Text

Proposed Tech Specs Allowing Temporary Rev to Setpoint for Main Steam Line Radiation High Scram & Isolation
	ML20203L430
Person / Time
Site:	Brunswick
Issue date:	08/22/1986
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20203L429	List: ML20203L427; ML20203L430;
References
	NLS-86-233, NUDOCS 8608260226
	Download: ML20203L430 (9)
	v • d • e

_ _ _..

Enclosure i to SERIAL: NLS-86-233 Revised Brunswick-2 TS Pages (86TSB11) 8608260226 860822 PDR ADOCK 0500 4

P (3985 MAT /pgp)

Summary List of Revisions Page No.

description of Change 2-4 Added indication of Note (7) to Item 6.

2 2-6 Provided Note (7) regarding determination of Main Steam Line Radiation - High Setpoints.

3/4 3-11 Added indication of Note (i) to item 1.C.I.

3/4 3-16a New Page. Provided Note (i) regarding determination of Main Steam Line Radiation - High setpoints.

l 3/4 3-17 Added indication of Note (b) to Item 1.c.l.

Revised Note designation

to (a) on Items 1.a.1 and 1.a.2.

3/4 3-21 Revised Note designation

to (a) on Item 5.a.

Removed Note *

~

3/4 3-21a New page. Includes Note (a) which is old Note

from page 3/4 3-21. Provides Note (b) regarding determination of Main Steam Line Radiation - High setpoints.

)

i l

i i

( 3985 MAT /pgo )

I

(BSEP-2-90)

TABLE 2.2.1-1 0

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS En ALIhWABLE FUNCTIONAL UNIT AND INSTRUMElfr MIMBER TRIP SETPOInfr VALUES E

G 1.

Intermediate Range Monitor, Neutron Flux - High(1)

$ 120 divisions of full scale

$ 120 divisipns (C51-I RM-K601 A, B,C,D,'E,F,C,H )

of full scale ra 2.

Average Power Range Monitor (CS I-APRM-CH. A, B,C,D,E,F)

Neutron Flus - High, 15%(2)

$ 15% of RATED THERMAL POWER

$ 15% of RATED a.

THERMAL POWER b.

Flow Biased Neutron Flux - HighI3)(4)

$ (0.66 W + 54%)

$ (0.66 W'+ 54%)

ro c.

Fixed Neutron Flux - HighI4)

I-

$ 120% of RATED THERMAL POWER

$ 120% of RATED THERMAL POWER 3.

Reactor Vessel Steam Dome Pressure - High 5 1045 psig

$ 1045 psig (B21-PTM-NO23A-1,B-1,C-1,D-1) 4.

Reactor Vessel Water Level - Low, Level 1

> +162.5 inches *

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

Main Steam Line Isolation Valve - Closure (5) 10% closed

$ 10% closed (B21-F022A,B,C,DI B21-F028A,B,C,D)

II) g 6.

Main Steam Line Radiation - High

$ 3 x full power background 5 3.5 x full power g

(D12-na -K603 A, B,C, D) background Pg'i 7.

Drywell Pressure - High

$ 2 peig 5 2 peig (C72-PTM-M002A-1,8-1,C-1,D-1) n P

8.

Scram Discharge Volume Water Level - High

$ 109 gallons

$ 109 gallons (Cl2-LSH-NOl3A,B,C,D)

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

(BSEP-2-90)

TABLE 2.2.1-1 (Continued)

REhCTOR'PROTECTIONSYSTEMINSTRUMENTATIONSETPOINTS TABLE NOTATION 1

Vessel water levels refer to REFERENCE LEVEL ZERO.

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

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

(2) This Average Power Range Monitor scram function is a fixed point and is increased when the reactor mode switch is placed in the Run position.

(3) The Average Power Range Monitor scram function is varied, Figure 2.2.1-1, as a function of recirculation loop flow (W). The trip setting of this

)

function must be maintained in accordance with Specification 3.2.2.

(4) The APRM flow-biased high neutron flux signal is fed through a time constant circuit of approximately 6 seconds. The APRM fixed high neutron flux signal does not incorporate the time constant, but responds directly j

to instantaneous neutron flux.

(5) The Main Steam Line Isolation Valve-Closure scram function is e

automatically bypassed when the reactor mode switch is in other than the Run position.

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

RATED THERMAL POWER.

i[

(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 normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and i

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 j

be determindd 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 j

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 thermal power, while these functions are l

required to be operable.

I I

i BRUNSWICK - UNIT 2 2-6 Amendment No.

4 I

.-r-y,---,,.,,.-

-w

1 (BSEP-2-90) i TABLE 3.3.2-1 Eg ISOLATION ACTUATION INSTRUNENTATION Eg VALVE CROUPS MINIMUM NUMBER APPLICABLE 7:

OPERATED BY OPERABLE CHANNELS OPERATIONAL s

TRIP FUNCTION AND INSTRUMENT huMBER SICNAL(a)

PER TRIP SYSTEM (b)(c)

CONDITION ACTION 1.

PRIMARY CONTAINMENT IS6LATION a.

Reactor Vessel Water Level -

1.

Low, Level 1 2,6,7,8 2

1, 2, 3 20 i

(B21-LT-5017A-1,B-1,C-1,D-1)

(B21-LTM-NOl7A-1,8-1,C-1,D-1) 2.

