Text

Proposed Tech Specs,Incorporating Revised Min Critical Power Ratio Values & Revised MAPLHGR Values for New BP8DRB299 Fuel Type
	ML20092N834
Person / Time
Site:	Brunswick
Issue date:	06/26/1984
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20092N825	List: ML20092N824; ML20092N834; ML20092N840;
References
	84TSB15, NLS-84-274, NUDOCS 8407050105
	Download: ML20092N834 (17)
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, ENCLOSURE 1 1 i

SERIAL NO.: NLS-84-274 ;

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. BRUNSWICK STEAM ELECTRIC PLANA PROPOSED TECHNICAL SPECIFICATION PAGES - UNIT 2

- REFERENCE NUMEER 84TSB15 ,

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l 0 5000 10000 15000 20000 25000 40000 30000 35000 AVERAGE PLANAR EXPOSURE (mwd /t)

FUEL TYPE 8DB274L _(8X8) l MAXIMt.N AVERAGE PLANAR LINEAR HEAT -

g GENERATION RATE (MAPLHGR)

-i VERSUS AVERAGE PLANAR EXPOSURE 5

e-FIGURE 3.2.1-1 '

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N g FUEL TYPE 8DRB265H (8X8R) g MAXIMtN AVERAGE PLANAR LINEAR HEAT -

g GENERATION RATE (MAPUlGR)

-l VERSUS AVERAGE PLANAR EXPOSURE 5

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FUEL TYPE 8DRB283 (8X8R)

MAXIMLN AVERAGE PLANAR LINEAR HEAT -

p GENERATION RATE (MAPIM R) 4 VERSUS AVERAGE PIR4AR EXPOSURE 5

FIGURE 3.2.1-3 i

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I o VERSUS AVERAGE PLANAR EXPOSURE I E l z

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I 9 i FIGURE 3.2.1-6 l

_ _ - , . _ - _ , . , , _ . -_ ,_ - - - - . . . - - . . _ _ _ _ - . - . . . .__..,m___ . . _ . . . __ ,, . . . , , , _ . . . _ , _ _ . _ - . . . _ _ . _ _ . . _ _ _ _ _ _ . _ _ . _ _ _ _ _ - _ _ _ _ , ___ _

(BSEP-2-35)

POWER DISTRIBUTION LIMITS i

3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The flow-biased APRM scram trip setpoint (S) and roc block trip set point (SRB) shall be established according to the following relationship:

l S;$ (0.66W + 54%) T SRB d- (0.66W + 42%) T l where: S and S RB are in percent of RATED THERMAL POWER.

l W = Loop recirculation flow in percent of rated flow, T = Lowest value of the ratio of design TPF divided 7y the MTPF obtained for any class of fuel in the core (T j:_ l.0). and Design TPF for: 8 x 8 fuel = 2.43 8 x 8R fuel = 2.39 P8 x 8R fuel = 2.39 BP8 x 8R fuel = 2.39 APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POJER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION:

With S or S RB exceeding the allowable value, initiate corrective action within !

15 minutes and continue corrective action so that S and SRB are within the required limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to Iess 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 4.2.2 The MTPF for each class of fuel shall be determined, the value of T calculated, and the flow biased APRM trip setpoint adjusted, as required: i

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 j least 15% of RATED TRERMAL 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 l operating with a LIMITING CONTROL ROD PATTERN for MTPF.

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BRUNSWICK - UNIT 2 3/4 2-8 Amendment No. L l

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. (BSEP-2-35)

POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION POR 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 with the following MCPR limit adjustments:

a. Beginning-of-cycle (BOC) to end-of-cycle (EOC) minus 2000 NWD/t with ODYN OPTION A analyses in effect and the end-of-cycle recirculation pump trip system inoperable, the MCPR limits are listed below:

1. MCPR for 8 x 8 fuel - 1.25

2. MCPR for 8 x 8R fuel = 1.26

3. MCPR for P8 x 8R fuel = 1.28

4. MCPR for BP8 x 8R fuel = 1.28

b. E0C minus 2000 MWD /t to EOC with ODYN OPTION A analyses in effect and g the end-of-cycle recirculation pump trip system inoperable, the MCPR limits are listed below: ,

