Text

Corrected Tech Spec Pages from Amends 141 & 77 to Licenses DPR-57 & NPF-5,modified to Correct Typos &/Or Include Previously Issued Amends
	ML20236E256
Person / Time
Site:	Hatch
Issue date:	07/24/1987
From:	; NRC
To:	;
Shared Package
ML20236D321	List: ML20236D318; ML20236E256;
References
	TAC-61900, TAC-61901, NUDOCS 8707310288
	Download: ML20236E256 (17)
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BASES FOR LIMITING SAFETY SYSTEM SETTINGS l 2.1 FUEL CLADDING INTEGRITY y ,, ,

The abnormal operational transients applicable to operation of the HNP-1 Unit have been analyzed throughout the spectrum of planned operating conditions.

The analyses were based upon plant operation in accordance with the operating map given in Figure 3-1 of Ref. 3. In addition, 2436 MWt is the licensed l maximum power level e f HNP-1, and this represents the maximum steady-state power which shall not knowingly be exceeded.

Transient analyses performed for each reload are given in Reference 1. Models and model conservatism are also described in this reference. As discussed in Reference 2, the core-wide transient analyses for single-loop operation are conservatively bounded by two-loop analyses. The flow dependent rod block and scram setpoint equations are adjusted for one-pump operation.

Steady-state operation without forced recirculation will.not be permitted, except during startup testing. The analysis to support operation at various I

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Ai HATCH - UNIT 1 1.1-10 Amendment No. 141 8707310288 870724 PDR P

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A LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6.J. Recirculation System 4.6.J. Recirculation System

1. Core thermal power shall not exceed 1. Recirculation pump speeds shall be l 0 1% of rated therma) power without recorded at least once per day.

W' forced recirculation.

< 2. With only one recirculation loop

2. Wher<ever the reactor is in the in operation, verify that the START & HOT STANDBY or RUN reactor operating conditions are modes, at least one outside the Operation Not Allowed recirculation loop shall be in Region in Figure 3.6-5: d operation.

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

3. The requirements applicable to single-loop operation as identified (b) Whenever thermal power has in Sections _1.1. A, 2.3. A, 3.1. A, been changed by at least 5% of )

3.2.G, 3.11.A, and 3.11.C shall be rated thermal power and steady-in effect following the removal of state conditions have been 9 one recirculation loo: from service, reached. l or the unit shall be placed in the j HOT SHUTOOWN condition within 12 J hours and in COLD S NTDOWN within i l the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4. With only one recir ulation loop ;

in operation and the unit in the Operation Not Allowed Region,

, specified in Figure 3.6-5, initiate I action within 15 minutes to place l the unit in the Operation Allowed l Region, identified in Figure 3.6-5, l within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Otherwise, place I

l the reactor in the HOT SHUTDOWN condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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5. Following one pump operation the j l discharge valve of the low speed l I pump may not be opened unless the speed cf the faster pump is less than 50% of its rated speed.

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1 HATCH - UNIT 1 3.6-9c Amendment No. 141

LIMITING CONDlilONS FOR OPERATION SURVEILLANCE RE0VIREMENTS 3.11. FUEL RODS 4.11. FUEL RODS Applicability Applicability The Limiting Conditions for Operation The Surveillance Requirements apply associated with the fuel rods apply to to the parameters which monitor the those parameters which monitor the fuel rod operating conditions.

fuel rod operating conditions.

Objective Objective The Objective of the Limiting Condi- The Objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type performance of the fuel rods. and frequency of surveillance to be applied to the fuel rods.

Specifications Specifications A. Av3 rage Planar Linear Heat Genera- A. Average Planar Linear Heat Genera-tion Rate (APLHGR) tion Rate (APLHGR)

During power operation, the APLHGF. The APLHGR for each type of fuel as for all core locations shall not a function of average planar I

exceed the appropriate APLHGR limit exposure shall be determined daily for those core locations. The APLHGR during reactor operation at 2 25%

limit, which is a function of average rated theretl power.

planar exposure and fuel type, is the appropriate value f rom Figure 3.11-1, sheets 1 through 6, multiplied by the smaller of the two MAPFAC f actors de-termined f rom Figure 3.11-1, sheets 7 and 8, For single-loop operation, the MAPFAC p is a constant value of 0.75 when power is greater than 52%

of rated thermal power. For power less than 52% of rated thermal power, the MAPFAC p is the same as the comparable two-loop value (Figure 3.11.1, sheet ?). If at any time i during operation it is determined l by normal surveillance that the limiting value for APLHGR is being exceeded, a: tion shall be initiated I

within 15 minutes to restore operation to within the prescribed limits.

l If the APLHGR is not returned to within the prescribed limits within two (2) hours, then reduce reactor power to less than 25% of rated thermal power within the next four (4) hours. B. Linear Heat Generation Rate (LHGR)

If the limiting condition for operation is restored prior to expiration of the The LHGR as function of core specified time interval, then further height shall be checked daily dur-progression to less than 25% of rated ing reactor operation at t 25%

l thermal power is not required. rated thermal power.

