ML20247J138

Corrected Amend 20 to License NPF-58,correcting Typos

ML20247J138
Person / Time
Site:	Perry
Issue date:	05/18/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247J145	List: ML20247J138 ML20247J153
References
NUDOCS 8906010053
Download: ML20247J138 (4)

Text

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POWER DISTRIBUTION LIMITS 3/4.2 POWER DISTRIBUTION LIMITS I

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 All AVERAGE PLANAR LINEAR HEAT GENEPATION RATES (APLHGRs) shall not exceed the result obtained from multiplying the applicable MAPLHGR values

• by the smaller of either the flow dependent MAPLHGR factor (MAPFAC ) of Figure 3.2.1-1 f

or the power dependent MAPLHGR factor (MAPFAC ) of Figure 3.2.1-2.

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

ACTION:

If at any time during operation it is determined that an APLHGR is exceeding the result of the above multiplication, initiate corrective action within 15 minutes and restore APLHGR to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the above limits:

i a.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER in one hour,:andi c.

Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL R0D PATTERN for APLHGR.

d.

The provisions of Specification 4.0.4 are not applicable.

l

[

• These applicable MAPLHGR values are:

1) Those that have been approved for the respective fuel and lattice type as a function of the average planar exposure (as determined -by the NRC approved methodology described in GESTAR-II)

I or l

2) When hand calculations are required, the MAPLHGR as a function of the l

average planar exposure for the most limiting lattice (excluding natural uranium) shown in the Figures 3. 2.1-3, 3. 2.1-4, 3. 2.1-5, and 3. 2.1-6 for the applicable type of fuel.

PERRY - UNIT 1 3/4 2-1 Amendment No. 20 1

8906010053 890518 l

PDR ADOCK 05000440 P

PDC

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20 40 60 80 100 120 CORE FLOW (% "s 1TED), F FLOW DEPENDENT MAPLHGR FACTOR (MAPFAC )

f FIGURE 3.2.1-1 PERRY - UNIT 1 3/42-2 Amendment flo. 20

3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section assure that the peak cladding temper-ature following the postulated design basis loss-of-coolant accident will not exceed the.2200 F limit specified in 10 CFR 50.46.

i 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE l

This specification assures that the peak cladding temperature (PCT) following the postulated design basis Loss-of-Coolant Accident (LOCA) will not exceed the limits specified in 10 CFR 50.46 and that the fuel design analysis limits specified in GESTAR-II (Reference 1) will not be exceeded.

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 dependent only secondarily on the rod to rod power distribution within an assembly. The peak

. clad temperature is calculated assuming a 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 depen-dent steady state gap conductance and rod-to-rod local peaking factor. The Technical Specification AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) is this LHGR of the highest powered rod divided by its local peaking factor.

The MAPLHGR limits of Figures 3.2.1-1, 3.2.1-2, and 3.2.1-3 are multiplied by the smaller of either the flow dependent MAPLHGR factor (MAPFAC ) or the power f

dependent MAPLHGR factor (MAPFAC ) corresponding to existing core flow and p

power state to assure the adherence to fuel mechanicalidesicjn bases during the most limiting transient. MAPFAC 's are determined using the three-f dimensional BWR simulator code to analyze slow flow runout transients.

MAPFAC 's are generated using the same data base as the MCPR to protect the p

p core from plant transients other than core flow increases.

The Technical Specification MAPLHGR value is the most limiting composite of the fuel mechanical design analysis MAPLHGR and the ECCS MAPLHGR.

Fuel Mechanical Design Analysis:

NRC approved methods (specified in Reference 1) are used to demonstrate that all fuel rods in a lattice, operating at the bounding power history, meet the fuel design limits specified in Reference 1.

This bounding power history is used as the basis for the fuel design analysis MAPLHGR value.

LOCA Analysis: A LOCA analysis is performed in accordance with 10 CFR Part 50 Appendix K to demonstrate that the MAPLHGR values comply with the ECCS limits specified in 10 CFR 50.46.

The analysis is performed for the most limiting break size, break location, and single failure combination for the plant.

PERRY - UNIT 1 B 3/4 2-1 Amendment No. 20 i

L L

POWER DISTRIBUTION LIMITS l

BASES AVERAGE PLANAR LINEAR HEAT GENERATION RATE (Continued)

Only the most limiting MAPLHGR values are shown in the Technical Specifi-cation figures for multiple lattice fuel. When hand calculations are required, these Technical Specification MAPLHGR figure values for that fuel type are used for all lattices in that bundle.

For some GE fuel bundle designs MAPLHGR depends only on bundle type and burnup.

Other GE fuel bundles have MAPLHGRs that vary axially depending upon the specific combination of enriched uranium and gadolinia that comprises.a fuel bundle cross section at a particular axial node.

Each particular combination of enriched uranium and gadolinia, for these fuel-bur.J1e types, is called a lattice type by GE.

These particular fuel bundle types have MAPLHGRs that vary by lattice type (axially) as well as with fuel-burnup.

Approved MAPLHGR values (limiting values of APLHGR) as a function of fuel 'rx! lattice types, and as a function of t.1e average planar exposure are proviaed in Technical Specification Figures 3.2.1-3 through 3.2.1-6.

PERRY - UNIT 1 B 3/4 2-2 Amendment No. 20

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