

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Attachment 2 t Millstone Unit No. 3 Proposed Revision to Technical Specificaticas ,

Cycle Specific Parameter Limits

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t DEFINITIONS {

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SECTION EAGI

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o 1.32' SLAVE RELAY TEST............................................. 16 1 1.33 SOURCE CHECK................................................. 1-6 :

1.34 STAGGERED TEST BASIS......................................... 16 ,

1.35 THERMAL P0WER................................................ 1-6 :

1.36 TRIP ACTUATING DEVICE OPERATIONAL TEST....................... 16 l.37 UNIDENTIFIED LEAKAGE......................................... 1-6 :

1.38 UNRESTRICTED AREA............................................ 1-6

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1.39 VENTING...................................................... 1-7 .;

1.40 SPENT FUEL POOL STORAGE PATTERNS............................. 1-7 1,41 SPENT FUEL P00L STORAGE PATTERNS................ ............ 1-7 :

1.42 CORE OPERATING LIMITS REP 0RT................................ 1-7 TABLE-1.1 FREQUENCY N0TATION................ ................... , 1-8 i

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TABLE 1.2 O P ERAT I ONA' M00 E S . . . . . -, , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-9 ;

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MILLSTONE - UNIT 3 ii i

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS 1 1

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SECTION Pf_GI :

i 3/4.0 APPLICABILITY............................................... 3/4 0 1 3 3/4.1 REACTIVITY CONTROL SYSTEMS ,

3/4.1.1 BORATION CONTROL Shutdown Margin - T,yg Greater Than 200'F................ 3/4 1 1

' Shutdown Margin - T,yg Less Than or Equal to 200'F. . . . . . . 3/4 1-3 Moderator Temperature Coefficient........................ 3/4 1-4 ;

Minimum Temperature for Criticality...................... 3/416 1

L 3/4.1.2 BORATION SYSTEMS !

Flow Path - Shutdown..................................... 3/4 1-7 L Flow Paths - Operating................................... 3/4 1 8 ;

1 L Charging Pump Shutdown................................. 3/4 1-9 i L Charging Pumps - Operating...............................

3/4 1 10 ,

s Dorated Water Source - Shutdown.......................... 3/4 1-11 j Borated Water Sources - Operating.,...................... 3/4 1 12. .

- 3/4.1.3- HOVABLE CONTROL ASSEMBLIES -

Group Height............................................. 3/4 1-14

- TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE

. EVENT OF AN INOPERABLE FULL-LENGTH R00................... 3/4 1 16 -

L Position Indication Systems Operating.................. 3/4 1-17 :

Position Indication System - Shutdown.................... 3/4 1-18 Rod Drop Time............................................ 3/4 1-19 Shutdown Rod Insertion Limit............................. '3/4 1-20 >

Control Rod Insertion Limits............................. 3/4 1-21 ) I 3/4.2 POWER DISTRIBUTION LIMITS -

1 L 3/4.2.1 AXIAL FLUX DIFFERENCE.................................... 3/4 2 1 Four Loops 0perating..................................... 3/4 2-1 l

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. lNDil LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION Pf_G1 Three Loops 0perating.................................... 3/4/2-4 L 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F g (Z)..................... 3/4 2-7 Four Loops 0perating..................................... 3/4 2-7 Three Loops 0perating.................................... 3/4 2-11 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R................................................... 3/4 2 15 Four Loops 0perating..................................... 3/4 2-15 Three Loops 0perating.................................... 3/4 2-18

- 3/4.2.4 QUADRANT POWER TILT RATI0................................ 3/4 2 20 3/4.2.5 DNB 9ARAMETERS........................................... 3/4 2 23 TABLE 3.2-1 DNB PARAHETERS........................................ 3/4 2-24

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1/!.9 1NRTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...................... 3/4 3 1 1

TABLE 3.3 1 REACTOR TRIP SYSTEM INSTRUMENTATION................... 3/4. 3-2 l TABLE 3.3-2 k!ACf0R TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES.... 3/4 38 TABLE 4.3-1 P.EACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................................. 3/4 3-10 3/4.3.2 ENGIt!EERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.......................................... 3/4 3-15 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.......................................... 3/4 3-17 i TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM !

INSTRUMENTATION TRIP SETP0lNTS........................... 3/4 3-26 I

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[e ADMINISTRATIVE CONTROLS i ,.

SECTION PHE

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6.8 PROCEDURES AND PR0 GRAMS.......................................... 6 16 I i

t 6.9 REPORTING REQUIREMENTS........................................... 6-19 !

