ML20133J464
| ML20133J464 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/30/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20133J466 | List: |
| References | |
| DPR-71-A-086 NUDOCS 8508120033 | |
| Download: ML20133J464 (17) | |
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k UNITED STATES
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g NUCLEAR REGULATORY COMMISSION O
- j WASHINGTON, D. C. 20555 l
CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated April 26, 1985, as supplemented July 2,1985, 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 (i) 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 Comission's regulations and all applicable requirements have been satisfied.
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 Facility Operating License No. DPR-71 is hereby amended to read as follows:
8508120033 850730
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PDR ADOCK 05000325 P
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ef-fective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 30, 1985
ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The changed areas are indicated by vertical lines.
Pages 3/4 2-2 3/4 2-3 3/4 2-4 3/4 2-5
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3/4 2-6 3/4 2-7 3/4 2-8 3/4 2-9 3/4 2-10 3/4 2-14 3/4 2-16 3/4 3-42 8 3/4 2-3 5-1
7.
a MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) y VERSUS AVERAGE PLANAR EXPOSURE i
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i BRUNSWICK - UNIT 1 3/4 2-4 Amendment No.
86 l
B
E MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) y VERSUS AVERAGE PLANAR EXPOSURE i
13.0 E
- 1 11.1 12.1 I
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d of Operation g,
- 9. 0 li E.
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5000' 10000 15000 20000 25000 30000 35000 40000 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type P80R8265H (P8X8R)
Fir,IIRF 'a ? 1-A
l MAXIMUM AVERAGE PLANAR LINEAR llEAT GENERATION RATE (MAPLHGR)
=
h VERSUS AVERAGE PLANAR EXPOSURE e
13.0 H
- 12. 0 12.0 12.0
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of Operation
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- 8. 0 l
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5000' 10000 15000 20000 25000 30000 35000 40000 8
AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type P80R8284H (P8X8R) i
' FIGilRE 3. 2.1-5
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AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type P80RB299 (P8X8R)
FICURE 3.2.1-6 l
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.8 AVERAGE PLANAR EXPOSURE (mwd /t)
Fuel Type BP80R8299 (BP8X8R)
FIGURE 3.2.1-7
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(BSEP-1-60)
....,.._ 1 POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTS
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LIMITING CONDITION FOR OPERATION 3.2.2 The flow-biased APRM scram trip setpoint (S) and rod block trip set point (SRB) shall be essablished according to the following relationship S $ (0.66W + 54%) T SRB $ (0.66W + 42%) T wheret S and S are in percent of RATED THERMAL POWER.
RB W = Loop recirculation flow in percent of rated flow, T 4 Lowest value of the ratio of design TPF divided by the HTPF obtained for any class of fuel in the core (T $ 1.0), and Design TPF fort 8 x 8R fuel = 2.39 P8 x 8R fuel = 2.39 BP8 x 8R fuel = 2.39 APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
ACTION:
With S or SRB 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or reduce THERMAL POWER to less than 25% of RATE,D 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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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 requiredt a.
At least once per-24 hours',
' ~ ' '
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 c.
operating with a LIMITING CONTROL ROD PATTERN for MTPF.
BRUNSWICK UNIT - 1 3/4 2-9 Amendment No. 86
(BSEP-1-60)
POWER DISTRIBUTION LIMITS e
3/4.2.3 MINIMUM CRITICAL POWER RATIO LIMITINC CONDITION FOR 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:
g Beginning-of-cycle (BOC) to end-of-cycle (EOC) minus 2000 MWD /t with s.
ODYN OPTION A analyses in effect, the MCPR limits are listed below:
1.
MCPR for 8 x 8R fuel = 1.25 2.
MCPR for P8 x 8R fuel = 1.27 3.
MCPR for BP8 x 8R fuel = 1.27 EOC minus 2000 MWD /t to EOC with ODYN OPTION A analyses in effect, b.
the MCPR limits are listed below:
1.
MCPR Tor 8 x 8R fuel = 1.36 2.
MCPR for P8 x 8R fuel = 1.39 3.
MCPR for BP8 x 8R fuel = 1.39 BOC to EOC minus 2000 MWD /t with ODYN OPTION B analyses in effect, c.
the MCPR limits are listed below:
1.
MCPR for 8 x 8R fuel = 1.24 2.
MCPR for P8 x 8R fuel = 1.24 3.
MCPR for BP8 x 8R fuel = 1.24 d.
EOC minus 2000 MWD /t to EOC with ODYN OPTION B analyses in effect, the MCPR limits are listed below:
1.
-HCPR for 8 x 8R fuel = 1.25 2.
.3.
MCPR for BP8 x 8R fuel = 1.27 APPLICABILITY: OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% RATED THERMAL POWER ACTION:
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 />.