1. MCPR for 8 x 8 fuel = 1.36

2. MCPR for 8 x 8R fuel = 1.37

3. MCPR for P8 x 8R fuel = 1.40 i 4. MCPR for BP8 x 8R fuel = 1.40

c. BOC to EOC minus 2000 MWD /t with ODYN OPTION B analyses in effect and the end-of-cycle recirculation pump trip system inoperable, the MCPR limits are listed below:

1. MCPR for 8 x 8. fuel = 1.23

2. MCPR for,8 x 8R fuel = 1.24

3. MCPR for P8 x 8R fuel = 1.24

4. MCPR for BP8 x 8R fuel = 1.24 EOC minus 2000 MWD /t to EOC with ODYN OPTION B analyses in effect and d.

the end-of-cycle recirculation pump trip system inoperable, the MCPR limits are listed below:

1. MCPR for 8 x 8 fuel = 1.24

2. MCPR for 8 x 8R fuel = 1.25

3. MCPR for P8 x 8R fuel = 1.28

4. .MCPR for BP8 x 8R fuel = 1.28

. ' APPLICABILITY: OPERATIONAL CONDITION 1 when THERMAL POWER is greater than i or equal to 25% RATED THERMAL POWER BRUNSWICK - UNIT 2 3/4 2-9 Amendment No.

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Y (BSEP-2-35)

POWER DISTRIBUTION LIMITS i L

LIMITING CONDITION FOR OPERATION (Continued)

. l ACTIOM:

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 . i SURVEILLANCE REQUIREMENTS I

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4.2.3.1 MCPR, as a function of core flow, shall be determined to be equal to I 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 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 reutor is operating in a LIMITING CONTROL ROD PATTERN for MCPR. '

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t i BRUNSWICK - UNIT 2 3/4 2-10 Amendment No. !

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1 (BSEP-2-35) .

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ca TABLE 3.2.3.2-1 E

TRANSIENT OPERATING LIMIT MCPR VALUES S

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TRANSIENT FUEL TYPE g 8x8 8x8R PSx8R BP8 x 8R E

NONPRESSURIZATION TRANSIENTS FOC + EOC 1.23 1.24 1.24 1.24 TUREINE TRIP / LOAD REJECT WITHOUT BYPASS MCPRA MCPR B R R R MCPR A B A B A B w BOC + EOC - 2000 1.25 1.08 1.26 1.08 1.28 1.09 1.28 1.09 b

EOC - 2000 + EOC 1.36 1.24 1.37 1.25 1.40 1.28 1.40 1.28 FEEDWATER CONTROL FAILURE MCPRg MCPRB R MCPR MCPRA R MORA MCPR B A B B -

BOC + EOC - 2000 1.17 1.11 1.17 1.11 1.17 1.11 1.17 1.11 I EOC - 2000 + EOC 1.17 1.11 1.17 1.11 1.17 1.11 1.17 1.11 B

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.EF

, (BSEP-2-3 5 )

POWER DISTRIBUTION LIMITS 3/4.2.4 LINEAR HEAT GENERATION RATE LIMITING CONDITION POR OPERATION 3.2.4 The LINEAR HEAT GENERATION RATE (LHCR) shall not exceed 13.4 kw/ft for 4

8 X 8, 8 X 8R, P8 X 8R, and BP8 x 8R fuel assemblies.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION:

With the LHCR of any fuel rod exceeding the above limit, initiate corrective action within 15 minutes and continue corrective action so that the LHGR 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 .

i SURVEILLANCE REQUIREMENTS

'4.2.4 LHCRs shall be determined to be equal to or less than the limit:

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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 on a LIMITING CONTROL ROD PATTERN for LHCR.

i BRUNSWICK - UNIT 2 3/4 2-15 Amendment No.

v (BSEP-2-35)

E TABLE 3.3.4-2 -

E E CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS

M TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWABLE VALUE 3

E 1. APRM (CSI-APRM-CH. A,B,C.D.E.F) y a. Upscale (Flow Biased) < (0.66W + 42%) T* T*

u 1 (0.66W + 42%)

MTPF MTPF

b. Inoperative NA NA

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

d. Upscale (Fixed) [12%ofRATEDTHERMALPOWER [12%ofRATEDTHERMALPOWER

2. ROD BLOCK MONITOR (CSI-RSM-CH.A,B)

a. Upscale < (0.66W + 39%) T* < (0.66W + 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) w a. Detector not full in NA NA L b. Upscale i 1 x 105 cps i 1 x 105 cps

c. Inoperative NA NA

d. Downscale > 3 cps > 3 cps

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

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 -

5. SCRAM DISCHARGE VOLUME (C12-LSH-N013E)

$ a. Water Level High 1 73 gallons 1 73 gallons

E V '

$ T=2.43 for 8 x 8 fuel.