6.9.1 ROUTINE REP 0RTS................................................ 6-19

Startup Report................................................. 6-19 An n u a l Re p o rt s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 19 Annual Radiological Environmental Operating Report. . . . . . . . . . . . . 6-20 ;

Semiannual Radioactive Effluent Release Report. . . . . . . . . . . . . . . . . 6.21 Monthly Operating Reports...................................... 6 21 ,

tore Operating Limits Report........................... ....... 6 '

6.9.2 SPECIAL REPORTS.......... ..,............ ..................... 6 22 i 6.10 RECORD RETENT10N............ .......r...-................. ...... 6-22 g,11- RADIATION PROTEC110M_ PROGRAM.................................... 6-23 l

6.12 HIGH RADIATION AREA............................................. 6 23 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE i CALCULATION MANUAL (REM 0DCM).................................... 6-25 6.14 RADI0 ACTIVE WASTE TREATMENT..................................... 6 25 ,

b MILLSTONE - UNIT 3 xx

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DEFINITIONS VENTING 1.39 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not inply a VENTING process.

Sl'ENT FUEL POOL STORAGE PATTERNS:

1.(0 Region I spent fuel racks contain a cell blocking device in every 4th location for criticality control. This 4th location will be referred to as the blocked location. A STORAGE PATTERN refers to the blocked location and all adjacent and diagonal Region I cell locations surrounding the blocked location. Boundary configuration between Region I and Region 11 must have cell blockers positioned in the outermost row of the Region I perimeter, as shown in Figure 3.9 2.

1,41 Region II contains no cell blockers. , ,

CORE OPE 4ATING _ LIMITS Bffl[LL,[CQJJJ ,

1.42 The CORE OPERATIN3 LIMITS REPORT (COLR) is the unit-specific document that provides core operatir.g limits f'ar the current operating reload cycle. l These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.6. Unit Operation within these operating limits is addressed in individual specifications.

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9 MILLSTONE - UNIT 3 1-7

. REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT l

LIMITING CONDITION FOR OPERATION l 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the CORE OPERATING LIMITS REP 0 The maximum upper limit shall be less positive than +0.5 x 10~gTS (COLR).

Ak/k/'F for all the rods 1 withdrawn, beginning of cycle life (B0L), condition for power levels up to 70% RATED THERMAL POWER with a linear ramp to O Ak/k/'F at 100% RATED THERMAL POWER.

APPLICABILITY: BOL - MODES I and 2* only**. i End of Cycle life (E0L) Limit - MODES 1, 2, and 3 only**. l ACTION:

L With the MTC more positive than the BOL limit of Specification

a. ;

3.1.1.3 above, operation in MODES 1 and 2 may proceed provided: l 1

1. Control rod withdrawal limits are established and maintained ;

sufficient to restore the MTC to less positive than the above l limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY withic H1r rext 6 I hours. These withdrawsl li:n',ts shall be in addition to the :

insert;on 7,imita of Specification 3.1.3.6; l

l. 2. The control rods are maintained within the withdrawal limits l established above entil a subsequent calculation verifies that the MTC hat been restsred to within its limit for the all rods withdrawn condition; and

3. A Special Report is prepared and submitted to the Commission, pursuant to Specification 6.9.2, within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn c.ondition.

l b. With the MTC more negative than the E0L limit specified in the COLR, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With K,ff greater than or equal to 1.

- See Special Test Exceptions Specification 3.10.3.

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REACTIVITY CONTROL SYSTEMS ,

SURVEILLANCE REQUIREMENTS t

4.1.1.3 The MTC shall be determined to be within its limits during each :

fuel cycle as follows: -

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a. The MTC shall be measured and compared to the BOL limit of Specifi-

' cation 3.1.1.3, above, prior to initial operation above 5% of ;

RATED THERMAL POWER, after each fuel loading; and b.- The MTC shall be measured at any THERMAL POWER and compared to the 300 ppm surveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm. In the event this comparison indicates the MTC is more negative than the 300 ppm surveillance limit specified in the COLR, the MTC shall be ,

remeasured, and compared to the E0L MTC limit specified in the COLR, at least once per 14 EFPD during the remainder of the fuel -

cycle.

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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 and '

positioned within 112 steps (indicated position) of their group step counter demand position. !

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 j interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specifkation 3.1.1.1 is 8atisfied within I hour and be in HOT STANDBY wittiin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With one full-length rod trippable b'it inoperable due to causes other than addressed oy ACTION t., trovo, or :nisaligned from its group step ecunter demand height by more than 112 steps (indicated position), POWER OPERATION may continute provided that within 1 ,

hour: ,

1. The rod is restored to OPERABLE status within the above i

alignment requirements, or l 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Specification 3.1.3.6. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or

3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:

l 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; b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

MILLSTONE - UNIT 3 3/4 1-14

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. x REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION _

ACTION (Contimtd1 c) A power distribution map is obtagned from the movable incore detectors and F (Z) and F a withintheirlimitswi$hin72hobYs;reverifiedtobe-and '

d) With four loops o>erating, the THERMAL POWER level is !