BRUNSWICK UNIT - 1 3/4 2-10 Amendment No. 86
TABLE 3.2.3.2-1 (BSEP-1-60)
E i
y l
TRANSIENT OPERATING LIMIT MCPR VALUES E
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TRANSIENT FUEL TYPE j
y 8x8R P8x8R BP8x8R e
I NONPRESSURIZATION TRANSIENTS BOC + EOC 1.24 1.24 1.24 1
t TURBINE TRIP / LOAD REJECT WITHOUT BYPASS
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MCPR MCPR MCPR MCPR MCPR HCPR A
B A
B A
B BOC + EOC - 2000 1.25 1.08 1.27 1.08 1.27 1.08 w
h EOC - 2000 + EOC 1.36 1.24 1.39 1.27 1.39 1.27 FEEDWATER CONTROL FAILURE i
MCPR MCPR MCPR MCPR MCPR MCPR A
B A
B j
A B
BOC + EOC - 2000 1.21 1.15 1.21 1.15 1.21 1.15 EOC - 2000 + EOC 1.32 1.25 1.34 1.27 1.34 1.27 I
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(BSEP-1-60)
POWER DISTRIBUTION LIMITS 3/4.2.4 LINEAR HEAT CENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.4 The LINEAR HEAT CENERATION RATE (LHCR) shall not exceed 13.4 kw/ft for 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 LHCR is within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 4.2.4 LHCR shall be determined to be equal to or less than the limit:
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 on a LIMITING CONTROL ROD PATTERN for LHCR.
BRUNSWICK UNIT - 1 3/4 2-16 Amendment No. 86
E TABLE 3.3.4-2 (SSEP-1-60)
Ei E!
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS M
pc E!
TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWABLE VALUE 4
1.
APRM (CSI-APRM-CH. A,B,C,D,E,F) a.
Upscale (Flow Biased)
$ (0.66W + 42%)
T*
$ (0.66W + 42%)
T*
MTPF MTPF b.
Inoperative NA NA c.
Downscal e
> 3/125 of full scale
> 3/125 of full scale d.
Upscale (Fixed)
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112% of RATED THERMAL POWER
$ 12% of RATED THERMAL POWER 2.
ROD BLOCK HONITOR (CSI-RBM-CH.A,B) a.
Upscale
$ (0.66W + 41%)
T*
$ (0.66W + 41%)
T*
MTPF MTPF b.
Inoperative NA NA c.
Downscale 3 3/125 of full scale 3 3/125 of full scale D
3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D) e a.
Detector not full in NA NA b
5 5
b.
Upscale
$ 1 x 10 cps 5 1 x 10 cps c.
Inoperative NA NA d.
Downscale 3 3 cps 3 3 cps 4.
INTERMEDIATE RANCE MONITORS (C51-I RM-K601 A, B,C,D, E, F,C,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.
Downscal e 3 3/125 of full scale 3 3/125 of full scale g
5.
SCRAM DISCHARGE VOLUME (C11-LSH-N013E) g a.
Water Level - High
$ 73 gallons 5 73 gallons n.
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- T=2.39 for 8x8R fuel y
T=2.39 for P8x8R fuel e
T=2.39 for BP8x8R fuel 1
(BSEP-1-60) t r
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 PEAKINC FACTOR of 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 2.39 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.
2/4.2.3 MINIMUM CRITICAL POWER RATIO The required operating limit MCPR's at steady state operating conditions as specified in Specification 3.2.3 are derived from the established fuel claddingintegritySafggyLimitMCPRof1.07,andananalysisofabnormal 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
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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 r?nd power, positive reactivity insertion, and coolant temperature decrease.
The required minimum operating limit MCPR of Specification 3.2.3 is obtained when the transient which yields the largest ACPR is added to the Safety Limit MCPR of 1.07.
Prior to analysis of abnormal operational transients, an initial fuel bundle MCPR was determined. This parameter is based on the bundle flow calculated by a CE multichannel ste modelasdescribedinSection4.4ofNEDO-20360ggystateflowdistribution and on core parameters shown in Reference 3, response to Items 2 and 9.
BRUNSWIC% UNIT - 1 B 3/4 2-3 Amendment No.
86
(BSEP-60).
4 5.0 DESIGN FEATURES l
5.1 SITE EXCLUSION AREA The exclusion area shall be as shown in Figure 5.1.1-1.
5.1.1 LOW POPULATION ZONE The low population zone shall be as shown in Figure 5.1.2-1, based on 5.1.2 the information given in Section 2.2 of the FSAR.
SITE BOUNDARY For the The SITE BOUNDARY shall be as a shown in Figure 5.1.3-1.
5.1.3 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 The PRIMARY CONTAINMENT is a steel-lined reinforced concrete structure 5.2.;
composed of a series of vertical right cylinders and truncated cones which This drywell is attached to a suppression chamber through a form a drywell.
The suppression chamber is a concrete steel-lined pressure series of vents.
The primary containment has a minimum free vessel in the shape of a torus.
air volume of (288,000) cubic feet.
I DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:
Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperature: drywell 300 F.
0 suppression chamber 200 F.
Maximum external pressure 2 psig.
c.
5.3 REACTOR CORE FUEL t.SSEMBLIES The reactor core shall contain 560 fuel assemblies, of 8x8R, P8x8R, and 5.3.1 Each fuel assembly contains 62 fuel rods. All fuel rods BPSx8R fuel types.
Each fuel rod shall have a nominal active shall be cladded with Zircaloy 2.
fuel length 150 inches.
Amendment No. 86 5-1 BRUNSWICK - UNIT 1 P
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