Text

Amends 175 & 206 to Licenses DPR-71 & DPR-62,respectively, Revising TS to Increase STIs & Allowable OOS Times for Selected Instrumentation of TS Section 3/4.3 & Allow Proposed Bases Mods
	ML20082G462
Person / Time
Site:	Brunswick
Issue date:	03/30/1995
From:	Bateman W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20082G465	List: ML20082G462; ML20082G467;
References
	NUDOCS 9504130265
	Download: ML20082G462 (94)
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UNITED STATES 3J

)

E NUCLEAR REGULATORY COMMISSION' o

WASHINGTON, D.C. 20m0001

' %,...../

CAROLINA POWER & LIGHT COMPANY. et al.

DOCKET NO. 50-325-BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 l

AMENDMENT TO FACILITY OPERATING LICENSE f

Amendment No.175 License No. DPR-71 1.

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

1 A.

The application for amendment filed by Carolina Power & light-Company (the licensee), dated October 28, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as

)

amended (the Act), and the Commission'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-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-71 is hereby amended to read as follows:

i 9504130265 950330 PDR ADOCK 05000324 P

PDR I

E

-- (2)

Technical Specifications The Technical Specifications contained in Appendices A and B,'as revised through Amendment No.175, are hereby incorporated in the license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3.

This licenie amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION y

N /

u btwi~

William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 30, 1995 5

'i ATTACHMENT TO LICENSE AMENDMENT NO.175 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 j

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Pages Insert Paaes 3/4 3-1 3/4 3-1 l

3/4 3-la 3/4 3-2 3/4 3-2 I

3/4-3-3 3/4 3-3 3/4 3-5 3/4 3-5 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 i

3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-17a 3/4 3-17a 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 l

3/4 3-30 3/4 3-30 t

3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35

)

3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-43 3/4 3-43 1

3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46 3/4.3-46 3/4 3-49 3/4 3-49 3/4 3-51 3/4 3-51 j

3/4 3-64c 3/4 3-64c 3/4 3-88 3/4 3-88 3/4 3-89 3/4 3-89 3/4 3-91 3/4 3-91 3/4 3-92 3/4 3-92 3/4 3-93 3/4 3-93 3/4 3-94 3/4 3-94 3/4 3-96 3/4 3-96 B 3/4 3-1 B 3/4 3-1 B 3/A 3-2 B 3/4 3-2 B 3/4 3-2a B 3/4 3-3d B 3/4 3-3d B 3/4 3-3e B 3/4 3-3e B 3/4 3-6 B 3/4 3-6

1 3/4 3 -INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION.

3.3.1 As.a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE. Set points and interlocks are given j

in Table 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

With one channel less than the Minimum Number of OPERABLE Channels per a.

Trip System required by Table 3.3.1-1 in one or more Functional Units, place the inoperable channel and/or that trip system in the tripped condition

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With two or more channels less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.1-1 in one or more Functional Units:

1.

Within one hour, verify sufficient channels remain OPERABLE or in the tripped condition

to maintain trip capability in the Functional Unit, and 2.

Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the inoperable channel (s) in one trip system and/or that trip system ** in the tripped condition

and 3.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other trip system to an OPERABLE status or place them in the tripped condition

1 Otherwise, take the ACTION required by Table 3.3.1-1 for the Functional Unit.

c.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit shall be taken.

This ACTION a) plies to that tri) system with the most inoperable 1

channels: if )oth trip systems lave the same number of inoperable channels, the ACTION can be applied to either trip system.

F BRUNSWICK - UNIT 1 3/4 3-1 Amendment No.78,J71,175

e-

)

3/4 3 INSTRUMENTATION 3/4 3.1-REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS j

4.3.1.1 Each reactor arotec' tion system instrumentation channel 'shall be demonstrated OPERABLE Jy the' performance of the CHANNEL CHECK CHANNEL.

CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shal'1 be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE' TIME of each reactor trip function'shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

t Neutron detectors are exempt from response time testing.

i BRUNSWICK - UNIT 1 3/4 3-la Amendment No. 175

p s

?

h TABLE 3.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION E-A APPLICABLE MINIMUM NUMBER

~

OPERATIONAL ~

OPERABLE CHANNELS FUNCTIONAL UNIT

-CONDITIONS PER TRIP SYSTEM (a)

ACTION.

