ML20237C163
| ML20237C163 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/15/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237C165 | List: |
| References | |
| NUDOCS 8712210089 | |
| Download: ML20237C163 (14) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 5
-l W ASHINGTON, D. C. 20555
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MISSISSIPPI POWER & LIGHT COMPANY.
SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 39 License No. NPF-29 i
1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by System Energy Resources, Inc.
(the licensee), dated October 9. 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is' reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
8712210009 871215}
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2.
Accordingly, the license is amended by changes to the Technical Specifications, as. indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Fecility Operating License No. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications g
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 39, are hereby incorporated into this license. System Energy Resources, Inc. shall operate the facility in accordance with the. Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects-I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: December 15, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines. The corresponding overleaf page(s) have been provided to maintain document completeness.
Remove Insert 1
3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2
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3/4 2-2a 3/4 2-2a I
3/4 2-2b 3/4 2-2b 3/4 2-2c 3/4 2-3 3/4 2-3 (overleaf) 3/4 2-3a 3/4 2-3b 3/4 2-4 3/4 2-4 (overleaf) l B 3/4 2-1 B 3/4 2-1 B 3/4 2-2 B 3/4 2-2 (overleaf) 1 lU_-__ --_-_.
l 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 During two loop operation 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-la, 3.2.1-lb, or 3.2.1-Ic as multiplied by the smaller of either the flow-dependent MAPLHGR factor (MAPFAC ) of Figure 3.2.1-2, or the power-dependent MAPLHGR factor f
(MAPFAC ) of Figure 3.2.1-3.
p During single loop operation, the APLHGR for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits as determined below:
a) for fuel type 8CR210 - the limit shown in Figure 3.2.1-1 l
as multiplied by the smaller of either MAPFAC, MAPFAC or 0.86; f
p and b) for the ANF fuel types the limit determined in "a" above for fuel type j
8CR210.
APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
During two loop operation or single loop operation, with an APLHGR exceeding the limits of Figures 3.2.1-1, 3.2.1-la, 3.2.1-lb, or 3.2.1-Ic as corrected by l
the appropriate multiplication factor for each type of fuel, 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 required limits:
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 /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LIMITING CONTROL ROD PATTERN for APLHGR.
d.
The provisions of Specification 4.0.4 are not applicable.
GRAND GULF-UNIT 1 3/4 2-1 Amendment No. 39
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l FIGURE 3.2.1-2 MAPFACf Amendment No. 39 l
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GRAND GULF-UNIT 1 3/4 2-3b Amendment No. 39 l
POWER DISTRIBUTION LIMITS 3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than both MCPR and MCPR limits at indicated core flow and THERMAL POWER as f
shown in Figures 3.2.3-1pand 3.2.3-2.
i APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
With MCPR less than the applicable MCPR limits determined from Figures 3.2.3-1 and 3.2.3-2, initiate corrective action within 15 minutes and restore MCPR 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 />.
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c.
SURVEILLANCE REQUIREMENTS l
4.2.3 MCPR shall be determined to be equal to or greater than the applicable MCPR limits determined from Figures 3.2.3-1 and 3.2.3-2:
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 /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and 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 c.
with a LIMITING CONTROL ROD PATTERN for MCPR.
d.
The provisions of Specification 4.0.4 are not applicable.
I GRAND GULF-UNIT 1 3/4 2-4
s 3/4.2 POWER DISTRIBUTION LIMITS BASES
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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.
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 50.46.
The peak cladding temperature (PCT) following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all l
the rods of a fuel assembly at any axial location and is dependent only secondar-ily on the rod to rod power distribution within an assembly. The peak clad ter-perature is calculated assuming a LHGR for the highest powered rod which is
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This LHGR equal to or less than the design LHGR corrected for densification.
times 1.02 is used in the heatup code along with the exposure dependent steady The Technical Speci-state gap conductance and rod-to-rod local peaking factor.
fication AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) is this LHGR of The Maximum Aver-the highest powered rod divided by its local peaking f actor.
age Planar Linear Heat Generation Rate (MAPLHGR) limits of Figures 3.2.1-1, 3.2.1-la, 3.2.1-lb, or 3.2.1-It are multiplied by the smaller of either the flow dependent MAPLHGR factor (MAPFAC ) or the power dependent MAPLHGR factor (MAPFAC )
f p
corresponding to existing core flow and power state to assure the adherence to The maximum fuel mechanical design bases during the most limiting transient.
factor (MAPFAC) for single loop operation is 0.86.
For single-loop operation with ANF 8x8 fuel, a MAPLHGR.imit corresponding l
to the product of the highest enriched GE fuel MAPLHGR, and the appropriate MAPFAC, can be conservatively used, provided that the average planar exposure I
is limited to 28,500 MWD /ST.
MAPFAC 's are determined using the three-dimensional BWR simulator code to f
analyze slow flow runout transients.
Two curves for each fuel vendor are pro-vided for use based on the existing setting of the core flow limiter in the Recirculation Flow Control System.
The curve representative of a maximum core flow limit of 107.0% is more restrictive due to the larger potential flow runout transient.
to protect MAPFAC 's are generated using the same data base as the MCPRp p
the core from plant transients other than core flow increases.
The daily requirement for calculating APLHGR when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER is sofficient since power distribu-tion shifts are very slow when there have not been significant power or control GRAND GULF-UNIT 1 B 3/4 2-1 Amendment No. 39
l 3/4.2 POWER DISTRIBUTION LIMITS BASES l
AVERAGE PLANAR LINEAR HEAT GENERATION RATE (Continued)
The requirement to calculate APLHGR within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the rod changes.
completion of a THERMAL POWER increase of at least 15% of RATED THERNAL POWER ensures thermal limits are met after power distribution shifts while still a11otting time for the power distribution to stabilize. The requirement for calculating APLHGR after initially determining a LIMITING CONTROL ROD PATTERN exists ensures that APLHGR will be known following a change in THERMAL POWER or power shape, that could place operation exceeding a themal limit.
i The calculational procedure used to establish the APLHGR limits is based on a loss-of-coolant accident analysis. The analysis was, performed using calculational models which are consistent with the requirements of Appendix K to 10 CFR 50. These models are described in references 1, 6, and 8.
3/4.2.2 [ DELETED]
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GRAND GULF-UNIT 1 B 3/4 2-2 Amendment No. 23 l
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