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HATCH - UNIT 1 3.11-1 Amendment No. 141 1

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LIMITING CONDIV10NS FOR OPERAlION SURVil~LIEdCE REOU!REMENTS B. Linear Heat Generation Rate (LHGR) B. Linear Heat (eneration Rate (LHGR)

During power operation, the LHGR as The LHGR as function of core a function of core height shall not height shall De checked daily dur-.

exceed the limiting value shmt'in ing reactor operation at > 25%

Figure 3.11-2 f or 7 x 7 fuel vi /the ' rated thermal power.

limiting value of 13.4 kw/f t f or any 8 x 8 fuel. If at any time dJring 1

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l HATCH - ilNIT 1 3.ll-la Araendment No. 141

LIMIVING CONDIVIONS FOR OPERATION SURVEILLANCE RE0VIREMEN15 3.11 B. sinear Heat Generation Rate (LHGR)

(Continued) rperation it is determined by normal surveillance that the limiting value for LHGR is being exceeded, action shall be initiateo within 15 minutes to restore operation to within the prescribed limits. If the LHGR is not returned to within the prescribed limits within two (2) hours, then reduce reactor power to less than 25% of rated thermal power within the next four (4) hours, if the limiting condition for operation is restored prior to expiration of the specified time interval, then further progression to less than 45%

of rated thermal power is not required.

C. Minimum Critical Power Ratio (MCPR) 4.11.C.1. Minimum Critical Power Ratio (MCPR)

MCPR shall be determined to be-The minimum for two-loop critical power operation ratio shall be (MCPR)l equal equal to or greater than the to or greater than the operating applicable limit, daily during limit MCPR (0LMCPR), which is a reactor power operation at 1 25%

function of scram time, core rated thermal power and folluwing power, and core flow. For 25% < any change in power level or dis-power < 30%, the OLMCPR is given in tribution that would cause opera-Figure 3.11.6. For power 1 30%, tion with a limiting control rod the OLMCPR is the greater of either: pattern as described in the bases for Specification 3.3.F.

1. The applicable limit determined from Figure 3.11.3, or 4.ll.C.2. Minimum Critical Power Ratio limit

2. The applicable limit from either Figures 3.11.4 or 3.11.5 The MCPR limit at rated flow and multiplied by the Kp factor rated power shall be determined for determined f rom Figure 3.11.6, each fuel type, as appropriate where t is the relative f rom figures 3.11.4 or 3.11.5, measured scram speed with respect using:

to Option A and Option B scram speeds. If x is determined to a. t=1.0 prior to initial scram .

be less than zero, then the time measurements for the !

OLMCPR is evaluated at t=0. cycle, performed in accordance with specifications 4.3.C.2.a.

or

b. t is determined from scram time measurements performed in accordance with specifica-tion 4.3.C.2.

The determination of the limit must be completed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the conclusion of each scram time surveillance test required by specification 4.3.C.2.

HATCH - UNIT 1 3.11-2 Amendment No. 141

. LIM 111NG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11.C. Minimum Critical Power Ratio (MCPR1 For sin'le-loop g operation, the MCPR limit is increased by 0.01 over the comparable two-loop value.

If at any time during operation it is determined by nornel surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the steady state MCPR is not returned to.within the prescribed limits within two (2) hours, then reduce reactor power to less than 25% of rated therwel power within the next four(4) hours. If the Limiting Condition for Operation is restored prior to expiration of I' the specified time interval, then I further progression to less than 25% of rated thermal power is not required.

D. Reoortina Requirements If any of the limiting values iden-tified in Specifications 3.11.A.,

B., or C. are exceeded, a Reportable Occurrence report shall be submitted.

If the corrective action is taken, as described, a thirty-day written report will meet the requirements of this specification.

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l HATCH - UNIT 1 3.11-2a Amendment No. 141

BASES FOR LIMITING CONDITIONS FOR OPER4'10N AND SURVEILLANCE REQUIREMENTS 3.11. FUEL RODS A. AveraQe Planar Linear Heat veneration Rate ( APLHGR)

This specification assures that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the limit specifi W in the 10 CFR 50, Appendix K, even considering the postulated effects of fuel pellet densification.