reduced to less tian or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 i hours the High Neutron Flux Trip Setpoint is reduced to -;

less than or equal to 85% of RATED THERMAL POWER, or e) With three loops operating, the THERMAL POWER level-is i reduced to less than or equal to 50% of RATED THERMAL ;

POWER within the next hour and within the following 4 '

hours the Nettron Flux High Trip Setpoint is reduced to less than or equal to 60% of RATED THERMAL POWER. ,

c. With more than one rod trippable but inoperabis due to causes

, cther than addressed by ACTION a.. above, POWER OPERATION may '!

l. cortinue provided that: :

1. Withir I hour, the renainder of the rods in the bank (s) with !

the inoperable rods are aligned to within 112 steps of the '

inoperable rods while maintaining the rod sequence and ;

insertion limits of Specification 3.1.3.6. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 .

during subsequent operation, and '

2. The inoperable rods are restored to OPERABLE status within 72 l hours,

d. With more than one rod misaligned from its group step counter +

demand height by more than il2 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , SURVEILLANCE RE0VIREMENTS 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months exce)t during time intervals when the rod position deviation monitor is inoperaale, then verify the group positions at least .

once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . j-4.1.3.1.2 Each full-length rod not fully inserted in the core shall be j determined to be OPERABLE by m,vement of at least 10 steps in any one I

, ' direction at least once per 31 days.

1 MILLSTONE - UNIT 3 3/4 1 15

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REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD' INSERTION LIMIT

. LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall'be -limited in physical insertion as specified in the core operating limits report (COLR).

APPLICABILITY: MODES 1* and 2* **.

ACTION:

With a maximum of one shutdown rod inserted beyond the insertion limits specified in the COLR except for surveillance testing pursuant to Specification 4.1.3.1.2, within I hour either:

a. Restore the rod to within the limit specified in _the COLR, or

b. Declare the rod to be inoperable and apply Specification 3.1.3.1. j SURVEILLANCE RE0VIREMENTS !

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' i 4.1.3.5 Each shutdown rod snall be determined to'be within the insertion !

limits specified in the COLR:- I

a. Within 15 minutes prior to withdrawal of any rods in Control Bank '

A, B, C, or D during an approach to reactor criticality,.and j i

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

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See Special Test Exceptions Specifications 3.10.2 and 3.10 3.. -j ')

i i **With K,ff greater than or equal to 1. !

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. REACTIVITY CONTROL-SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified in the core operating limits report (COLR).

APPLICABILITY: MODES 1* and 2* **. -!

ACTION:

With the control banks inserted beyond the insertion limits specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a. Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or i

b. Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank posi.-

tion using the insertion limits specified in the COLR, or

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

SURVEILLANCE RE0VIREMENTS 4.1.3.6 The position-of each control bank shall be determined to be within the 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 rod insertion limit monitor is inoperable, then verify the individual rod positions at least_once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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See Special Test Exceptions Specifications 3.10.2 and 3.10.3. .

- With K,77 greater than or equal to 1. )

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3/4.2- POWER DISTRIBUTION LIMITS !

3 .

-3/4'2.1- AXIAL FLUX DIFFERENCE FOUR LOOPS OPERATING LIMITING-CONDITION FOR OPERATION j

.3.2.1.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the' target band (flux difference units) about the target flux difference. The target band is provided in the core operating limits report (COLR).

The indicated AFD may deviate outside the required target band at greater than ,

or equal to 50% but less than 90% of RATED THERMAL POWER provided the indicated j

' AFD is within the Acceptable Operation Limits specified in the COLR and the ;

cumulative penalty deviation time does not exceed I hour during the previous '

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The indicated AFD may deviate outside the required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

' APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER.*

ACTION: >

a. With the indicated AFD outside of the required-target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, I within 15 minutes either- t i

1. Restore the indicated AFD to within the target band limits, or

2. Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER. !

I b .- With the indicated AFD outside of the required target band for more than I hour of cumulative penalty deviation time during the previous I 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptable Operation Limits specified in the COLR and with THERMAL POWER less than 90% but equal to or greater than l 50% of RATED THERMAL POWER, reduce:

1

1. THERMAL POWER to less than 50% of RATED THERMAL POWER within 4 30 minutes, and i

2. The Power Range Neutron Flux - High** Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special. Test Exceptions Specification 3.10.2.-

- Surveillance testing of the Power Range Neutron Flux Channels may be j performed pursuant to Specification 4.3.1.1 provided the indicated AFD is j maintained within the Acceptable Operation Limits specified in the COLR. A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the j required target band during testing without penalty deviation.