1. Intermediate Range Monitors:

a.

Neutron Flux - High

2. S'"

3 1

3. 4 2

2' b.

Inoperative

2. 5 3

1 y

3. 4 2

2

2. Average Power Range Monitor a

Neutron Flux High. 15%

2. 5'"

2 3-b.

Flow Biased Simulated Thermal 1

2 4

Power - High c.

Fixed Neutron Flux - High. 120%

1 2

4 d.

Inoperative

1. 2. 5 2;

5 e.

Downscale 1

2 4

f.

LPRM-

1. 2. 5 (c)

.NA-f

3. Reactor Vessel. Steam Dome Pressure - High-

1. 2'"

2-l6

4. Reactor Vessel Water Level

. Law. Level 1

1. 2 2

6

[

5. Main Steam Isolation Valve - Closure 1

4 4

O g

6. Main Steam Line Radiation - High

1. 2'* '

.2 7-E L

M

.n

,cp u.

b x.

'E 5;ep;

-TABLE 3.3.1-1 (Continued) n REACTOR PROTECTION SYSTEM INSTRUMENTATION 1g A

APPLICABLE MINIMUM NUMBER- '

4 OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)

ACTION

7. Drywell Pressure - High

1. 2'd 2.

6 e

8. Scram Discharge Volume Water Level - High

1. 2, 5'"

2 5

9. Turbine Stop Valve - Closure l'O 4

8 W

10. Turbine Control Valve Fast Closure.

[

Control Oil Pressure - Low 1(*

2

~

'8

11. Reactor Mode Switch in Shutdown Position 1.2.3.4.5 1

9'

12. Manual Scram 1.2.3.4.5 1

10

13. Automatic Scram Contactors 1.2.3.4.5 2

10 l

ia

.F N=

~

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O m

r TABLE 3 31-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION _10 -

In OPERATIONAL CONDITION 1 or-2, be in at least HOT SHUTDOWN o

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

7 In OPERATIONAL CONDITION 3 or 4. lock the reactor mode switch in

~

the Shutdown position within one hour.

In OPERATIONAL CONDITION 5. suspend ~all o)erations involving-CORE ALTERATIONS or positive reactivity c1anges and fully insert all. insertable control rods within one hour.

HQIES (a)

When a channel is placed in an inoperable status solely for performance

^

of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Functional Unit maintains RPS trip capability.

(b)

The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn

and during shutdown margin demonstrations.

(c)

An APRM channel is inoperable if there are less than 2 LPRM inputs per-level or less than eleven LPRM inputs to an APRM channel.

(d)

These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.

(e)

This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(f)

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(g)

These functions are bypassed when THERMAL POWER is less than 30% of-RATED THERMAL POWER.

Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

BRUNSWICK - UNIT 1 3/4 3-5 Amendment No.26,28,J39,175

a.

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q TABLE 4.3.1-1 7

-REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1 C

3 CHANNEL

.. OPERATIONAL-CHANNEL FUNCTIONAL CHANNEL

. CONDITIONS IN WHICHI

~

FUNCTIONAL UNIT CHECK TEST CALIBRATION (*). ' SURVEILLANCE REOUIRED

1. Intermediate Range Monitors:

a.

Neutron Flux - High D

S/ U(b"". W(*

-R 2

0 W

R 3.'4. 5!

b.

Inoperative NA W(*

NA 2;3.4.5-

-y 2.-Average Power Range Monitor:

Y a.

Neutron Flux - High 15%

S S/ U(*"". W(*

Q 2

S W(")

Q 5-b.

Flow-Biased Simulated Thermal S

S/U("..Q W(*"". 0 1

Power - High c.

Fixed Neutron Flux'- High, 120%-

S=

S/U(". 0 W'".-Q

- 1:

' I d.

Inoperative NA Q("""'

NA~

'1. 2. 5

~ 1 e.

Downscale NA Q

NA

.1.-

. I' W

g f.