The peak cladding temperature following a postulated loss-of-coolant acci-dent is primarily a function of the average heat generation rate of all the

. rods of a fuel assembly at any axial location and is only dependent second- i arily on the rod to rod power distribution within an assembly. Since ex-pected local variations in power distribution within a fuel assembly effect the calculated peak clad temperature by less than 20'F relative to the peak temperature for a typical fuel design, the limit on the average linear heat generation rate is sufficient to assure that calculated temperatures conform to 10 CFR 50.46. The limiting value for APLHGR at rated conditions )

is shown in Figures 3.11-1, sheets 1 thru 6.

A flow dependent correction factor incorporated into Figure 3.11-1 (sheet 8) is 1 applied to the rated conditions APLHGR to assure that the 2200*F PCT limit is j complied with during LOCA initiated from less than rated core flow. In addition, other power and flow dependent corrections given in Figure 3.11-1 (sheets 7 and 8) are applied to the rated conditions APLHGR limits to assure that the fuel thermal-mechanical design criteria are met during abnormal transients initiated from off-rated conditions for two-loop and single-loop operations, References 2 and 8. For single-loop operation, a 0.75 multiplica- ,

tion factor to APLHGR limits for all fuel bundle types conservatively bounds j that required by Reference 2. .

The calculational procedure used to establish the APLHGR shown in Figures 3.11-1, sheets 1 thru 6, is based on a loss-of-coolant accident analysis.

The analysis was performed using General Electric (GE) calculational models which are consistent with the requirements of Appendix K to 10 CFR 50. A complete discussion of each code employed in the analysis is presented in Reference 1.

A list of the significant plant input parameters to the loss-of-coolant accident analysis is presented in Table 3-1 of NEDO-24086(*). Further discussion of the APLHGR bases is found in NEDC-30474-p(*).

For sin ARTS (*)gle-loop MAPLHGRS operation (SLO),

will define the the mostConditon Limiting restrictiveforofOperation.

the SLO and HATCH - UNIT 1 3.11-3 M* ** *

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- 3.11.C. Minimum Critical Power Qatio (MCPR) (Continued)

' According to figure 3.11.4 o7.3.11.5, the 100% power,100%. flow operatine limit MCPR (OLMCPR) depends on the average scram time, t, of the control rods, where:

t = 0 or ' ave 'B, whichever is greater t

g. - tB where: 'A =-1.096 sec (Specification 3.3.C.2.a. scram time limit .

to notch 36)

B = u + 1.65 "1 o (Reference 7 ) l.

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where: u = 0.822 sec (mean scram time used in the transient analysis) o = .018 sec (standard deviation of p)

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IN

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where: n = number of surveillance tests performed to date in the cycle j l

Ni = number of active control rods measured in the ith l surveillance test !

ti = average scram time to notch 36 of all rods in the ith surveillance test N3 = total number of active rods measured in 4.3.C.2.a The purpose of the MCPR f , and thep K of Figures 3.11-3 and 3.11-6, respectively, is to define operating limits at other than rated core flow and power conditions. At !

less than 100% of rated flow and power, the required MCPR is the larger value of the {

MCPRf and MCPRp at the existing core flow and power state. The MCPRys are established to protect the core from inadvertent core' flow increases such that the 99.9% MCPR limit requirement can be assured.

The MCPR f s were calculated such that for the maximum core flow rate and the corres-ponding THERMAL POWER along the 105% of rated steam flow control line, the limiting bundle's relative power was adjusted until the MCPR was slightly above the Safety Limit. Using this relative bundle power, the MCPRs were calculated at different points along the 105% of rated steam flow control line corresponding to different core flows. The calculated MCPk at a given point of core flow is defined as MCPRr, The core power dependent MCPR operating limit MCPR p is the power rated flow MCPR operating limit multiplied by the Kp f actor given in Figure 3.11- 6.

The Kp s are established to protect the core from transients other than core flow increases, including the localized event such as rod withdrawal error. The K sp were determined based upon the most limiting transient at the given core power level. (For further information on MCPR operating limits for off-rated conditions, reference NEDC-30474-P.(*))

When operating with a single-recirculation pump, the MCPR Safety and Operating Limits are increased by an u.vunt of 0.01 over the comparable values for two-recirculation pump operation.(8)

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3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 ALL AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be equal to or less than the applicable APLHGR limit, which is a function of fuel type and AVERAGE PLANAR EXPOSURE. The APLHGR limit is given by the applicable rated power, rated-flow limit taken from Figures 3.2.1-1 through 3.2.1-11, multiplied by the smaller of either:

a. The factor given by Figure 3.2.1-12, or

b. The factor given by Figure 3.2.1-13.

