Text

Proposed Tech Specs Re Power Distribution Limits for Fuel Cycle 5 Reload Operation
	ML20053C164
Person / Time
Site:	Brunswick
Issue date:	05/20/1982
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20053C160	List: ML20053C159; ML20053C164; ML20053C174; ML20053C186;
References
	NUDOCS 8206010539
	Download: ML20053C164 (29)
	v • d • e

r INDEX DEFINITIONS SECTION 1.0 DEFINITIONS PAGE ACTI0N....................................................... 1-1 AVERAGE PLANAR EXP0SURE...................................... 1-1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE................... 1-1 CHANNEL CALIBRATION.......................................... 1-1 CHANNEL CHECK................................................ 1-1 CHANNEL FUNCTIONAL TEST...................................... 1-2 CORE ALTERATION.............................................. 1-2 CRITICAL POWER RATI0......................................... 1-2 DOSE EQUIVALENT I-131........................................ 1-2 E-AVERAGE DISINTEGRATION ENERGY.............................. 1-2 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME........... 1-2 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME. . . . 1-3 FREQUENCY N0TATION........................................... 1-3 IDENTIFIED LEAKAGE........................................... 1-3 ISOLATION SYSTEM RESPONSE TIME . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 L IMITING CONTROL R0D PATTERN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 LINEAR HEAT GENERATION RATE.................................. 1-3 LOGIC SYSTEM FUNCTIONAL TEST................................. 1-3 MAXIMUM FRACTION OF LIMITING POWER DENSITY................... 1-4 MAXIMUM TOTAL PEAKING FACT 0R................................. 1-4 MINIMUM CRITICAL POWER RATI0................................. 1-4 0200010 BRUNSWICK - UNIT 2 I Amendment No.

INDEX DEFINITIONS SECTION 1.0 DEFINITIONS (Continued) PAGE ODYN OPTION A................................................ 1-4 ODYN OPTION B................................................ 1-4 O P E RAB LE - O PE RAB I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 O P E RAT ION AL COND ITION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 PHYSICS TESTS................................................ 1-4 P RE S SU RE BOU ND ARY LEAKAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 PRIMARY CONTAINMENT INTEGRITY................................ 1-5 RATED THERMAL P0WER.......................................... 1-5 REACTOR P ROTECTION SYSTEM RESPONSE TIME . . . . . . . . . . . . . . . . . . . . . . 1-5 REPORTABLE OCCURRENCE........................................ 1-5 ROD DENSITY.................................................. 1-5 SECONDARY CONTAINMENT INTEGRITY.............................. 1-6 SHUTDOWN MARGIN.............................................. 1-6 S P I RAL RE L0 AD . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 SPIRAL UNL0AD................................................ 1-6 TRERMAL P0WER................................................ 1-6 TOTAL PEAKING FACT 0R......................................... 1-6 UNIDENTIFIED LEAKAGE.........................................- 1-6a FREQUENCY NOTATION, TABLE 1.1................................ 1-7 OPERATIONAL CONDITIONS, TABLE 1.2............................ 1-8 BRUNSWICK - UNIT 2 II Amendment No.

y- - n 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these specifications may be achieved. The defined terms appear in capitalized type and are applicable throughout these Technical Specifications.

ACTIqN ACTIONS are those additional requirements specified as corollary statements to each specification and shall be part of the specifications.

AVERAGE PLANAR EXPOSURE The AVERAGE PLANAR EXPOSURE shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

AVERACE PLANAR LINEAR HEAT GENERATION RATE The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be anplicable to a specific planar height and is equal to the sum of the LINEAR HEtt GENERATION RATES for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment as necessary of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indication and/or status derived from independent instrument channels measuring the same parameter.

BRUNSWICV - UNIT 2 1-1 Amendment No.

l

DEFINITIONS CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABLITY including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABLITY including alarm and/or trip functions.