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_ 3/4 2-1

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, I b POWER DISTRIBUTION LIMITS l LIMITING CONDITION FOR OPERATION l

1 ACTION (Continued) 1

c. With the indicated AFD outside of the required target band for more 1 than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation time during the previous l l

-24 hours and with THERMAL POWER less than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AFD is-within the required target band.

SURVEILLANCE RE0VIREMENTS _ )

' 4.2.1.1.1 The indicated AFD shall be determined to be within'its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a. Monitoring the indicated AFD for each OPERABLE excore channel:

1) At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and

2) At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the j AFD Monitor Alarm to OPERABLE status. '

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging. !

4.2.1.1.2 The indicated AFD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AFD to be outside the target band. Penalty deviation outside of the required target band shall be accumulated on a time basis of:

a. One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to' or above 50% of RATED THERMAL POWER, and -

b. One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50%

of RATED THERMAL POWER.

4.2.1.1.3 The target flux difference of each OPERABLE excore channel shall be l

determined by measurement at least once per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable.

1 4.2.1.1.4 The target flux difference shall be updated at least once per

=31 Effective Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.1.3 above or by linear interpolation between the most recently measured value and 0% at the end of the cycle life. The provi-sions of Specification 4.0.4 are not applicable.

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POWER DISTRIBUTION LIMITS

' AXIAL FLUX DIFFERENCE

THREE LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.2.1.2 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the target band (flux difference units) about the target flux difference. The target band is provided in the core operating limits report-(COLR).

The indicated AFD may deviate outside the required target band at greater than or equal to 32% but less than 65% of RATED THERMAL POWER provided the indicated AFD is within the Acceptable Operation Limits specified in the COLR and the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The indicated AFD may deviate outside the required target band at greater than 15% but less than 32% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER.*

ACTION:

a. With the indicated AFD outside of the required target band and with THERMAL POWER greater than or equal to 65% of RATED THERMAL POWER, within 15 minutes either:

1. Restore the indicated AFD to within the target band limits, or

2. Reduce THERMAL POWER to less than 65% of RATED THERMAL POWER.

b. With.the indicated AFD outside of the required target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptable Operation Limits specified in the {

COLR and with THERMAL POWER less than 65% but equal to or greater than 32% of RATED THERMAL POWER, reduce:

1. THERMAL POWER to less than 32% of RATED THERMAL POWER within 30 minutes, and L

L 2. The Power Range Neutron Flux - High** Setpoints to less than or l equal to 37% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

. *See Special Test Exceptions Specification 3.10.2.

o ** Surveillance testing of the Power Range Neutron Flux Channels may be L performed pursuant to Specification 4.3.1.1 provided the indicated AFD is

! maintained within the Acceptable Operation Limits specified in the COLR. A l- total-of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the required target band during testing without penalty deviation.

MILLSTONE - UNIT 3 3/4 2-4 1

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,. , POWER DISTRIBUTION LIMITS m, l LIMITING CONDITION FOR OPERATION l ACTION (Continued) =

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c. With the indicated AFD outside of the required target band for more i than I hour of cumulative penalty deviation time during the previous - l 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 32% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 32% of RATED THERMAL POWER until the indicated AFD is l within the required target band, i

-SVRVEILLANCE RE0VIREMENTS 4.2.1.2.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a. Monitoring the indicated AFD for each OPERABLE excore channel:

1) At least once per 7 days when the AFD Monitor Alarm is OPERABLE, >

and

2) At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the-AFD Monitor Alarm to OPERABLE status. ,

~

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2.1.2.2 The indicated AFD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AFD to be outside the target band. Penalty deviation outside of the required target band shall be accumulated on a time basis of:

! a. One minute penalty deviation for each 1 minute of POWER OPERATION L outside of the target band at THERMAL POWER levels equal to or above L

32% of RATED THERMAL POWER, and-

b. One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 32%

of RATED THERMAL POWER.

L 4.2.1.2.3 The target flux difference of each OPERABLE excore channel shall be determined by measurement at least once per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable.

4.2.1.2.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to Specification-4.2.1.2.3 above or by linear interpolation between the most recently measured value and 0% at the end of the cycle life. The provi- '

sions of Specification 4.0.4 are not applicable.

MILLSTONE - UNIT 3 3/4 2-5

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l: - MILLSTONE-- UNIT 3 3/4 2-6 t

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I- . .