APPLICABILITY: CONDITION 1, when THERMAL POWER 2 25% of RATED THERMAL POWER.

ACTION:

With an APLHGR exceeding the applicable limits, initiate corrective action within l 15 minutes and continue corrective action so that the APLHGR meets 3.2.1 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 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 APLHGRs shall be verified to be equal to or less than the applicable 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. Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, 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 j operating with a LIMITING CONTROL R0D PATTERN for APLHGR. i HATCH - UNIT 2 3/4 2-1 Amendment No. 77

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POWER DIST.L oTION LIMITS 3/4.2.3 filNIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 4 3.2.3 ALL MINIMUM CRITICAL POWER RATIOS (MCPRs) for two-loop operation, l shall be equal to or greater than the MCPR operating limit (0LMCPR), which is a function of average scram time, core flow, and core power. For 25%

s Power < 30%, the OLMCPR is givon in Figure 3.2.3-4. For Power 2 30%,

the OLMCPR is the greater of either:

a. The applicable limit determined from Figure 3.2.3-3, or

b. The appropriate Kp given by Figure 3.2.3-4, multiplied by the appropriate limit from Figure 3.2.3-1 or 3.2.3-2,where:

t = 0 or ' ave 'B , whichever is greater, t

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A *B t A = 1.096 sec (Specification 3.1.3.3 scram time limit to notch 36),

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n N

} 4 i=1

n Nt 2 i i t,y,

= i=1 n

1 "i i=1 n= number of surveillance tests performed to date in cycle, Ng = number of active control rods measured in the i th surveillance test, t

4 = average scram time to notch 36 of all rods measured in the i th surveillance test, and Ng = total number of active rods measured in 4.1.3.2.a.

i For single-loop operation, the MCPR limit is increased by 0.01 over the comparable two-loop value.

APPLICABILITY: CONDITION 1, when THERMAL POWER 2 25% RATED THERMAL POWER HATCH - UNIT 2 3/4 2-6 Amendment No. 77-

3/4.2.3 MINIMUM CRITICAL POWER RATIO (CONTINUED)'

SURVEILLANCE REQUIREMENTS ACTION:

With MCPR ess than the. applicable limit determined from Specification 3.2.3.a or 3.2.3.b for two-loop or single-loop operation, initiate corrective l

. action within 15 minutes and continue corrective action so that MCPR is equal to or greater than the applicable limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than or equal to 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.2.3 The MCPR limit at rated flow and rated power shall be determined for i each type of fuel (8X8R, P8X8R, BP8X8R, and 7X7) from Figures 3.2.3-1 and 3.2.3-2 using:

a. t = 1.0 prior to the initial scram time measurements for the cycle performed in accordance with Specification 4.1.3.2.a, or

b. t as defined in Specification 3.2.3; the determination of the limit must be completed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the conclusion of each scram time surveillance test required by Specification 4.1.3.2.

MCPR shall be determined to be equal to or greater than the applicable limit:

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

b. Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, 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 R00 PATTERN for MCPR.

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HATCH - UNIT 2 3/4 2-7 Amendment No. 77

3/4.4 REACT 0f. COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM j RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.4.1.1 At least one recirculation loop of the reactor coolant system shall be in operation with its recirculation pump operating and the associated pump discharge valves OPERABLE, and

a. With only one recirculation loop in operation, the Functional Units 2.b of Table 2.2.1-1 and 1.a of Table 3.3.5-2, the limits on APLHGR in Section 3/4.2.1 and MCPR in Section 3/4.2.3 shall be in effect,

b. With only one recirculation loop in operation, the limit specified in Figure 3.4.1.1-1 shall be in effect.

APPLICABILITY: CONDITIONS 1* and 2*.

ACTION:

a. With no recirculation loops in operation, place the reactor mode switch in the SHUTDOWN position,

b. With requirements of Specification 3.4.1.1.a not met within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the removal of one recirculation loop from service, place the unit in the HOT SHUTDOWN condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and in COLD SHUTDOWN within the following'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. With only one recirculation loop in operation and the Unit in the Operation Not Allowed Region specified in Figure 3.4.1.1-1, initiate action within 15 minutes to place the Unit in the Operation Allowed Region in Figure 3.4.1.1-1 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Otherwise, place the reactor in the HOT SHUTDOWN condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l SURVEILLANCE REQUIREMENTS 4.4.1.1.1 Each pump discharge valve shall be demonstrated OPERABLE by cycling {

each valve through at least one complete cycle of full travel:

a. Each startup** prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER, and

b. During each COLD SHUTDOWN which exceeds 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .**

l

See Special Test Exception 3.10.4.