CORE ALTERATION CORE ALTERATION shall be the addition, removal, relocation, or movement of fuel, sources, incore instruments, or reactivity controls in the reactor core with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of the movement of a component to a safe, conservative location.

CRITICAL POWER RATIO The CRITICAL POWEk ctTIO (CPR) shall be ratio of that power in the assembly which is calculated, by application of the GEXL correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

DOSE EQUIVAI.ENT I-131 DOSE EQUIVALENT I-131 shall be concentration of I-131, pCi/ gram, which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The following is defined equivalent to 1pCi of I-131: I-132, 29pci; I-133, 3.6pci; I-134, insignificant; I-135, 12pci.

E-AVERAGE DISINTEGRATION ENERGY 5-AVERAGE DISINTEGRATION ENERGY shall be the average, weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling, of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes with half lives greater than 15 minutes making up at least 95% of the total non-iodine activity in the coolant.

EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME The EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS actuation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

^

BRUNSWICK - UNIT 2 l-2 Amendment No.

r-DEFINITIONS END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME The END-OF-CYCLE RECIRCULATION PUMP TRI? SYSTEM RESPONSE TIME shall be that time interval to recirculation pump breaker trip from initial movement of the associated:

a. Turbine stop valves, and

b. Turbine control valves.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAXAGE IDENTIFIED LFAKAGE shall be:

a. Leakage into collection systems, such as pump seal or valve packing

. leaks, that is captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not be PRESSURE BOUNDAA LEAKAGE. -

ISOLATION SYSTEM RESPONSE TIME '

The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays where applicable.

LIMITING CONTROL ROD PATTERN A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a limiting value for APLHGR, LHGR, or MCPR.

LINEAR HEAT GENERATION RATE LINEAR HEAT GENERATION RATE (LHGR) shall be the power generation in an arbitrary length of fuel rod, usually one foot. It is the integral of the heat flux over the heat transfer area associated with the unit length, usually measured in KW/ft.

LOGIC SYSTEM FUNCTIONAL TEST A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all relays and contacts of a logic circuit, from sensor output to activated device, to ensure that components are OPERABLE.

BRUNSWICK - UNIT 2 1-3 Amendment No.

DEF7NITIONS MAXIMUM FRACTION OF LIMITING POWER DENSITY MAXIMUM FRACTION OF LIMITING POVER DENSITY shall be the highest value of LINEAR HEAT GENERATION RATE (LHGR) divided by the corresponding LHGR limit occurring in the reactor core.

MAXIMUM TOTAL PEAXING FACTOR The MAXIMUM TOTAL PEAKING FACTOR (MTPF) shall be the largest TPF which exists in the core for a given class of fuel for a given operating condition.

MINIMUM CRITICAL POWER RATIO The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

ODYN OPTION A ODYN OPTION A shall be analyses which refer to minimum critical power ratio limits which are determined using a transient analysis plus an analysis uncertainty penalty.

ODYN OPTION B ODYN OPTION B shall be analyses which refer to minimum critical power ratio limits determined using a transient analysis which includes a requirement for 20% scram insertion times to reduce the analysis uncertainty penalty.

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL CONDITION An OPERATIONAL CONDITION shall be any one inclusive combination of mode switch position and average reactor coolant temperature as indicated in Table 1.2.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and are 1) described in Section 13 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

BRUNSWICK - UNIT 2 1-4 Amendment No.

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PRESSURE BOUNDARY LEAKAGE , !

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PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isol, table fault in a reactor coolant system component body, pipe wall, orf vessel wall. '

PRIMARY CONTAINMENT LNTEGRITY PRIMARY CONTAINMENT INTEGRITY shall exist when:

a. All penetrations required to be closed during accident conditions are either:

1. Capable of being closed by an OPERABLE containment automatic isolation valve system, or

2. Closed by at least one manual valve, blind flange, or

/ deactivated automatic valve secured in its closed position,

except as provided in Table 3.6.3-1 of Specification 3.6.3.1, or

b. All equipment hatches are closed and sealed.

c. Each containment air lock is OPERABLE pursuant to Specification 3.6.1.3.