POWER' DISTRIBUTION LIMITS 3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fg FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION I

j -3.2.2.1 Fg (Z) shall be limited by the following relationships:

F(Z)sFhTPK(Z)forP>0.5 g

P l RTP

-Fg (Z) $ F O K(Z) for P $ 0.5 0.5 l

RTP F the F limit at RATED THERMAL POWER (RTP) provided in the c0re=perati0glimitsreport(COLR).

o

, and Where: P = THERMAL POWER RATED THERMAL POWER K(Z) - the normalized F (Z) as a function of core height specified in the COLR. n I APPLICABILITY:- MODE 1. ,

' ACTION: j i

With Fg (Z) exceeding its limit: -l

a. Reduce THERMAL POWER at least 1% for each 1%gF (Z) exceeds the ;

limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High. Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower ~AT Trip Set- !

points have been reduced at least 1% for each 1% F (Z) exceeds i the limit, and n

b. Identify and correct the-cause of the out-of-limit condition.

prior to increasing THERMAL POWER above the reduced limit re- J quired by ACTION a., above; THERMAL POWER may then be increased J provided F (Z) is demonstrated through-incore mapping to be a within its nlimit. ]

> l 1

a MILLSTONE - UNIT 3 3/4 2-7 1

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POWER DI'STRIBUTION LIMITS SURVEILLANCE'RE0VIREMENTS :

4.2.2.1.1- The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 F xy shall be evaluated to determine ifgF (Z) is within its limit by:

a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER,

b. Increasing the measured Fxy_ component of the power _ distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties, C

c.. Comparing the F Specification 49. computed (F2.1.2b.,abMe)obtainedin to:

1) The F xy lioits for RATED THERMAL POWER (FRTP) for the appropriate x

measured core planes given in Specification 4.2.2.1.2e. and f.,

below, and

2) The relationship:

F "fRTP [3,pp 3,p)),

x x l

Where F is the limit for fractional THERMAL POWER operation expresshasafunctionofF RTP PF is the power factor multiplier for F specified9n.the MLR, and P is the fraction ofRATEDTHERMAL40WERatwhichF xy was measured.

xy according to:the following schedule:

d. Remeasuring F

1) When F x

is greater than the F xRTP limit for the appropriate -

measured core plane but less than the F relationship, C

. additional pog distrigution maps shalTYbe taken and F xY compared to F xy and F xy either: -

l a) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL C

POWER or greater, the THERMAL POWER at which F was last determined, or XY b) At least once per 31 Effective Full Power Days (EFPD),

whichever occurs first.

MILLSTONE - UNIT 3 3/4 2-8

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POWER DISTRIBUTION LIMITS SURVEILLANCE RE0VIREMENTS (Continued) i 1

RTP

2) ' Wher. the F x

is less than or equal to the F x limit for the appropriate measured core plane, additional- power distribution maps shall be taken and F compared to F RTP andFhy at least 4 x x once per 31 EFPD.

e. The F xy limits for RATED THEP. MAL POWER (F P) shall be provided for -

all core planes containing Bank "D"' control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per Specifica L tion 6.9.1.6;-

f. The F xy limits of Specification 4.2.2.1.2e., above, are not applica- i ble in the following core planes regions as measured in. percent of core height from the bottom of the fuel:

1) Lower core region from 0 to 15%, inclusive,

2) Upper core region from 85 to 100%, inclusive,

3) Within 2% of core height (i2.88 inches) of grid plane regions.

The total core height eliminated from the grid plane regions located between 15% and 85% of core height shall not exceed 20%

of total core heiOLt (144 inches).

l I 4) Core plane regions within 2% of core height 1 2.88 inches) about the bank demand position of the Bank "D" control rods.

g. With F x exceeding F x the effects of F xy on Fn(Z) shall- be evaluated to determine ifqF (Z) is within its limits.

4.2.2.1.3 When qF (Z) is measured for other than F xy determinations, an overall measured F (Z) shall be obtained from a power distribution map and 9

increased by 3% to account for manufacturing tolerances and further increased by 5%~to account for measurement uncertainty.

l MILLSTONE - UNIT 3 3/4 2-9

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~ MILLSTONE - UNITL3 3/4 2-10

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.- l POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL Fe,CTOR .1gf,Z1 THREE LOOPS OPERATING LIMITING CONDITION FOR OPERATION _

1 3.2.2.2 Fg (Z) shall be limited by the following relationships:

F(Z)1FhTP.[K(Z))forP>.0.325 g

P F(Z)1(FhTP)[K(Z)]forPs0.325 g

0.325 RTP L F The F limit at RATED THERMAL POWER (RTP) specified in the :

g chre operatibg limits report (COLR). !

l

, and i Where: P - THERMAL POWER '

RATED THERMAL POWER l- K(Z) - the normalized F (Z) as a function of core height H specified in the COLR. n APPLICABILITY: . MODE-1.

J ACTION:

With Fg (Z) exceeding its limit:

a. Reduce THERMAL POWER at least 1% for each 1% gF (Z) exceeds the L limit'within 15 minutes and similarly reduce the Power Range L Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER I

OPERATION may proceed for up .to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Set-points have been reduced at least 1% for each'1% Fg(Z) exceeds l the limit. The Overpower AT Trip Setpoint reduction shall be "

performed with the reactor in at least ' HOT- STANDBY.

