Text

Proposed Changes to Tech Specs,Providing Cycle 3 Specific Operating Limit MAPLHGR & Max Critical Power Ratio Values, & Limiting Trip Setpoint of Rod Block Monitor Not to Exceed 107% Power.Changes Necessary to Support Startup
	ML20042A878
Person / Time
Site:	Hatch
Issue date:	03/11/1982
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20042A874	List: ML20042A873; ML20042A878; ML20042A882;
References
	TAC-48110, NUDOCS 8203240228
	Download: ML20042A878 (6)
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t ATTACHENT 1 NRC DOCKET 50-366 i OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS i Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the

! attached proposed amendment to Operating License tPF-5 and has determined that:

a. The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license;

b. The proposed amendment does not contain several complex issues, does not involve ACRS review, and does not require an environmental impact statement;

c. The proposed amendment does not involve a complex issue, an environmental issue or more than one safety issue;

d. The proposed amendment does involve a single safety issue, namely, the changing of operating Power Distribution Limits for the reconfigured cycle 3 core including the new fuel type; e) The proposed change is therefore a Class II amendment.

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ATTACFfEtiT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN 1. HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGE TO TECHNICAL SPECIFICATI0ftS The proposed change to Technical Specifications (Appendix A to Operating License NPF-5 would be incorporated as follows:

Remove Page Insert Page 3/4 2-1 3/4 2-1 3/4 2-48 3/4 2-7a 3/4 2-7a B 3/4 2-1 B 3/4 2-1 3/4 3-40 3/4 3-40

'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) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, or 3.2.1-5.

APPLICABILITY: CONDITION 1, when THERMAL POWER 3,25% of RATED THERMAL POWER.

ACTION:

With an APLHGR exceeding the limits of Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, or 3.2.1-5, initiate corrective action within 15 minutes and continue corrective action so that APLHGR is within the 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 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 AFLHGRs 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, or 3.2.1-5:

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 R0D PATTERN for APLHGR.

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

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.o AVERAGE PLANAR EXPOSURE (Mwd /st)

FUEL TYPE P8DRB263 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR)

VERSUS AVERAGE PLANAR EXPOSURE FIGURE 3.2.1-5

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MCPR LIMIT FOR 8X8R FUEL AT RATED FLOW FIGURE 3.2.3-1 1.36 ..___..

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MCPR LIMIT FOR P8X8R FUEL AT RATED FLOW FIGURE 3.2.3-2 l 11atch Unit 2 3/4 2-7a Amendment No.

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 22000 F limit specified in the Final Acceptance Criteria (FAC) issued in June 1971 considering the postulated effects of fuel pellet densification.

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE This specification assures that the peak cladding temperature follow-ing the postulated design basis loss-of-coolant accident will not exceed the limit specified in 10 CFR 50, Appendix K.

The peak gladding temperature (PCT) following a postulated loss-of-coolant accident is crimarily 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 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 dependent steady state gap conductance and rod-to-rod local peaking factor. The Technical Specification APLHGR is this LHGR of the highest powered rod divided by its local peaking factor.

The limiting value for APLHGR is shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3,

3. 2.1-4, a nd 3. 2.1-5.

The calculational procedure used to establish the APLHGR shown on Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, and 3.2.1-5, is based on a loss-of-coolant accident analysis. The analysis was performed msing 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. Differences in this analysis compared to previous analyses performed with Refe,rence 1 are: (1) the analysis assumes a fuel : .onoly planar power consistent with 102% of the MAPLHGR shown in Figures 3.2.1-1, 3.2.1-2, 3.2.1-3, 3.2.1-4, and 3.2.1-5; (2) fission product decay is computed assuming an energy release rate of 200 MEV/ fission; (3) pool boiling is assumed after nucleate boiling is lost during the flow stagnation period; and (4) the effects of core spray entrainment and counter-current flow limitation as described in Reference 2, are included in the reflooding calculations.

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.

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HATCH - UP.2T 2 B 3/4 2-1 Amendment No.

TABLE 3.3.5-2 .

CONTROL ROD WITHDRAHAL DLOCK INSTRUMErlTATION SETPOINTS ,

y .

b! _T_R_I_P__S_E_T_ POI NT ALLOHARLE VALUE TRIP F_U_t.lCTION -

si 1. APRM n

n, a. Flow Referenced. Simulated I Thermal Power - tipscale < (0.66 W + 427)* < (0.66 W + 42%)*-

b. Innpera t ive liA RA '

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

d. ticutron flux - liigh.12% 3 12/125 of full scale 3 12/125 of full scale

2. ROD BLOCK 110filTOR

a. Upscale < (0.66W + 41%)Not to exceed 107% < (0.66 W + 41%)

b. Inopera tive MA EA

c. Downscale 3.3/125 of full scale 3,3/125 of full scale w

1: 3. . 50tlRCE RANGE MONITORS w

I- a. Octector not full in flA NA

b. Upscale < 1 x 10$ cps < 1 x 10 cps Inopera tive NA flA c.

d. Downscale 2,3 ces 2,3 cps

4. IrlTE_RMEDIATE RANGE M0tilTOR_S_

ga a. Detector not full in NA NA .

m b. lipscale *

, < 100/125 or full scale < 106/125 of full scale Inoperative EA E c. EA

= d. Downscale > 5/125 of full scale > 5/125 of full scale -

5. SCRAM DISCllARrE VOLUME ,

a. Water level-High < 36.2 gallons < 36.2 gallons

The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow (W). The trip setting of this function must Ie maintained in accordance with Specification 3.2.2. ~

ML20042A878

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