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d. The containment leakage rates are within the limits of Specification

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The sealing mechanism associated with each penetration (e.g., welds, 4 bellows, or 0-rings) is OPERABLE.

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, , RATED THERMAL POWER -

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' FATED THERMAL POWER shall be a total reactor. core heat transfer rate to the r'eactor coolant of 2436 MWT.

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) REACTOR PROTECTION SYSTEM RESPONSE TIME REACTOR PROTECTION SYSTEM RESPONSE TIME shlll be the time interval from when l the ' monitored parameter' exceeds its trip 'setpoint at the channel sensor until '

de-energization of the scram pilot valve solenoids.

~~ i REPORTABLE OCCURRENCE r

A REPORTABLE OCCURRENCE shall be any o,f those conditions specified in

! Specifications 6.9.1.8 and 6.9.1.9.

ROD DENSITY ~/

ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number of notches'. All rods fully inserted are equivalent to 100% ROD' DENSITY. '

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BRUNSWICK - UNIT 12 } ,

1-5 Amendment No.

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o DEFINITIONS SECONDARY CONTAINMENT INTEGRITY SECONDARY CONTAINMENT INTEGRITY shall exist when:

a. All automatic Reactor Building ventilation system isolation valves or dampers are OPERABLE or secured in the isolated position.

h. The standby gas treatment system is OPERABLE pursuant to Specification 3.6.6.1.

c. At least one door in each access to the Reactor Building is closed.

d. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.

SHUTDOWN MARGIN SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor would be suberitical assuming that all control rods capable of insertion are fully inserted except for the analytically determined highest worth rod which is assumed to be fully withdrawn, and the reactor is in the shutdown condition, cold, 68'F , and Xenon-f ree.

SPIRAL RELOAD A SPIRAL RELOAD is the reverse of a SPIRAL UNLOAD. Except for two diagonal fuel bundles around each of the four SRMs, the fuel in the interior of the core, symmetric to the SRMs, is loaded first.

SPIRAL UNLOAD A SPIRAL UNLOAD is a core unload performed by first removing the fuel from the outermost control cells (four bundles surrounding a control blade). Unloading continues in a spiral fashion by removing fuel from the outermost periphery to the interior of the core, symmetric about the SRMs, except for two diagonal fuel bundles around each of the four SRMs.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals.

b.

The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TOTAL PEAKING FACTOR The TOTAL PEAKING FACTOR (TPF) shall be the ratio of local LHGR for any specific location on a fuel rod divided by the average LHGR associated with the fuel bundles of the same type operating at the core average bundle power.

BRUNSWICK - UNIT 2 1-6 Amendment No.

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DEFINITIONS UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.

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BRUNSWICK - UNIT 2 1-6a Amendment No.

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w 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4 1.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.1.1 The SHUTDOWN MARGIN shall be equal to or greater than 0.38% a k/k.

APPLICABILITY: CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

With the SHUTDOWN MARGIN less than 0.38% a k/k:

a. In CONDITION 1 or 2, reestablish the required SHUTDOWN MARGIN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . l

b. In CONDITION 3 or 4, immediately verify all control rods to be fully inserted, suspend all activities that could reduce the SHUTDOWN MARGIN, and demonstrate SECONDARY CONTAINMENT INTEGRITY within I hour; reestablish the required SHUTDOWN MARGIN.

c. In CONDITION 5, suspend CORE ALTERATIONS and other activities that could reduce the SHUTDOWN MARGIN, fully insert all insertable control rods, and demonstrate SECONDARY CONTAINMENT INTEGRITY within I hour; reestablish the required SHUTDOWN MARGIN. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.1 THE SHUTDOWN MARGIN shall be determined to be equal to or greater than 0.38% a k/k:

a. By measurement within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to or during the first start-up af ter completing CORE ALTERATIONS, and l

b. By analytical determination within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter detection of a withdrawn control rod that is immovable or untrippable, except that the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable rod.