I

b. Identify and correct the cause of the out-of-limit-condition prior to increasing THERMAL POWER above the reduced limit re-

k. quired by ACTION a., above; THERMAL POWER may then be increased W provided Fg (Z) is demonstrated through incore mapping to be within its limit.

y MILLSTONE - UNIT 3 3/4 2-11

POWER DISTRIBUTION LIMITS-SURVEILLANCE REOUIREMENTS (Cont'inued) l

2) When the F C

is_less than or equal to the F0 .65 RTP limit for the appropriatPmeasured core plane, additional *fower distribution 0

. maps shall be taken and F comparedtoF.65RTPandFfat l

x x x

""3 l' once per 31 EFPD. y u

e. The F xy limitsfor65%ofRATEDTHERMALPOWER(Fh65RTP)andt xy l multiplier (MFxy) shall be provided for all core planes containing l

Bank "D" control rods 'and all unrodded core planes in the COLR . l

. h f.

p The F xy limits of. Specification 4.2.2.2.2e., above, are not applicable

'in the following core planes regions as' measured in percent of core I height'from the bottom of the fuel:

l j

1) - Lower core region from 0 to 15%, inclusive, ;

i

2) Upper core region from 85 to 100%, inclusive, l

3) Within 2% of core height ( 2.88 ine.hes) of grid plane regions. :

l The total core height eliminated from the grid plane regions J l located between 15% and.85% of core height shall not exceed- 'l

.20% of total core height (144 inches), j

-j-L 4)- Core plane regions within 2% of core height (i2.88 inches) about sj l

the bank demand position of the Bank "D" control rods. l 1-

! g. With F C exceeding F l the effects of F o l to det rmine if FQ(Z is within its limns.n F (2) shall be evaluated O

j L

-4.2.2.2.3 When gF (Z) is measured for other than Fxy determinations, an overall measured F (Z) shall be obtained from a power distribution map and increased by .

n '

3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty. '

i r

MILLSTONE - UNIT 3- 3/4 2-13

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% I g MILLSTONE - UNIT-3' 3/4 2-14

, l f,POWERDISTRIBUTIONLIMITS k .3/4.2.3 RCS' FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL TACTOR i t

- FOUR LOOPS OPERATING LLIMITING CONDITION FOR OPERATION <

g 3.2.3.1 : The_ indicated Reactor Coolant System (RCS) total- flow rate and FAH shall be maintained as follows:

a.. RCS total flow rate 2 385,210 gpm, and-

<b.

FfH 1FR A P [1.0 + PFAH.(1.0 - P)]'

Where:

THERMAL POWER ,

1)- P RATED THERMAL POWER N-

2) F . Measured values of F N -

iko,re detectors to obtain $H)obtained by using the ower distribution map. movable The N

measured value of F should )e used since Specification 3.2.3kYb.-takesintoconsiderationa-measurement '

uncertainty of 4% for incore measurement, RTP N

3) F = The F limit at RATED THERMAL POWER in the core operating ik$itsreporkH(COLR),

4) PF an$H - The power. factor multiplier for FAHprovided in the COLR, 5)- The meas'ured value of RCS total flow rate-shall be used since-

. uncertainties'of 1.8% for flow measurement have been included in.

Specification 3.2.3.la. C l APPLICABILITY: MODE 1. '

ACTION:

With the RCS total flow rate or FAH outside the region of acceptable operation: I

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

N

1. Restore the RCS total flow rate and FAH to within the above h limits, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3 MILLSTONE - UNIT 3 3/4 2-15

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L POWER DISTRIBUTION LIMITS c,; .

RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 1THREE LOOPS OPERATING LLIMITING' CONDITION FOR OPERATION 3.2.3.2 The indicated Reactor Coolant System (RCS) total flow rate' and F AH shall- be maintained as follows: >

a. RCS total flow rate 1 304,780 gpm, and

b. F AH IFRA P (1.0 + PFAH.(1.0 - P))

Where:

=

THERMAL POWER ,

1) P RATED THERMAL POWER N

-2) F Measured values of F AN obtained by using the movable ibUoredetectorstoobtaingpowerdistributionmap. '

The measured value of .N should be used since Speci- -

fication,3.2.3.2b.takegHinto consideration a measure .

ment uncertainty of 4% for incore measurement, RTP

3) F - The F ik$its reporgH(limit COLR),at RATED THERMAL POWER.in the core operating

4) PFAH - The power factor multiplier for FAH in the COLR, and-

5) The measured value of RCS total flow rate shall be used since uncertainties of 2.0% for flow measurement have-been included in Specification 3.2.3.2a.

' APPLICABILITY: MODE.1.