LPRM D-NA (g) 1, 2. 5 it

3. Reactor Vessel Steam Dome ~ Pressure'- High 25 Transmitter:

- NA("

' NA -

R"'

.1. 2 '

P Trip Logic:

0 0

-0

1. 2

. 1.

4. Reactor Vessel Water Level - Low. Level 1:

i Transmitter:

NA("

NA.

R"'

11. 2.

g Trip Logic:

D Q

Ql

1..: l

?

m xg TABLE 4.3.1-1 (Continued) n REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL

' OPERATIONAL CHANNEL FUNCTIONAL CHANNEL

. CONDITIONS IN WHICH'

~

FUNCTIONAL UNIT CHECK TEST CALIBRATION")

SURVEILLANCE REOUIRED

5. Main Steam Line Isolation Valve - Closure NA-Q R"

1 1:

6. Main Steam Line Radiation - High S

0"'

Ru).

1. 2' l~

7. Drywell Pressure - High Transmitter:

NA'"

NA R"'

1. 2 Trip Logic:

D Q

Q.

1. 2 l

[

8. Scram Discharge Volume Water Level - High NA Q

R

1. 2. 5'

9. Turbine Stop Valve - Closure NA Q

R" l '"'

l

10. Turbine Control Valve Fast Closure.

Control Oil Pressure - Low NA Q

R l'*) '

i

11. Reactor Mode Switch in Shutdown Position NA R.

NA 1.2.3.4.5.

12. Manual Scram

'NA Q

'NA

1. 2. 3. 4.- 5

13. Automatic Scram Contactors NA W

NA

'1.'2.

3. 4. 5 l' m

O6

?

i

.C

?

e -*

1

y TABLE 4 3.1-1 (Continuedr REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

(a): Neutron' detectors may be excluded from CHANNEL CALIBRATION.-

(b)

Within 24. hours prior.to startup.'if not performed within the previous-7 days.

-(c)

The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup. if not performed within the previous 7, days.

(d)

When changing from OPERATIONAL CONDITION 1-to OPERATIONAL CONDITION 2.

perform the recuired surveillance within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL C0tDITION 2. if not performed within the previous 7 days.

(e)

This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during

'0PERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

(f)

This calibration shall consist of the adjustment of the APRM flow-biased simulated thermal power channel to conform to a calibrated. flow signal, l.

(g)

The LPRMs shall be calibrated at least once per effective full power month (EFPM)-using the TIP system.

(h)

This calibration shall consist of a physical inspection and' actuation of these position switches.

(1)

Instrument alignment using a standard current source.

(j)

Calibration using a standard radiation source.

(k)

The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.

(1)

Transmitters are exempted from the quarterly channel calibration.

I (m)

Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

(n)

Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.

(o)

Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.

BRUNSWICK - UNIT 1 3/4 3-9 AmendmentNo.@78'W'We

I

. INSTRUMENTATION' 3/4.3 2 ISOLATION ACTUATION INSTRUMENTATION j

LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown J

in the Trip Setpoint column of Table 3.3.2-2.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

With an' isolation actuation instrumentation channel trip setpoint less a.

conservative than the value shown in the Allowable Values column of Table 3.3.2-2. declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b.

For any isolation actuation Trip Function with less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.2-1:

1.

Within one hour, verify sufficient channels remain OPERABLE or are placed in the tripped condition

to maintain automatic isolation actuation capability for the Trip Function, and 2.

Place the inoperable channel (s) in the tripped condition

within:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions common to RPS Instrumentation, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not common to RPS Instrumentation Otherwise take the ACTION required by Table 3.3.2-1.

c.

Deleted.

I d.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.2-1 for the Trip Function shall be taken.

I BRUNSWICK - UNIT 1 3/4 3-10 Amendment No. 33.78.730.177,175

d_

J t t INSTRUMENTATION" F

SURVEILLANCE REQUIREMENTS (Continued) 4 7

4.'3.2.3 The.150LATION SYSTEM RESPONSE TIME of each isolation function'shall be demonstrated to be within its limit at least once per 18 months.