BRUNSWICK - UNIT 2 3/4 1-1 Amendment No.

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3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION PJLTE LIMITING CONDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT CENERATION RATES (APLHCR's) for each type of fuel as a function of AVERACE PLANAR EXPOSURE shall not exceed the following limits:

a. During two recirculation loop operation, the limits are shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, 3.2.1-6, 3.2.1-7, 3.2.1-8, or 3.2.1-9. l APPLICABILITY: CONDITION 1, when THERMAL POWER > 252 of RATED THERMAL POWER.

ACTION: With an APLHCR exceeding the limits of Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, 3.2.1-6, 3.2.1-7, 3.2.1-8, or 3.2.1-9, initiate l corrective action within 15 minutes and continue corrective action so that APLHGR is within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to less than 25% 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 4.2.1 All APLHGR's shall be verified to be equal to or less than the ~

applicable limit determined from Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, 3.2.1-5, 3.2.1-6, 3.2.1-7, 3.2.1-8 or 3.2.1-9:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and i

c. Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with a LIMITING CONTROL ROD PATTERN for APLHGR.

i BRUNSWICK - UNIT 2 3/4 2-1 Amendment No.

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POWER DISTRZBUTION LIMITS 3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The flow-biased APRM scram trip setpoint (S) and rod block trip setpoint (SRB) shall be established according to the following relationships:

S ;[ (0.66W + 54%) T SRB j( (0.66W + 42%) T where: S and SRB are in percent of RATED THERMAL POWER, W = Loop recirculation flow in percent of rated flow, T = Lowest value of the ratio of design TPF divided by the MTPF obtained for any class of fuel in the core (T _< 1.0), and Design TPF for: P8 X 8R fuel = 2.39 8 X 8R fuel = 2.39 7X7 fuel = 2.60 8X8 fuel = 2.43

, APPLICABILITY: CONDITION 1, when THERMAL POWER )_ 25% of RATED THERMAL POWER.

ACTION:

With S or SRB exceeding che allowable value, initiate corrective action within 15 minutes and continue corrective action so that S and SRB are within the required time limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or reduce THERMAL POWER to less than 25%

of RATED THZRMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2 The MIPF for each class of fuel shall be determined, the value of T calculated, and the flow-biased APRM trip setpoint adjusted, as required:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and

c. Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with a LIMITING CONTROL ROD PATTERN for MTPF.

i l

BRUNSWICK - UNIT 2 3/4 2-10 Amendment No.

i

POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3.1 The MINIMUM CRITICAL POWER RATIO (MCPR), as a function of core flow, shall be equal to or greater than the MCPR limit times the Kg shown in Figure 3.2.3-1, provided that the end-of-cycle recirculation pump trip system is OPERABLE per specification 3.3.6.2, with:

a. If ODYN OPTION A analyses are in effect, the MCPR limits are listed below:

1. MCPR for 7x7 fuel - 1.21*

2. MCPR for 8x8 fuel = 1.29

3. MCPR for 8x8R fuel = 1.26 and

4. MCPR for P8x8R fuel = 1.27

b. If ODYN OPTION B analyses are in effect (refer to specification 3.2.3.2), the MCPR limits are listed below:

1. MCPR for 7x7 fuel = 1.20*

2. MCPR for 8x8 fuel = 1.29

3. MCPR for 8x8R fuel = 1.21 and

4. MCPR for P8x8R fuel = 1.22 APPLICABILITY: CONDITION 1 when THERMAL POWER > 25% RATED THERMAL POWER ACTION:

a. With the end-of-cycle recirculation trip system INOPERABLE per Specification 3.3.6.2, operation may continue and the provisions of Specification 3.0.4 are not applicable with the following MCPR limit 4 adjustments:

1 1. Beginning-of-cycle (BOC) to end-of-cycle (EOC . minus 2000 MWD /t, within one hour determine that MCPR, as a function of core flow, is equal to or greater than the MCPR limit times the Kf shown in Figure 3.2.3-1 with:

a. If ODYN OPTION A analyses are in effect, the MCPR limits are listed below: ,

1. MCPR for 7x7 fuel = 1.20*

2. MCPR for 8x8 fuel = 1.29,

3. MCPR for 8x8R fuel = 1.25 and,

4. MCPR for P8x8R fuel = 1.26

b. If ODYN OPTION B analyses are in effect (refer to specification 3.2.3.2), the MCPR limits are listed below:

1. MCPR for 7x7 fuel = 1.20*

2. MCPR for 8x8 fuel = 1.29

3. MCPR for 8x8R fuel = 1.22 and

4. MCPR for P8x8R fuel = 1.25 1

BRUNSWICK - UNIT 2 3/4 2-11 Amendment No.

c

2. EOC minus 2000 MMD/t to EOC, within one hour determine that MCPR, as a function of core flow, is equal to or greater than the MCPR limit times the Kg shown in Figure 3.2.3-1 with:

a. If ODYN OPTION A analyses are in effect, the MCPR limits are listed below:

1. MCPR for 7x7 fuel - 1.29*

2. MCPR for 8x8 fuel = 1.36

3. MCPR for 8x8R fuel = 1.37 and

4. MCPR for P8x8R fuel = 1.40

b. If ODYN OPTION B analyses are in effect (refer to specification 3.2.3.2), the MCPR limits are listed below:

1. MCPR for 7x7 fuel = 1.20*

2. MCPR for 8x8 fuel = 1.29,

3. MCPR for 8x8R fuel = 1.25 and,

4. MCPR for P8x8R fuel = 1.28

b. With MCPR, as a function of core flow, less than the applicable limit determined from Figure 3.2.3-1 initiate corrective action within 15 minutes and restore MCPR to within the applicable limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to less than 25% 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 4.2.3.1 MCPR, as a function of core flow, shall be determined to be equal to or greater than the applicable limit determined from Figure 3.2.3-1:

A. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , B. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and C. Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating in a LIMITING CONTROL ROD PATTERN for MCPR.

For 7x7 fuel assemblies, the K gf actor is based on the 112% flow curve of Figure 3.2.3-1 rather than the actual setpoint of 102.5%.

BRUNSWICK - UNIT 2 3/4 2-11A Amendment No.

r i 1

POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO (ODYN OPTION B)

LIMITING CONDITION FOR OfERATION 3.2.3.2 For the OPTION B MCPR limits listed in specification 3.2.3.1 to be used, the cyclo average 20% scram time (r,y,) shall be less than or equal to the Option B scram time limit (r ),gwhere r,y, and T are determined as B

follows:

I T = , where:

[ i 1-1 ,

1 = Surveillance test number, n - Number of surveillance tests performed to date in the cycle (including BOC),

Ng = Number of rods tested in the i ch surveillance test, and rg = Average scram time to notch 36 for surveillance test i N 1/2 T

B =u+1.65(n ) (a),wh'ere:

[ "i i=1 i = Surveillance test number n - Number of surveillance tests performed to date in the cycle (including BOC),

Ng = Number of rods tested in the i Ch surveillance test Ni = Number of rods tested at BOC, p = 0.834 seconds (mean value for statistical scram time distribution from de-energization of scram pilot valve solenoid to pickup on notch 36),

o = 0.059 seconds (standard deviation of the above statistical distribution).

APPLICABILITY: CONDITION 1, when THERMAL POWER 1 25% RATED THERMAL POWER.