T=2.39 for 8 x 8R fuel.

I T=2.39 for P8 x 8R fuel.

T=2.39 for BP8 x 8R fuel.

(BSEP-2-35) 1 INSTRUMENTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels shown in Tcble 3.3.6.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.6.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.*

l ACTION:

a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values Column of Table 3.3.6.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within one hour.

c. With the number of OPERABLE channels two or more less thaa required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

1. If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within one hour.

2. If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip system inoperable.

d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or take the ACTION required by Specification 3.2.3.

e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or take the ACTION required by Specification 3.2.3.

During Cycle 6 operation, the end-of-cycle recirculation pump trip (EOC-RPT) system will be inoperable (manually bypassed); therefore, Specification 3.3.6.2 above does not apply. The provisions of Specification 3.0.4 are not applicable.

BRUNSWICK - UNIT 2 3/4 3-82 Amendment No.

. (BSEP-2-35)

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 2.43 for 8 x 8 fuel and 2.39 for 8 x 8R, P8 x 8R, and BP8 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 POWER and peak flux indicates a TOTAL PEAKING FACTOR greater than 2.43 for 8 x 8 fuel and 2.39 for 8 x 8R, P8 x 8R, and BP8 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 reciprocal of the APRM gain change. The method used to determine the design TPF shall be consistent with the method used to determine the MTPF.

3/4.2.3 = MINIMUM CRITICAL POWER RATIO The required ope. rating limit MCPRs at steady state operating conditions as specified in Specification 3.2.3 are derived from the established fuel cladding integrity Safe Limit MCPR of 1.07, and an analysis of abnormal operational transients. 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 end power, positive reactivity insertion, and

. coolant temperature decrease.

Unless otherwise stated in cycle specific reload analyses, the limiting transient which determines the required steady state MCPR limit is the turbine- l 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 determined.. This parameter is based on the bundle flow calculated by a GE multichannel.gadystateflowdistributionmodelasdescribedinSection4.4 of NEDO-20360 and on core parameters shown in Reference 3, response to Items 2 and 9. ,

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

L

~ ' * * * -

(BSEP-2-35) 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.

SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1. For the purpose of effluent release calculations, the boundary for atmospheric releases is the SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The PRIMARY CONTAINMENT is a steel-lined, reinforced concrete structure composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete, steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum free air volume of 288,000 cubic feet.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

a. Maximum internal pressure 62 psig.

j b. Maximum internal temperature: drywell 300*F Suppression chamber 200*F

{

! c. Maximum external pressure 2 psig.

f

! 5.3 REACTOR CORE l FUEL ASSEMBLIES l

i 5.3.1 The reactor core shall contain 560 fuel assemblies. The 8 x 8 fuel assemblies contain 63 fuel rods and the 8 x 8R, P8 x 8R, EP8 x 8R fuel l assemblies contain 62 fuel rods. All fuel rods shall be clad with Zircaloy 2. The nominal active fuel length of each fuel rod shall be 146 inches for 8 x 8 fuel assemblies and 150 inches for 8 x 8R, P8 x 8R, and I

l BRUNSWICK - UNIT 2 5-1 Amendment No.

L

(BSEP-2-35)

. .- . ~ . -

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES (Continued)

BP8 x 8R fuel assemblics. The initial core loading shall have a maximum y enrichment of 2.47 weight percent U-235. Reload fuel shall be similar in f ' physical design to the initial core loading and shall have a maximum enrichment of 2.99 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 137 control rod assemblies, each consisting of a cruciform array of stainless steel tubes containing 143 inches of boron carbide, B 4C, powder surrounded by a cruciform-shaped stainless steel l sheath.

5.4 -REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The- nuclear boiler and reactor recirculation system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 4.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 1250 psig, and

c. For a temperature of 5750F.

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and

, recirculation system is approximately 18,670 cubic feet.

5.5 METEOROLOGICAL TOWER LOCATION f 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.

b f

e l-l l

i i BRUNSWICK - UNIT 2 5-4 Amendment No.

I 2-

ML20092N834

Text

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