Each test

shall include'at least one logic train such that both: logic trains are tested at I i

least once per 36 months and one channel.per function such that all channels are.

tested at least once every N times 18 months where N is the total number of 1

l redundart channels in a specific isolation. functions-l i

1 p

1 L

't

-0 i

k a

' Radiation mon.itors are

.mpt from response time testing.

i BRUNSWICK - UNIT 1 3/4 3-11 Amendment No. 69,115,122.

U1,175

TABLE 3l3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION I

NOTES When handling irradiated fuel in the secondary containment.

.(a) See Specification 3.6.3.1. Table 3.6.3-1 for valves in each valve group.

(b) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed as follows:

(1) For u) t6 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Trip Functions with a design that provides only one clannel per trip system.

(2)

For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all Trip Functions..

maintains isolation actuation capability. provided the Trip Function (c) Deleted.

l (d) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.

(e) With reactor steam pressure a 500 psig.

(f) Closes only RWCU outlet isolation valve.

l (g) Alarm only.

(h) Isolates containment purge and vent valves.

(1) Does not isolate E11-F015A.B.

~

(j) Does not isolate B32-F019 or B32-F020.

(k) Valve isolation depends upon low steam supply pressure coincident with high drywell pressure.

(1) Secondary containment isolation dampers as listed in Table 3.6.5.2-1.

i BRUNSWICK - UNIT 1 3/4 3-17a Amendment No. JM,175

E E

p; TABLE 4.3.2-1 n

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C5

' CHANNEL OPERATIONAL H

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SJRVEILLANCE REQUIRED

1. PRIMARY CONTAINMEN~ ISOLATION a.

Reactor Vessel Water Level -

1.

Law. Level 1 Transmitter:

NA

NA R

1. 2. 3 Trip Logic:

D Q

Q 1.~2. 3 l

2.

Low. Level 3 Transmitter:

NA

NA R

1. 2, 3 Trip Logic:

D Q

Q

1. 2. 3 l

o s*

b.

Drywell Pressure - High Y

Transmitter:

NA

'R

1. 2. 3

~-

Trip Logic:

D Q

Q

1. 2. 3 l

c.

Main Steam Line 1.

Radiation - High.

D Q

R(*

1. 2.-3 1

2.

Pressure - Low Transmitter:

NA

NA R

1-Trip L ic:

D Q

Q

.1 1

3.

Flow - Hi h Transmi ter:

NA

NA R(*'

1

e Trip Logic

D Q

Q 1

l' 8

d.

Main Steam Line Tunnel a

Condenser Vacuum gh Temperature - Hi NA Q

R

1. 2. 3

.I 8

e.

Low g

Transmitter:

NA ~

NA R'*'

1. 2

Trip Logic:

D Q

Q

.1. 2

l Ei f.

Turbine Building Area b

Temperature - High NA:

0 R

1. 2. 3c 1

-=

g.

Main Stack Radiation - High NA Q

.R 1.2.3' O~

h.

Reactor Building Exhaust

~

3 Radiation - High D

Q R

1. 2.'3 l

~

~-~

Si k

TABLE 4.3.2-1 (Continued) n ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAL Q

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION

, SURVEILLANCE REQUIRED

2. SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - High D

0 R

1.2.3.5, and'"

I b.

Drywell Pressure - High Transmitter:

NA

NA R

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 I

k' c.

Reactor Vessel Water Level -

Low. Level 2 P

Transmitter:

NA

NA R'b'

1. 2. 3 g

Trip Logic:

D Q

Q

1. 2. 3 1

3. REACTOR WATER CLEANUP SYSTEH ISOLATION a.

A Flow - High NA SA R

1. 2. 3 b.

Area Temperature - High NA SA R

1. 2. 3 c.

Area Ventilation A Temperature - High NA SA R

1. 2. 3 Fg d.

SLCS Initiation NA R

NA

1. 2 k

e.

Reactor Vessel Water Level -

3 Law. Level 2 Transmitter:

NA

NA R'*)

1. 2. 3 EF Trip Logic:

D Q

Q

1. 2. 3 l

g f.

A flw - High - Time Delay NA SA R

1. 2. 3 h

g.

