Text

Proposed Tech Specs,Revising Description of Control Rod Assemblies
	ML20198P268
Person / Time
Site:	Brunswick
Issue date:	10/29/1997
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20198P267	List: BSEP-97-0458, Application for Amends to Licenses DPR-71 & DPR-62,revising Description of Control Rod Assemblies,Per Description Contained in NUREG-1433,Rev 1; ML20198P268;
References
	NUDOCS 9711070043
	Download: ML20198P268 (9)
	v • d • e

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ENCLOSURES BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS DESCRIPTION OF CONTROL ROD ASSEMBLIES PAGE CHANGE INSTRUCTIONS UNIT 1 Removed page Inserted page 5-4 5-4 PAGE CHANGE INSTRUCTIONS UNIT 2 Removed page Inserted page 5-4 5-4 h b!Eb 4

ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS,1 AND 2 DOCKET NOS,50-325 AND 50-324 LICENSE NOS, DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS DESCRIPTION OF CONTROL ROD ASSEMBLIES TYPED TECHNICAL SPECIFICATION PAGES - UNIT 1 i

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DESIGN FEATURES 5.3 REACTOR CORE CONTROL R00 ASSEMBLIES 5.3.2 The reactor core shall contain 137 cruciform shaped control rod assemblies. The control material shall be boron carbide or hafnium absorber material as approved by the NRC.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculation system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 4.2 of the FSAR. with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 1250 psig, and

c. For a temperature of 575*F. -

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 18.670 cubic feet.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.

BRUNSWICK - UNIT 1 5-4 Amendment No. j l

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o ENCLOSURE 7 .

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS 1 AND 2 DOCKET NOS. 50 325 AND 50-324 LICENSE NOS. DPR-71 AND DPR 62 REQUEST FOR LICENSE AMENDMENTS DESCRIPTION OF CONTROL ROD ASSEMBLIES TYPED TEC11NICAL SPECIFICATION PAGES - UNIT 2

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. ,, . DESIGN FEATURES-

-5.3 REACTOR CORE CONTROL R00 ASSEMBLIES 5,3.2 The reactor core shall contain 137 cruciform shaped control rod assemblies. The control material shall be boron carbide or hafnium absorber material as approved by the NRC.

5.4 REACTORCOOLANTSYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculation system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 4.2 of the FSAR. with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 1250 psig, and

c. For a temperature of 575'F, .

VOLUME 5.4.2 The total wa' _r mJ ,,r. altaw or O' recc+ , m st' . <i recirculation syst a .ru s .i, m '; . J " - %n.

i 15 METEOROLOGICA J g 5A tg 3 U d 5.5.1 The meteorolos' : u"' ' oe . , _ she'.<n in Figure 5.,1. 1-1.

BRUNSWICK - UNIT 2 5-4 Amendment No.

ENCLOSURE 8 t i BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS,1 AND 2

. DOCKET NOS. 50-325 AND 50-324 LICENSE NOS DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS DESCRIPTION OF CONTROL ROD ASSEMBLIES e

l MARKED UP TECIINICAL SPECIFICATION PAGES - UNIT 1

c ..-o DESIGN FEATURES ll... .s' .

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5.3 REACTOR CORE CONTROL ROD ASSEMBLIES l

COrucWorm shaPedj l 5.3.2 Thereactorcoreshallcontain137/controlrodassembiles y :::h-

-sensi: ting- ef a cruciferr err:-/ ef ete! lere steel tube: :::::inir;

-:ppre:isstelj l':3 inch:: :: beren ::: bide, 34 C, peed:: :: hef ';; :t:::b; ecd: :::::: d:d by : ::::!!::: : hep:d :tcinier trel c' t'_ The contro l rnaterlat shan be boren carbide crc hafniu.m absorbe.e makeda.t as approved by the NRC.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculation system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 4.2 of the FSAR, with allowance for normal degradation purs6 ant to the applicable Surveillance Requirements. !

b. For a pressure of 1250 psig, and -

c. For a temperature of 575 F.

Y. .

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 18,670 cubic feet.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.

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BRUNSWICK - UNIT 1 5-4 Amendment No. 144>' '

..o ENCLOSURE 9 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS DESCRIPTION OF CONTROL ROD ASSEMBLIES MARKED-UP TECHNICAL SPECIFICATION PAGES - UNIT 2 -

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DESIC' FEATURES

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5.3 REACTGR CORE CONTROL ROD ASSEMBLIES eruciform Shapek t

5.3.2 .The reactor core shall contain 137 control rod assembliesy-esch cen:1: tin;; cf : crucifer- array of stainles e steel tubes conteir'.n;;

-spprer! ately 1^3 inche: ef herer carbide, C, poeder er hafniu :Sa+v4e+

-r:d: :urr:=ded by : :ru:!fer :h:p:d :::!n (te:: :::ci :h::th. ~[he, caricrol material shall be boron caeb'.de w hatniurn absoder male;ea as approved by the NRC.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculacion system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 4.2 of

, the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, #

b. For a pressure of 1250 psig, and

c. For a temperature of 5750F.

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VOLUME 5.4.2 The total water and steam volume of the reactor vessel and 4

recirculation system is approximately 18,670 cubic feet.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.

t 3RUNSWICK - UNIT 2 5-4 Amendment No. M

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ML20198P268

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