ACTION:

- With the RCS total flow rate or F"i A outside the region of acceptable operation: +

L a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

N

1. Restore the RCS total flow rate and F 3H to within the above

, limits, or l

2. Reduce THERMAL POWER to less than 32% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 37% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

MILLSTONE - UNIT 3 3/4 2-18

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REACTIVITY CONTROL SYSTEMS BASES MODERATOR TEMPERATURE COEFFICIENT (Continued)

These corrections involved: (1) a conversion of the MDC used in the '

FSAR safety analyses to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC observed between E0L, all rods withdrawn, RATED THERMAL POWER conditions, and those most adverse conditions of moderator temperature and pressure, rod insertion, axial power- skewing, and xenon concentration that can occur in normal operation and

-lead to a significantly more negative EOL MTC at RATED THERMAL POWER. These corrections transformed the MDC value used in the FSAR safety analyses into the limiting End of Cycle Life (E0L) MTC value. The 300 ppm surveillance limit MTC value represents a conservative MTC value at a core condition of 300 ppm equilibrium boron concentration, and is obtained by making corrections for burnup and soluble boron to the limiting E0L MTC value.

The-Surveillance Requirements for measurement of the MTC at the beginning 4 and near the end of the fuel cycle are adequate to confirm that the MTC r remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel ,

burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that' the reactor will not be made critical with the Reactor . Coolant System average temperature less than 551. This limitation is required to ensure: (1) the moderator temperature coefficient is within it analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the P-12 interlock is above its setpoint, (4) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (5) the reactor vessel is above its minimum RT NDT temperature.

3/4.1.2 BORATION SYSTEMS The Boron Injection System ensures that negative reactivity control is availabla during each mode of facility operation. The components required to y perform this function include: (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 200, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an -assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOWN MILLSTONE - UNIT 3 8 3/4 1-2

3/4.2 POWER DISTRIBUTION LIMITS l BASES l l

The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (1) maintaining the minimum DNBR in the core greater than or equal to 1.30 during normal operation and in short-term transients, and (2) limiting the fission gas- release, fuel )ellet temperature, and cladding mechanical properties to within assumed des'gn criteria. In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 22000F is not exceeded.

The definitions of certain hot channel and peaking factors as_ used in these specifications are as follows:

Fq(Z) Heat Flux Hot Channel Factor, is defined as the maximum local hect.

flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods; F

AH Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power; and Fxy(Z) Radial Peaking Factor, is defined as the ratio of peak power density to average power density in the horizontal plane at core elevation Z.

1/4.2.1 AXIAL FLUX DIFFERENCE -

The . limits on AXIAL FLUX DIFFERENCE (AFD) assure that the Fn(Z) upper bound envelope of the F limit specified in the Core Operating Lim'its Report (COLR) times the normaliSed axial peaking factor is not exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions. .

The full-length rods may be positioned within the core in accordance with L their respective insertion limits and should be inserted near their normal L

position for steady-state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER l'

for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

l MILLSTONE - UNIT 3 8 3/4 2-1

POWER DISTRIBUTION LIMITS

/ .~ BASES s

AXIAL FLUX DIFFERENCE (Continued)

Although- it is intended that the plant will be operated with the AFD within the target band required by Specifications 3.2.1.1 and 3.2.2.1 about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels. This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited. Accordingly, a 1-hour penalty deviation limit cumulative during the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s- is provided for operation outside of the target band but '

within the limits specified in the COLR at THERMAL POWER levels between 50%

and 90% of RATED THERMAL POWER (four loops o)erating) or between 32% and 65%

of RATED THERMAL POWER (three loops operat1ng). For THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER (four loops operating) or between ;

j 15% and 32% of RATED THERMAL-POWER (three loops operating), deviations of the L AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects.this reduced significance.

Provisions for monitoring the AFD on an automatic basis are derived from '

the plant process computer through the AFD Monitor Alarm. . The computer deter-mines the 1-minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of RATED THERMAL POWER. During four loop operation at THERMAL POWER i levels between 50% and 90% and between 15% and 50% RATED THERMAL POWER, the i

! computer outputs an alarm message when the penalty deviation accumulates beyond l i the limits of I hour and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively. During three loop operation at l L THERMAL POWER levels between 32% and 65% and between 15% and 32% RATED THERMAL 1 POWER, the computer outputs an alarm message when the penalty deviation accumu-lates beyond the limits of I hour and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively.

Figures 8 3/4 2-la and B 3/4 2-lb show typical monthly target bands.