Piping Outside RWCU Rooms Area NA SA R

1. 2. 3 Temperature - High m

g x

g-wrp; TABLE 4.3.2-1:-(Continued) x j.

' ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS H

c-z CHANNEL OPERATIONAL A

CHANNEL FUNCTIONAL CHANNEL -

-CONDITIONS IN WHICH-TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REOUIRED

~

4. CORE STANDBY COOLING SYSTEMS ISOLATION a.

High Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High i

Transmitter:

NA

NA R(b'

1. L 3 Trip Logic:

D 0

0

1. 2. 3 l

2.

HPCI Steam Line High Flow y

Time Delay Relay NA R

R

-1.-2, 3 cp 3.

HPCI Steam Supply Pressure - Low.

NA 0

R

1. 2. 3' I-U 4.

HPCI Steam Line Tunnel Temperature - High NA SA R

1. 2. 3 5.

Bus Power Monitor

~

NA R'

NA

1. 2. 3 6.

HPCI Turbine Exhaust.

NA

.0 Q

{1. 2. 3 I

Diaphragm Pressure - High k

7.

HPCI Steam Line Ambient g

Temperature - High NA SA R-1.-2. 3 8.

'HPCI Steam Line Area.

A Temperature - High NA

' SA R

1. 2. 3 z

P 9.

HPCI Equipment Area

. 1. 2. 3 Temperature.- High NA SA R

m.

?

10. Drywell Pressure - High X

Transmitter:

NA

LNA R(*)

1. 2. 3

?

Trip Logic -

D--

Q

^Q _

1. 2. 3 1-M

'^

TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS mB CHANNEL-OPERATIONAL 5;

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

' TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

SE.

b.

Reactor Core Isolation Cooling System Isolation-1.

RCIC Steam Line Flow - High Transmitter:

NA(

NA R

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 l

2.

RCIC Steam Line Flow - High Time Delay Relay NA R

R

'1. 2. 3 3.

RCIC Steam Supply Pressure - Low NA 0

0

1. 2. 3 1

4.

RCIC Steam Line Tunnel g

Temperature High NA SA R

1. 2. 3

[

5.

Bus Power Monitor NA R

NA

1. 2. 3

.8 6.

RCIC Turbine Exhaust Diaphragm Pressure - High NA 0

R

1. 2. 3 l'

7.

RCIC Steam Line Ambient Temperature - High NA SA R

1. 2. 3 8.

RCIC Steam Line Area A Temperature - High NA SA R

1. 2. 3 g

9.

RCIC Equipment Room Ambient g

Temperature - High NA SA R

1. 2. 3 2"

10. RCIC Equipment Room A Temperature - High NA SA R

1. 2. 3 5

11. RCIC Steam Line Tunnel Temperature - High

{

Time Delay Relay NA SA R

1. 2. 3' u*

12. Drywell Pressure - High Transmitter:

NA

NA R'b'

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 l

., y 4

~

.m rp; TABLE 4.3.2-1 (Continued) n ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C5 CHANNEL

'0PERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

~

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED-

5. SHUTDOWN COOLING SYSTEM ISOLATION a.

Reactor Vessel Water Level -

Law. Level.1 Transmitter:

NA*

NA.

R*

'1. : 2. 3 -

Trip Logic:

D

-Q Q

1. 2. 3 l

b.

Reactor Steam Dome Pressure.- High NA Q

R

1. 2. 3 I

u Y

El

=

a

.E h

1

-a

=.

.. =.

~

^h:

TABLE 13 2-1, (Continu4df ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

~ NOTES l

-(a)

The transmitter channel check is satisfied by the trip unit channel N

check. LA separate transmitter check is not required i

(b)

Transmitters are exempted from the quarterly channel' calibration.

l

-(c)-. Deleted, l'

L (d)

Testing shall verify-that the mechanical vacuum pump trips and the i

mechanical vacuum pump line valve closes.

'(e)

When reactor steam pressure = 500.psig.

t (f)

When handling irradiated fuel in the secondary containment.-

i i

l,

'I

.l

.I 4

BRUNSWICK - UNIT 1 3/4 3-32 Amendment No. 57,pp,J39,175

-INSTRUMENTATICd 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints l

set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2.

