Text

Amend 131 to License DPR-62,revising Main Steam Line High Radiation Scram & Isolation Setpoints,On one-time Basis,To Facilitate Test Injections of Hydrogen Into Reactor Coolant
	ML20215D945
Person / Time
Site:	Brunswick
Issue date:	12/10/1986
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Carolina Power & Light Co
Shared Package
ML20215D948	List: ML20215D945; ML20215D958;
References
	DPR-62-A-131 NUDOCS 8612170146
	Download: ML20215D945 (10)
	v • d • e

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UNITED STATES 8

NUCLEAR REIULATCRY COMMISSION o

'E WASHINGTON D. C. 20666 l

r-i CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.131 License No. DPR-62 t

1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Carolina Power & Light Company (thelicensee)datedAugust 22, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regula.tions 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 Commission; 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the common 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.

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-62 is hereby amended to read as follows:

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., i (2)TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.131, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION GJ s ma Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 10, 1986 1

ATTACHMENT TO LICENSE AMENDMENT NO.131 i

FACILITY OPERATING LICENSE N0. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Page No.

2-4 2-6 3/4 3-11 3/4 3-16a*

3/4 3-17 3/4 3-21 3/4 3-21a*

Page added

tow TABLE 2.2.1-1 E

cn REAC10R PROTECTION SYSTEN INSTRUDNtNTATION SETPOINTS 7:

FUNCTTONAL UNIT AND INSTRU E NT NtBIBER ALIDWABLR E

TRIP SETFOINT VALUES Q

1.

Intermediate Range Moni,E F C H) tor, Neutron Flux - High(I)

$ 120 divisions of full scale

$ 120 divisions I

(C51-IBM-K601A,B,C,D,,..

w I

of full scale I

2.

Average Power Range Monitor (C51-APRM-CH.A,B,C,D,1,F)

Neutron Flus - High, 151(2) a.

$ 15% of RATED TNERNAL POWER

$ 151 of RATED 11tERMAL POWER b.

Flow Biased Neutron Flus - HighI3)(4)

$ (0.66 W + 542)

$ (0.66 W + 541)

Fixed Neutron Flus - HighI0) c.

$ 1201 of RATED THERMAL POWER

$ 120% of RATED i

THERMAL POWER 3.

Reactor Vessel Steam Dome Pressure - High

$ 1045 pois 3 1045 psig (821-P11t-N023A-1,B-1,C-1.D-1 )

4.

Reactor Vessel Water Level - Low, level 1 3 +162.5 inches

3 +162.5 inches *

(B21-LTM-N017A-1,B-1 C-1 D-1) 5.

Main Steam Line Isolation Valve - Closure (5)

$ 10Z closed

$ 102 closed (B21-F022A,B,C,D) 821-F028A,B,C,D) g 6.

Main Steam Line Radiation - High(I)

< 3 a full power background

$ 3.5 x full power g

(D12-kn -K603 A,5,C,D)

{I backgrounT i

g 7.

Drywell Pressure - High

$ 2 psig

$ 2 psig (C72-PTM-N002A-1,5-1,C-1,D-1) n U

8.

Scram Discharge Volume Water Level - High

< 109 gallons

< 109 gallons i

E (Cl2-LSH-N013A,B C D)

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(Cl2-LSH-4516A,B,C,D)

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TABLE 2.2.1-1 (Cantinuid)

R[ACTORPROTECTIONSYSTEMINSTRUMENTATIONSETPOINTS TABLE NOTATION

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Vessel water levels refer to REFERENCE LEVEL ZERO.

(1) The Intermediate Range Monitor scram functions are automatically bypassed s.

when the reactor mode switch is placed in the Run position and the Average Power Range Monitors are on scale.

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"L (2) This Average Power Range Monitor scram function is a fixed point and is

' t increased when the reactor mode switch is placed in the Run< position.

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(3) The Average Power Range Monitor scram function is varied, Figure 2.2.1-1, i[t'\\

as a function of recirculation loop flow (W). The trip setting of this ti.

function must be maintained in accordance with Specification 3.2.2.