ACTION:

Within twelve hours after determining that i > T B, the operating limit MCPRs shall be either:

a. Adjusted for each fuel type such that the operating limit MCPR is the maximum of the non pressurization transient MCPR operating limit (f rom Table 3.2.3.2-1) or the adjusted pressurization transient MCPR operating limits, where the adjustment is made by:

T ave TB adjusted " option B + T ~

T ption A ~ option B A B BRUNSWICK - UNIT 2 3/4 2-12 Amendment No.

where: tg= 0.900 seconds, control rod average scram insertion time limit to notch (36) per Specification 3.1.3.3, MCPRoption A = Determined f rom Table 3.2.3.2-1, HCPRoption B = Determined from Table 3.2.3.2-1, or,

b. The OPTION A MCPR limits listed in Specification 3.2.3.1.

SURVEILLANCE REQUIREENTS 4.2.3.2 The values of i and i shall be determined and compared each time a scram time test is perf8E$ed. The requirement for the frequency of scram time testing shall be identical to Specification 4.1.3.2.

N BRUNSWICK - UNIT 2 3/4 2-12A Amendment No.

,, TABLE 3.2.3.2-1

o E

v2 TRANSIENT OPERATING LIMIT MCPR VALUES C

E 7:

, TRANSIENT FUEL TYPE

c. 7x7 8x8 8x8R P8x8R H

N NONPRESSURIZATION TRANSIENTS With RPT operable (op.) 1.20 1.29 1.21 1.22 With RPT inoperable (inop.) 1.20 1.29 1.22 1.25 TURBINE TRIP / LOAD REJECT WITiiOUT BYPASS t'

MCPR A MCPR g MCPR A MCPR g MCPR g MCPR B HCPRA MCPR g RPT (op.) 1.21 1.13 1.25 1.17 1.26 1.18 1.27 1.19 RPT (inop.) BOC + EOC - 2000 1.19 1.10 1.24 1.10 1.25 1.10 1.26 1.10 RPT (inop.) EOC - 2000 + EOC 1.29 1.19 1.36 1.24 1.37 1.25 1.40 1.28 FEEDWATER CONTROL FAILURE PCPR MCPR B HCPRA MCPR B MCPR A MCPR B UEN A HCPR B A

h- RPT (op.) 1.16 1.13 1.17 1.14 1.17 1.14 1.18 1.15 E

" RPT (inop.) BOC + EOC - 2000 1.17 1.11 1.18 1.12 1.18 1.12 1.18 1.12 RPT (inop.) EOC - 2000 + EOC 1.17 1.11 1.18 1.12 1.18 1.12 1.19 1.13

1

. TABLE 3.3.4-2

@ CONTROL ROD WITilDRAWAL BLOCK INSTRUMEP(TATION SETPOINTS 7:

TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWABLE VALUE

l. APRM (CSI-APRM-Cll.A,B,C,D,E,F)

E Q a. Upscale (Flow-Biased) < (0.66 W + 42%) T* j[ (0.66 W + 42%) T*

ro b. Inoperative _NA MTPF NA MTPF

c. Downscale > 3/125 of full scale > 3/125 of full scale

d. Upscale (Fixed) < 12% of RATED TifERMAL POWER < 12% of RATED Ti!ERMAL POWER

2. ROD BLOCK HONITOR (CSI-RBM-CH.A,B)

a. Upscale < (0.66 W + 39%) T* < (0.66 W + 39%) T*

b. Inoperative NA MTPF NA MTPF

c. Downscale > 3/125 of full scale > 3/125 of full scale

3. SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D) ti a. Detector not full in NA NA

b. Upscale < 1 x 105 cps

_ j(1 x 105 cps Y c. Inoperative NA NA C d. Downscale > 3 cps

_ > 3 cps

4. INTERMEDIATE RANGE MONITORS (C51-IRM-K601A,B,C,D,E,F,G.II)

a. Detector not full in NA NA

b. Upscale < 108/125 of full scale < 108/125 of full scale

c. Inoperative NA NA

d. Downscale _ 3/125 of full scale

_> 3/125 of full scale a

@- *T = 2.60 for 7 x 7 fuel.