APPLICABILITY: As shown in Table 3.3.3-1.

t ACTION:

a.

With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2. declare the channel inoperable until the channel'is restored to OPERABLE status with its tri consistent with the Trip Setpoint value p setpoint adjusted.

b.

With one or more ECCS actuation instrumentation. channels inoperable, take the ACTION required by Table 3.3.3-1.

c.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION. and CHANNEL FUNCTIONAL TEST operations-during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3-1, 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4.3.3.3 The ECCS RESPONSE TIME of each ECCS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all'ch6nnels are tested at least once every N times 18 months, where N is the total number of redundant channels in a specific ECCS function.'

t r

BRUNSWICK - UNIT 1 3/4 3-33 Amendment No,97,p,JM,I7J,175

~

J) i

'7-p; TABLE 3.3.3-1 n

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

+

C5*

~

MINIMUM APPLICABLE I

OPERABLE CHANNELg GPERATIONAL TRIP FUNCTION PER TRIP FUNCTION,

CONDITIONS ACTION.I.

1. CORE SPRAY SYSTEM a.

Reactor Vessel Water Level.- Low. Level 3

- 4 l'.'2. 3. 4. 5 30.I b.-

Reactor Steam Dome Pressure.- Low (Injection Permissive) 4 1.2.3.4.5 30 l

c.

Drywell. Pressure - High 4

1. 2. 3 30 1 1

]

d.

Time Delay Relay 1/ pump 1.2.3.4.5-31 ' l g

e.

Bus Power Monitor (d) 1/ bus 1.2.3.4.5

~'32 -

2. LOW PRESSURE COOLANT INJECTION H0DE OF RHR SYSTEM a.

Drywell Pressure - High-4

1. 2. 3 30 i

b.

Reactor Vessel Water Level - Law. Level 3 4

1. 2. 3. 4*). 5*'

30 I

g c.

Reactor Vessel Shroud Level (Drywell Spray Permissive) 1/ valve

1. 2. 3. 4*'. 5*'

31 1

A d.

Reactor Steam Dome Pressure - Low (Injection Permissive)-

S A

- 1.

RHR Pump Start and LPCI Injection Valve Actuation 4

1.'2. 3. 4* 5**)'

30 l

2.

Recirculation Loop Pump Discharge Valve Actuation 4

1. 2. 3. 4*). 5 30 I

.E e.

RHR Pump Start - Time Delay Relay 1/ pump 1, 2. 3. 4*). 5*)

31 I

f.

Bus-Power Monitor'd)

~

O

. 1/ bus

---1,

2. 3, 4*'

5*)

-32

~

e m

e w e

= + -

-.-+.-,--m w--

.m

.-m

---u 2 -

c 4

-c vi 5

TABLE 3.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 5

MINIMUM-

-APPLICABLE l:

H OPERABLECHANNELg-OPERATIONAL PER TRIP FUNCTION '

TRIP FUNCTION

~ CONDITIONS.

ACTION l

~

3. HIGH PRESSURE COOLANT JfME.CTION SYSTEM a.

Reactor Vessel Water Level - Low. Level 2 4

1.'2. 3 30 -I b.

Drywell Pressure - High 4.

1.2.3

30 l

c.

- Condensate Storage Tank Level - Low 2(*)

1. 2. 3

' 33 -

5:'

d.

Suppression Chamber Water Level - High 2(

1. 2. 3 33 a

(f e.

Bus Power Monitor (*

1/ bus

.l. 2. 3.

.32 4 AUTOMATIC DEPRESSURIZATION SYSTEM a.

ADS Inhibit Switch 2

1. 2. 3 36 I b.

Reactor Vessel Water Level - Law. Level 3 4

1. 2.'3 36 it c.

Reactor Vessel Water Level --Low.- Level 1 2

1. 2. 3 36: I k

d.

ADS Timer 2

1. 2. 3

36. 1.

aa.f e.

Core Spray Pump Discharge Pressure - High (Permissive)L 4

1. 2.' 3 36 l g

f.