3/4.2.2 and 3/4.2.3 HEAT FLUX ~ HOT CHANNEL FACTOR and RCS FLOW RATE AND N_QCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, RCS flow rate, 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 22000F ECCS acceptance ,

criteria limit. !

l L Each of these is measurable but will normally only be determined -l l periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic l surveillance is sufficient to ensure that the limits are maintained provided:

, a. Control rods in a single group move together with no individual rod insertion differing by more than 12 steps, indicated, from the group demand position;

b. Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6; j MILLSTONE - UNIT 3 8 3/4 2-2

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'g -e POWER DISTRIBUTION LIMITS .

1 BASES .

l HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT

[HANNEL FACTOR (Continued)

When an gF measurement is taken, an allowance for both experimental errcr J and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System, and a 3% allowance is appropriate for manufacturing tolerance.

The' Radial Peaking Factor, Fxy(Z), is measured. periodically to provide ,

assurance that the Hot Channel Factor, F (Z), remains within its limit. The F limit for RATED THERMAL POWER (F RTO) as provided in the Core Operatin LMitsReportSpecification6.9.1.6w8determinedfromexpectedpowercontro manuevers over the full range of burnup conditions in the core. 1 When RCS flow rate and F AH are measured, no additional allowances are necessary-prior to. comparison with the limits of the Limiting Condition for Operation. Measurement errors of 1.8% for four loop flow and 2.0% for three loop flow for RCS total flow rate and 4% for F AH have been allowed for-in

' determination of the design DNBR value.

The measurement error for RCS total flow rate is based upon performing a l

precision heat balance and using the result to calibrate the RCS flow rate-l indicators. Potential fouling of the 'feedwater venturi which might not .be L detected could bias the- result from the precision heat balance in a non-conservative manner. Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi will be added if venturis are inspected and cleaned at least once for 18 months. Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending L various plant performance parameters. If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either :

the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

! The 12-hour periodic surveillance of indicated RCS flow is sufficient to I detect only flow degradation which could lead to operation outside the accept-able region of operation defined in Specifications 3.2.3.1 and 3.2.3.2.

3/4.2.4 OVADRANT POWER TILT RATIO ,

, The QUADRANT POWER TILT RATIO limit assures that the radial power distribu-l tion satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during STARTUP testing and ,

periodically during power operation. l l

L MILLSTONE - UNIT 3 8 3/4 2-6

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e ADMINISTRATIVE CONTROLS l ':

1: ,

l- SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

6.9.1.4 - Routine Semiannual Radioactive Effluent Release Reports covering the- '

operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. .

A supplemental report containing dose assessments for the previous year L shall be submitted annually within 90 days after January 1.

The report shall include that information delineated in the REM 0DCM.

- Any changes to the REM 0DCM ~ shall be submitted in the Semiannual Radioactive Effluent Release Report.

MONTHLY OPERATING REPORTS 6.9.1.5 Routine reports of' operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, one copy 'to the Regional Administrator Region I, and one copy to the NRC Resident Inspector, no later than the 15th of each month following the' calendar month covered by the- .

report.

CORE OPERATING LIMITS REPORT 6.9.1.6.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, '

4

2. Shutdown Rod Insertion Limit for Specification-3/4.1.1.5, i

3. Control Rod Insertion Limits for Specification 3/4.1.1.6,

4. Axial Flux Difference Limits, target band for Specifications 3/4.2.1.1 and 3/4.2.1.2, 1

5. Heat Flux Hot Channel Factor, K(Z), Power Factor Multiplier for Specifications 3/4.2.2.1 and 3/4.2.2.2.

6. RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3.

I

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

, MILLSTONE - UNIT 3 6-21

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6.9.l'.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1. -WCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology," J July 1985.(W Proprietary). 1

2. WCAP-8385, " Power Distribution Control. and load Following Procedures

- Topical Report," September,1981 (W Proprietary).

3. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC)

January 31, 1980 -

Attachment:

Operation and Safety-Analysis Aspects of an Improved Load Follow Package.

4. - NUREG-800, Standard Review Plan,'U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981 Branch Technical. Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),

Revision 2,' July 1981.

5. WCAP-9220-P-A, Rev. 1, " Westinghouse ECCS Evaluation Model - 1981 Version," February 1982 (W Proprietary).

6. WCAP-11946, " Safety Evaluation Supporting a More Negative E0L Moderator- Temperature Coefficient Technical Specification for the Millstone Nuclear Power Station Unit 3 September 1988, (W Proprietary).

6.9.1.6.c The ' core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits,. nuclear limits such as shutdown margin, and transient and.

accident analysis limits) of the safety analysis are met.

6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document ~ Control Desk with copies to -the Regional Administrator and Resident' Inspector.

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. MILLSTONE - UNIT 3 6-21a 4

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Docket No. 50-423 B13431-i; .

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-Attachment 3 Millstone Unit No. 3 Sample Core Operating Limits Report ,

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February 1990 l

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ML20011F435

Text

Attachment:

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