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l (4) The APRM flow-blased high neutron fluz signal is fed through a time constant circuit of approximately 6 seconds. The APRM fixed high neutron finx signal does not incorporate the time constant, but responds directly to instantaneous neutron fluz.

(5) The Main Steam Line Isolation Valve-Closure scram function is' automatically bypassed when the reactor mode switch is in other than the

'i,o Run position.

(6) These scram functions cre bypassed when THERMAL POWER is less than 30% of i

q RATED THERMAL POWER.

j (7) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . prior to the planned start of the hydrogen injection test, with reactor power at greater than 22% of rated thermal power, the

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normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation

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level supected during the tes:. Tha background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determindd and the associated trip setpoints shall be set within 24 hoars of re-establishing normal radiation levels after completion of the hydrogen injection test or within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of sacablishing reactor

- power levels be16v 22% of rated thermal power, while these functions are required to be operable.

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BRUNSWICK - UNIT 2 2-6 Amendment No. f$,78,131 4

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l TABLE 3.3.2-1 Yg ISOLATION ACTUATION INSTRUNENTATION 5

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VALVE CROUPS MININtBf NtBfBER APPLICABLE

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OPERATED BY OPERABLE CNAtBIELS OPERATIONAL TRIP FLBBCTION AND INSTRLBSNT NtBIBER SIGNAL (a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION s

I Ey l '. PRIMARY CONTAIIBGENT ISbEATION a.

Reactor Vessel Water Level -

1.

tow, te 1 1 2, 6, 7, a 2

i, 2, 3 6

(B21-LT-N017A-1,B-1,C-1,D-1) 4 (B21-LTM-II017A-1,5-1,C-1, D-1 )

I 2.

Low, Le.el 2 1, 3 2

1, 2, 3 20 (821-LT-IID24A-1,5-1, and B21-LT-M025A-1,B-1) t2 (B21-LTM-IIO24A-1,B-1 and B21-LTM-10025A-1,8-1) u I

p b.

Drywell Pressure - High 2,6,7 2

1, 2, 3 20 (C72-PT-N002A,B,C,D)

(C72-PTM-91002 A-1, B-1, C-1, D-1) c.

Main Steam Line 1.

Radiation - Nigh (d) 1 2

1,2,3III (D12-RN-K603A,B,C,D) 21 2.

Pressure - Low 1

2 1

22 (821-PT-N015A,B,C,D) g (821-P1M-N015A-1,B-1,C-1,D-1 )

3.

Flow - High 1

2/line 1

J2

((

(821-PDT-bl006A,B,C,D; B21-PDT-II007A,B,C,D8 i

B21-PDT-1000BA, B,C,DI i

g 821-PDT-II009A,B,C,D)

(821-PDTM-It006 A-1, B-1, C-1, D-1 ;

,' e g.

821-PDTM-NOO7A-1,5-1.C-1,D-1; y

821-PDTM-N00BA-1,8-1.C-1,D-1; y

821-PDTM-N009A-1,8-1,C-1,D-1)

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TABLE 3.3.2-1 (Centinued)

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. ISOLATION ACTUATION INSTRUMENTATION

r ACTIONS j

t (i)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test, with reactor power at greater than 22% of rate'd thermal power, the

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normal full power radiation background level and associated trip setpoints may be changed based on a calulated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and the associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels after completion of the hydrogen injection test or within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of establishing reactor power levels below 22% of rated charsal power, while these functions are required to be operable.

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BRUNSWICK - UNIT 2 3/4 3-16a Amendment No. 131 e

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TABLE 3.3.2-2 m

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ISOLATION ACTUATION INSTRUMENTATION SETPOINTS O

i g

ALLOWABLE p;

TRIP FUNDTION AND INSTRUMENT NUMBER

. TRIP SETPOINT VALUE a

1.

PRIMARY CONTAINNENT ISOLATION e

a.