RHR-(LPCI MODE) Pump Discharge Pressure.- High (Permissive) 2/ pump

1. 2. 3 236 I k

g.

Bus Power Monitor (*

1/ bus-

1. 2. ' 3.

32

~

4,D e.,

-m w

..e-

.-,e m

1-m

TABLE 3.3 3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTIONS ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

I a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , verify sufficient channels remain OPERABLE or are placed in the tripped condition to maintain automatic ECCS actuation capability for the Trip Function, and b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . place all inoperable channels that do not

. cause the Trip Function to occur in the tripped condition.

Otherwise, declare the associated ECCS inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare I

the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify I

bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the associated ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Tri) Function requirement, place at I

least one inoperable channel in t1e tripped condition within one hour or declare the HPCI system inoperable.

I ACTION 34 - With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE to maintain actuation capability of either ADS Trip System A or ADS Trip System B and restore the inoperable channels to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, declare ADS inoperable.

BRUNSWICK - UNIT 1 3/4 3-37 Amendment No. 60,00,175 l

e TABLE'3.3 3-1 (Continued)-

EMERGENCV CORF COOLING SYSTEM ACTUATION INSTRUMENTATION n

E (a) When a. channel is placed in'an inoperable status solely for performance of

-required Surveillances.. entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the-Trip Function or the redundant Trip Function maintains ECCS actuation: capability.

(b) Not applicable when two core spray system subsystems are OPERABLE'per Specification 3.5.3.1.

(c) Provides signal to HPCI pump suction valves only.

(d) Alarm only.

f (e) Required when ESF equipment is required to be OPERABLE.

-(f) Deleted.

'l BRUNSWICK - UNIT 1 3/4 3-38 Amendment - No. 66,139,Jf 9,175

= -

m TABLE 4.3.3-1 m

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAL p

CHANNEL FUNCTIONAL CHA4NEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBMTION SURVEILLANCE REQUIRED 1.

CORE SPRAY SYSTEM a.

Reactor Vessel Water Level -

Low. Level 3 Transmitter:

NA)

NA R

1.2.3.4.5 Trip Logic:

D Q

Q 1.2.3.4.5 I

b.

Reactor Steam Dome Pressure - Low Transmitter:

NA

NA R

1.2.3.4.5 Trip Logic:

D Q

Q 1.2.3.4.5 I

w w

a c.

DrYWell Pressure - High A,

Transmitter:

NA

NA R'*'

1. 2. 3 Trip Logic:

0 Q

Q

1. 2. 3 1

w d.

Time Delay Relay NA R

R 1.2.3.4.5 e.

Bus Power Monitor NA R

NA 1.2.3.4.5 2.

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM g

a.

Drywell Pressure - High Transmitter:

NA

NA R(

1. 2. 3 ag Trip Logic:

D Q

Q

1. 2. 3 I

a b.

Reactor Vessel Water Level -

Low. Level 3 zo Transmitter:

NA

NA R'*'

1. 2. 3. 4'd' 5""'

g Trip Logic:

D Q

Q 1.2.3.4'd': 5' l

b c.

Reactor Vessel Shroud Level

?

Transmitter:

NA

NA R'*'

1. 2. 3. 4"). 5""

3 Trip Logic:

D Q

Q

1. 2. 3. 4"). 5 I

L E

L

4 i

E

q TABLE 4.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REOUIREMENTS EC CHANNEL OPERATIONAL CHANNEL FUNCTIONAL-CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION

' SURVEILLANCE' REQUIRED LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued)

d. Reactor Steam Dome Pressure - Low NA

NA R'"

1. 2. 3. 4'". 5'*

1. RHR Pump Start and LPCI-Injection Valve Actuation D

Q Q

1. 2. 3. 4'*

S'"

I ca 2.

Recirculation Loop Pump 2

Discharge Valve Actuation D

Q Q

1.'2. 3. 4'*. S'*

I

[

e. RHR Pump Start - Time Delay Relay NA R

R

1. : 2. 3, 4'*.' 5'S

f. Bus Power Monitor NA R

NA

1. 2. 3. 4'*. 5'*

3.