$ T = 2.43 for 8 x 8 fuel.

T = 2.39 for 8 x 8R fuel.

p T = 2.39 for P8 x 8R fuel. .

L ___ _ _ _ . _ . _ _ - _ _ _ _ _ _ _ - - - - -

SPECIAL TEST EXCEPTIONS 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS LIMITING CONDITION FOR OPERATION 3.10.3 The requirements of Specifications 3.9.1, and 3.9.3, and Table 1.2 may be suspended to permit the reactor mode switch to be locked in the Start-up position and to allow two control rods to be withdrawn for shutdown margin demonstrations provided at least the following requirements are satisfied:

e. The source range monitors are OPERABLE with the RPS circuitry shorting links removed per Specification 3.9.2,

b. The rod worth minimizer is OPERABLE per Specification 3.1.4.1 and is programmed for the shutdown margin demonstration, and

c. The " notch-override" control shall not be used during movement of the control rods.

APPLICABILITY: CONDITION 5, during shutdown margin demonstrations.

ACTION:

With the requirements of the above specification not satisfied, immediately restore the reactor mode switch to the Refuel position.

SURVEILLANCE REQUIREMENTS 4.10.3 Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the performance of a shutdown margin l demonstration verify that:

a. The source range monitors are OPERABLE per dpecification 3.9.2, and

b. The rod worth minimizer is OPERABLE with the required program, per Specification 3.1.4.1.

BRUNSWICK - UNIT 2 3/4 10-3 Amendment No.

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 APRM SETPOINTS The fuel cladding integrity safety limits of Specification 2.1 were based on a TOTAL PEAKING FACTOR of 2.60 for 7 x 7 fuel, 2.43 for 8 x 8 fuel, 2.39 for 8 x 8R fuel and 2.39 for P8 x 8R fuel. The scram setting and rod block functions of the APRM instruments must be adjusted to ensure that the MCPR does not become less than 1.0 in the degraded situation. The scram settings and rod block settings are adjusted in accordance with the formula in this specification when the combination of THERMAL PORER and peak flux indicates a COTAL PEAKING FACTOR greater than 2.60 for 7 x 7 fuel, 2.43 for 8 x 8 fuel, 2.39 for 8 x 8R and 2.39 for F8 x 8R fuel. This adjustment may be accomplished by increasing the APRM gain and thus reducing the slope and intercept point of the flow referenced APRM high flux scram curve by the reciptocal of the APRM gain change. The method used to determine the design TPF shall be consistsat with the method used to determine the MIPF.

3/4.2.3 MINIMUM CRITICAL POWER RATIO The required operating limit MCPRs at steady state operating conditions as specified in Specification 3.2.3 are derived f rom the established fuel cladding integrity Safe operationaltransients.g{)LimitMCPRof1.07,andananalysisofabnormal For any abnormal operating transient analysis evaluation with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time during the transient, assuming an instrument trip setting as given in Specification 2.2.1.

To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO (CPR). The type of transients evaluated were loss of flow, increase in pressure and power, positive reactivity insertion, and coolant temperature decrease.

The limiting transient which determines the required steady state MCPR limit is the turbine trip with failure of the turbine bypass. This transient yields the largest A MCPR. When added to the Safety Limit MCPR of 1.07 the required minimum operating limit MCPR of Specification 3.2.3 is obtained. Prior to the analysis of abnormal operational transients an initial fuel bundle MCPR was dete rmined . This parameter is based on the bundle flow calculated by a GE multichannel of NED0-20360 ggadystateflowdistributionmodelasdescribedinSection4.4 and on core parametars shown in Reference 3, response to Items 2 and 9.

BRUNSWICK - UNIT 2 B 3/4 2-3 Amendment No.

ML20053C164

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