- If not performed within the previous 31 days.

HATCH - UNIT 2 3/4 4-l' Amendment No. 77 !

3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section assure that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the 2200 F limit specified in the Final Acceptance Criteria (FAC) issued in June 1971 considering the postulated effects of fuel pellet densification. These specifications also assure that fuel design margins are maintained during abnormal transients.

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE This specification assures that the peak cladding temperature following '

the postulated design basis loss-of-coolant accident will not exceed the limit specified in 10 CFR 50, Appendix K.

The peak cladding temperature (PCT) following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is depencent only )

i secondarily on the rod-to-rod power distribution within an assembly. The peak clad temperature is calculated assuming an LHGR for the highest powered rod which is equal to or less than the design LHGR corrected for densification. ,

This LHGR times 1.02 is used in the heatup code along with the exposure l dependent steady state gap conductance and rod-to-rod local peaking factor. l The Technical Specification APLHGR is this LHGR of the highest powered rod I divided by its local peaking factor. The limiting value for APLHGR is shown in the figures for in Technical Specification 3/4.2.1. For single-loop operation, Reference 1 requires a 0.75 multiplication factor to 8X8R and l P8X8R bundles.

The calculational procedure used to establish the APLHGR shown in the figures in Technical Specification 3/4.2.1 is based on a loss-of-coolant accident analysis. The analysis was performed using General Electric (GE) calculational models which are consistent with the requirements of Appendix K to 10 CFR 50. A complete discussion of each code employed in the analysis is presented in Reference 1.

A flow dependent correction factor incorporated into Figure 3.2.1-12 is applied to the rated conditions APLHGR to assure that the 2200 F PCT limit is complied with during a LOCA initiated from less than rated core flow. In addition, other power and flow dependent corrections given in Figures 3.2.1-12 and 3.2.1-13 are applied to the rated conditions to assure that the fuel thermal-mechanical design criteria are preserved during abnormal transients initiated from off-rated conditions.

A list of the significant plant input parameters to the loss-of-coolant accident analysis is presented in bases Table B 3.2.1-1. Further discussion of the APLHGR limits is given in Reference 2. l HATCH - UNIT 2 B 3/4 2-1 Amendment No. 77

l POWER DISTRIBUTION LIMITS j BASES MINIMUM CRITICAL POWER RATIO (Continued) i The purpose of the MCPR , and the K of Figures 3.2.3-3 and 3.2.3-4, ,

respectively is to define op rating limi&s at other than rated core flow and '

power conditions. At less than 100% of rated flow and power, the required MCPR is the larger value of the MCPRf and MCPR at the existing core flow and i

power state. The MCPRf s are es ablished Eo protect the core from inadvertent core flow increases suwh that the 99.9% MCPR limit requirement can be assured. {

The MCPR s were calculated such that for the maximum core flow rate and thecorresponbingTHERMALPOWERalongthe105%ofratedsteamflowcontrol l line, the limiting bundle's relative power was adjusted until the MCPR was '

slightly above the Safety Limit. Using this relative bundle power, the MCPRs were calculated at different points along the 105% of rated steam flow control I line corresponding to different core flows. The calculated MCPR at a given point of core flow is defined as MCPRf .

The core power dependent MCPR operating limit, MCPR , is the rated power and rated flow MCPR operating limit multiplied by the K Pfactor given in Figure 3.2.3-4 P

i The K s ar

, flowincreEses,eestablishedtoprotectthecorefromtransientsotherthancore including the localized event such as rod withdrawal error. The

(

l K s were determined based upon the most limiting transient at the given core power l level. For further information on MCPR operating limits for off-rated conditions. '

See Reference NEDC-30474-P. O I

l l

1 l

HATCH - UNIT 2 B 3/4 2-4 Amendment No. 77

v t e Letter Sequence Other
TAC:61900, (Open) TAC:61901, (Open)
Initiation Request, Request, Request Acceptance... Administration Questions Answers Results Approval... Other: ML20203H787, ML20206K007, ML20236D318, ML20236E256
MONTHYEAR1986-07-22 [Table View]

ML20236E256

Text

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