ML20101R185

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Proposed Tech Specs 2.1.2 Revising MCPR Safety Limits from 1.07 to 1.09 for Cycle 11 Operation,Ts 5.3.1 to Reflect GE13 Fuel & Figure 3.1.5-1 to Reflect Changes to Poison Matl Concentration Needed to Achieve Reactor Shutdown
ML20101R185
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 04/08/1996
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20101R183 List:
References
NUDOCS 9604160095
Download: ML20101R185 (9)
v • d • e


Text

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2.0 SAFETY LIMITS AND LIMITINC SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL POWER (Low Pressure or Low Flow) 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 800 psia or core flow less than 10% of rated flow.

APPLICABILITY: CONDITIONS 1 and 2.

ACTION:

With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel steam dome pressure less than 800 psia or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

THERMAL POWER (High Pressure and High Flow)

LOi 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than M l

with the reactor vessel steam dome pressure greater than 800 psia and core flow greater than 10% of rated flow.

l APPLICABILITY: CONDITIONS 1 and 2.  !

l ACTION

  • 1 With MCPR less than d theM.09 reactor vessel steam dome pressure greater l than 800 psia and core flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.

l APPLICABILITY: CONDITIONS 1, 2, 3, and 4.

ACTION:

With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure < 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

l BRUNSWICK - UNIT 1 2-1 Amendment No.

9604160095 960408 PDR ADOCK 05000325 P PDR l-,

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BRUN51r!CK-4JN1T 1 3/4 1-20 NT NO. 106

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SODIUM PENTABORATE SOLUTION VOLUME iirisms CONCENTRATION REQUIREMENTS 22.0 21.0 p 20.0 Region of Required Volume Concentration 55 19.0 -

Acceptable Operation Range 3

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This volume-concentration range

~ 17.0 supports a reactor vessel natural boron concentration of at least 660 ppm.

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Low Level High Level 11.0 Alarm at Alarm at 3220 gals

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3700 gals

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10.0 2000 2500 3000 3500 4000 4500 5000 5500 l

i Net Volume of Solution in Tank (gals)

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1 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1, based on the information given in Section 2.2 of the FSAR.

SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1. For the purpose of effluent release calculations, the boundary for atmospherid 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 CONFICURATION 5.2.1 The PRIMARY CONTAINMENT is a steel-lined, reinforced concrete structure composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete, steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum free I

air volume of (288,000) cubic feet. l l

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

a. Maximum internal pressure 62 psig.
b. Maximum internal temperature: drywell 300*F suppression chamber 200'F l

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c. Maximum external pressure 2 psig.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 'the reactor core shall contain 560 f el assemblies limited to the following fuel types: BP8x8R, CE8x8EB, CE8x8NB-33 and GEIS.

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BRUNSL'ICK - UNIT 1 5-1 Amendment No. J4; "

ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 NRC DOCKET NO. 50-325 OPERATING LICENSE NO. DPR-71 REQUEST FOR LICENSE AMENDMENT FUEL CYCLE 11 RELOAD LICENSING TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1

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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 S'AFETY LIMITS

f. .
THERMAL POWER (Low Pressure or Low Flow) 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 800 psia or core flow less than j 10% of rated flow. .

4 1

! APPLICABILITY: CONDITIONS 1 and 2.

j ACTION:

i With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel

! steam dome pressure less than 800 psia or core flow less than 10% of rated i flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

THERMAL POWER (Hiah Pressure and Hiah Flow) 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 1.09 l  :

with the reactor vessel steam dome pressure greater than 800 psia and core  !

flow greater than '10% of rated flow.

i APPLICABILITY: CONDITIONS 1 and 2.

ACTION:

With MCPR less than 1.09 and the reactor vessel steam dome pressure greater l l than 800 psia and core flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. l REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.

APPLICABILITY: CONDITIONS 1. 2, 3. and 4.

ACTION:

With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure s 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

BRUNSWICK - UNIT 1 2-1 Amendment No.

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FIGURE 3.1.5-1 j SODIUM PENTABORATE SOLUTION VOLUME i CONCENTRATION REQ'JIREMENTS i

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Sodium Pentaborate Solution Volume Concentration Requirements 22.0 ,

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21.0 -

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l 20.0 - - - - - - -

- j - -- ------ Region of Required Volume Concentration i-----~ ~----

l l Acceptable Operation Range 3 pa 19.0 - - - - - - - ~ ~ - - - - - - - - - - - - - -

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i i TNs volume-cancertrWian range  !  !

6. 17,0 -... -~....~ j ~~4~ supports a stor vessei nsurg baron 4... . ... . . . . . . . . . . . .

g .  ; j concatrWion of d least 660 pprn l l g . .

. . _% 16.0 -.~----~~L~----~~+-  :-- --r~---- l-~ - - -

l l 15.0 ----~~~~;-~~---a- - - - -

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0 l 14.0 _................!................!-- .......!,..................!..-. ....!...............!,.................

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12.0 --- ----+~----~~~+- --*--------+-----+~------

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11.0 -------~<-------~-~~---+-------~s--- - - - ~ ~ ~ - ~ " - - -

l 10.0 2000 2500 3000 3500 4000 4500 5000 5500 Net Volume d Solutionin Tank (gals)

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BRUNSWICK - UNIT 1 3/4 1-20 Amendment No.

- _ _ . ._. _ . _ _ _ _ _ _ . . . _ . _ _ . . _ . _.___m e *.-

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.-based on the information given in Section 2.2 of the FSAR.

SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1. For the purpose of effluent release calculations the boundary for atmospheric releares 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 5.2.1 The PRIMARY CONTAINMENT is a steel-lined, reinforced concrete structure composed of a series of vertical right cylinders and truncated cones which form a drywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete, steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum free air volume of 288.000 cubic feet.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

a. Maximum internal pressure 62 psig.
b. Maximum internal temperature: drywell 300 F suppression chamber 200 F
c. Maximum external pressure 2 psig.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies limited to the following fuel types: BP8x8R. GE8x8EB GE8x8NB-3. and GE13. I l

BRUNSWICK - UNIT 1 5-1 Amendment No. i i

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Chronology .

e February 4 - 6,1996: Action i

+ Toxicologist Review of BNP Pre-Screening Operations .

. No Deficiencies in Set-up or Use of Analysis Equipment

. Errors Were Mistakes of Transposition and Omission e February 14,1996: Action

+1ndustry Notification issued Regarding Erroneous Data Reporting During On-Site Vendor Pre-Screening Operations e February 19,1996: Action

, + Submitted Informational Report on issues to NRC Staff Cp&L

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