Reactor Vessel Water Level -

i

( B21-LIM-NO17A-1,B-1,C-1,D-1 )

-> + 162.5 inches (a)

-> + 162.5 i'nchesY8) 1.

Low, Level 1 3 + 112 inches (a)

+ 112 inches ")

I 2.

Low, Level 2 (B21-LTH-NO24A-1,B-1 and i

B21-LTM-N025A-1,B-1) 1 j

b.

Drywell Pressure - High 5 2 psig

$ 2 psig (C72-PTM-N002A-1,B-1,C-1,D-1)

E' c.

Main Steam Line

-< 3 x full power background (b) < 3,5, gogg po,,7(b) 1.

Radiation - High

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(D12-RH-K603A,B,C,D) background 2.

Pressure - Low 3 825 psig 1 825 psig (B21-PTM-N015A-1,B-1,C-1,D-1) 3.

Flow - High

$ 140% of rated flow

$ 140% of rated flow (B21-PDTH-NOO6A-1,B-1,C-1,D-1; B21-PDTM-NOO7A-1,8-1,C-1,D-1; B21-PDTM-NOO8A-1,8-l,C-1,D-1; B21-PDTH-NOO9A-1,B-1,C-1,D-1) 4.

Flow - High

$ 40% of rated flow

< 40% of rated flow g

(B21-PDTS-N006A-2; a

B21-PDTS-N007B-2; E.

B21-PDTS-N008C-2; 0

B21-PDTS-NOO9D-2) i S

E.

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1.

2

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g TABLE 3.3.2-2 (Continued)

Ug ISOIATION ACTUATION INSTRLMENTATION SETPOINTS n

1 8

ALLONABLE g

TRIP

FUNCTION AND INSTRUIENT NIMBER TRIP SETPOINT VALUE n

i 3.

RCIC Steam supply Pressure - Low 1 50 pois t 50 peig y

(E51-PS-N019A,B,C,D) 4.

RCIC Steam Line Tunnel Tamp - High

$ 175'F

$ 175*?

(E51-T3-33193 E51-TS-33203 i

E51-TS-33213 E51-TS-33223 E51-TS-33233 E51-TS-3355; i

E51-TS-3487) 5.

Bus Power Monitor NA NA (E51-K42 and E51-E43) 6.

RCIC Turbine Exhaust Diaphragm Pressure - High 1 10 peig 1 10 psig (E51-PS-H012A,B,C,D)

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7.

RCIC Steam Line Ambient Temp - High 1 200*F

$ 200*F (E51-TS-M603A,B) 8.

RCIC Steam Line Area A Temp - High

$ 50*F

$ 50*F (E51-dTS-N604A,8) -

9.

RCIC Equipment Room Ambient Temp - High

$ 175'F

$ 175*F (E51-TS-N602A,8) 10.

RCIC Equpment Room & Temp - High

$ 50*F

$ 50*F i

S.

(E51-dTS-N601A,5) 1 8

R 5.

SHUTDOWN COOLING SYSTEN ISOLATION i

A P

a.

Reactor Vessel Nater Level -

]

Q Low, Level 1 1 + 162.5 inches (a)

+ 162.5 inches (a)

(821-LTM-N017A-1,8-1,C-1,D-1)

' ~

B b.

Reactor Steam Dome Pressure - High

$ 140 ps'ig

< 140 psig 1

(832-PS-N018A,8)

TABLE 3.3.2-2 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS

t l

NOTES 3

(a)

Vessel water levels refer to REFERENCE LEVEL ZERO.

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(b)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test, with reactor power at greater than 22% of rated thermal power, the normal full power radiation background level and associated trip setpoints may be changed based on a caluisted value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations.or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and the associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re establishing normal radiation levels after completion of the hydrogen injection: test or within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of establishing reactor a

power levels below 22% :of rated thermal power, while these functions are required to be operable.

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BRUNSWICK - UNIT 2 l

3/4 3-21a Amendment No.131 l

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ML20215D945

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