Low, Level 2 1, 3 2

1, 2, 3 20 (821-LT-NO24A-1,B-1, and 821-LT-N025A-1,B-1) t (B21-LTM-NO24A-1,B-1 and B21-LTM-NO25A-1,B-1)

Yp b.

Drywell Pressure - High 2,6,7 2

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

(C72-PTM-N002A-1,8-1,C-1,D-1) 1 c.

Main Steam Line l

1.

Radiation - High (d) 1 2

1, 2, 3(I) 21 (D12-RM-K603A,B,C,D) i 2.

Pressure - Low 1

2 1

22 (B21-PT-W015A,B,C,D)

(821-PTM-NO15A-1,B-1,C-1,D-1)

G 3.

Flow - High 1

2/line 1

22 (B21-PDT-NOO6A,B,C,D; B21-PDT-NGO7A,B,C,D; B21-PDT-NOO8A,B,C,D; y

B21-PDT-NOO9A,B,C,D)

(B21-PDTM-N006A-1,B-1,C-1,D-1; B21-PDTM-NOO7A-1,B-1,C-1,D-1; B21-PDTM-NOO8A-1,B-1,C-1,D-1; B 21-PDTM-N009 A-1, B-1. C-1, D-1 )

(BSEP-2-90)

TABLE 3.3.2-1 (Continued)

^

ISOLATION ACTUATION INSTRUMENTATION ACTIONS (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 rated thermal power, the 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 belov 22% of rated thermal power, while these functions are required to be optrable.

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

(BSEP-2-90) m TABLE 3.3.2-2 M

~

ISOLAT:.ON ACTUATION INSTRUMENTATIOh SETPOINTS S

A i

e ALLOWABLE

,M, TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SET ___

VALUE INT 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

1.

Low, Level 1

~> + 162.5 inches (a)

> + 162.5 inches (a)

(B21-LTM-NOl7A-1,B-1.C-1,D-1) 2.

Low, Level 2

> + 112 inches (*)

> + 112 inches (a)

(B21-LTM-NO24A-1,B-1 and B21-LTM-NO25A-1,B-1) b.

Drywell Pressure - High 5 2 psig

$ 2 psig (C72-PTM-HOO2A-1,B-1,C-1,D-1)

Ei c.

Main Steam Line

[

(D12-RM-K603A,B,C,D)

-< 3 x full power background (b) < 3.5 x full power (b) l.

Radiation - High background 2.

Pressure - Low

> 825 psig

> 825 psig (B21-PTM-NO15A-1,B-1,C-1,D-1) 3.

Flow - High

$ 140% of rated flow

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

Flow - High

$ 40% of rated flow

$ 40% of rated flow g

(B21-PDTS-NOO6A-2; B21-PDTS-NOO7B-2; a

l-B21-PDTS-NOO8C-2; g

B21-PDTS-NOO9 D-2 )

n

.b f

l o

1 (BSEP-2-90)

Il E

TABLE 3.3.2-2 (Continued)

\\

ens:g ISOLATION ACTUATION INSTRLMENTATION SETPOINTS M

8 ALLOWABLE g

TRIP FUNCTION AND INSTRUNENT MtMBER TRIP SETPOINT VALUE a

3.

RCIC Steam Supply Pressure - Lov 3 50 psig 1 50 psig (E51-PS-NDl9A,B,C,D) 4.

RCIC Steam Line Tunnel Temp - High

< 175*F

$ 175*F (E51-TS-3319; E51-TS-3320; E51-TS-3321; E51-TS-3322; E51-TS-3323; E51-TS-3355; E51-TS-3487) h 5.

Bus Power Monitor MA NA (E51-K42 and E51-K43) m i

l h

6.

RCIC Turbine Exhaust Diaphragm l

Pressure - High

$ 10 psig

$ 10 psig (E51-PS-N012A,B,C,D)

?

7.

RCIC Steam Line Ambient Temp - High

$ 200*F

$ 200*F 1

(E51-TS-N603A,5) 1 8.

RCIC Steam Line Area A Temp - High

$ 50*F

< 50*F i

(E51-dTS-N604A,B)

I j

9.

RCIC Equipment Room Ambient Temp - High

< 175*F

< 175*F (E51-TS-N602A,5) 10.

RCIC Equpment Room A Temp - High

< 50*F

< 50*F S.

(E51-dTS-N601A,B) i a

5 5.

SHUTDOWN COOLING SYSTEM ISOLATION i

a.

Reactor Vessel Water Level -

)

Low, Level 1 3 + 162.5 inches (a)

+ 162.5 inches (a)

{

(B21-LTM-N017A-1,B-1,C-1,D-1) s

]

b.

Reactor Steam Dome Pressure - High

< 140 psig

< 140 psig (B32-PS-NOl8A,B)

(BSEP-2-90)

TABLE 3.3.2-2 (continued)

ISOLATION ACTUATION INSTRUMENTATION SETPOINTS NOTES (a)

Vessel water levels refer to REFERENCE LEVEL ZERO.

(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 satpoints may be changed based on a catulated 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 asscciated 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 thermal power, while these functions are required to be operable.

1 BRUNSWICK - UNIT 2 3/4 3-2La Amendment No.

.

ML20203L430

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