HIGH PRESSURE COOLANT INJECTION SYSTEM

a. Reactor Vessel Water Level -

Low. Level 2 Transmitter:

NA(

NA R'*

1. 2. 3 g

Trip Logic:

D Q

Q

1. 2. 3 l

a b Drywell Pressure - High a!

Transmitter:

NA

NA R'*

1.-2. 3 Trip Logic:

D Q

Q

1. 2. 3 1

o 5

c. Condensate Storage Tank Level - Low NA' Q

Q

1. ' 2. 3 -

.I f

d. Suppression Chamber Water Level - High NA

-Q' Q

1, 2. 3 '_

i y

e. Bus Power Monitor NA R

NA

1. 2. 3

A I

E 5

h TABLE 4.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS-C5 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL

. CONDITIONS IN WHICH

~

TRIP FUNCTION CHECK

' TEST CALIBRATION SURVEILLANCE REQUIRED

4. AUTOMATIC DEPRESSURIZATION SYSTEM a.

ADS Inhibit Switch D("

R NA

1. 2. 3 b.

Reactor Vessel Water Level -

Low. Level 3 Transmitter:

NA

NA R*'

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 i

a w

c.

Reactor Vessel Water Level -

1.

Low. Level 1 Transmitter:

NA

NA R*'

-1, 2. 3

~

Trip Logic:

D Q

Q

1. 2. 3 l

d.

ADS Timer NA R

R

1. 2. 3 e.

' Core Spray Pum) Discharge Pressure - Higi NA

-Q Q

1. 2. 3 l

f.

RHR (LPCI MODE) Pump Discharge--

g Pressure - High NA Q

Q 1.-2. 3 i

A g.

Bus Power Monitor NA R-NA

1. 2. 3

.!?

L M

L ea-+g w

e-

n t

+

r-Q

- TABLE 4.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS-C5 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

~

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE-REQUIRED'

5. LOSS OF POWER

a. 4.16 kv Emergency Bus NA NA R..

.1. 2. 3.- 4'*. S'*

Undervoltage (Loss of Voltage)

b. 4.16 kv Emergency Bus NA M'

R

1. 2. 3. '4'*. : 5'*

Undervoltage (Degraded a1 Voltage)

Y 8;

i g

a i

Ra h

(a) The transmitter channel. check is satisfied by the trip unit channel check. A separate transmitter check i

+

is not required.

k (b) Transmitters are ' exes)ted from the quarterly channel. calibration. _

- 1 J

-- E-(c) The. ADS' Inhibit Switcles shall be maintained in the' Automatic position.~

(d) Required when ESF equipment is required to be OPERABLE.

u--

2

.-a-rm-.

am

,,_a.__w

-,a.s,se v.

m,,,

,.e,

,-w,,

w-w y-

, +,,,,,, -.

g-

ym_,

,,w.w

,w--

,.y_.

3g.,

,,,,3.gw

m i

TABLE 3.3.4-1 (Continued)

CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION NOTIS (a) When a channel is placed in an inoperable status solely for performance of-required Surveillances, entry into associated ACTIONS may be delayed for up.

to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains control rod withdrawal block capability.

(b) This function is bypassed if detector is reading >100 cps or the.IRM channels are on range 3.or higher.

(c) This function is bypassed when the associated IRM channels are on range 8 1

or higher.

(d) A total of 6 IRM instruments must be OPERABLE.

i (e) This function is bypassed when the IRM channels are on range 1.

(f) When (1) THERMAL POWER is greater than or ecual to 30% of RATED THERMAL POWER and less than 90% of RATED THERMAL P0kER and MCPR is less than 1.70.

or (2) THERMAL POWER is greater than or equal to 90% of RATED THERMAL POWER and MCPR is less than 1.40.

(g) With any control rod withdrawn. Not applicable to control rods removed per 1

Specification 3.9.10.1 or 3.9.10.2.

(h) This signal is contained in the Channel A logic only.

[

i f

I l

BRUNSWICK - UNIT 1 3/4 3-49 Amendment No. Y77,yf7,175 i

l

1 sg TABLE 4.3.4-1 C

CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REOUIREMENTS 5

CHANNEL OPERATIONAL ~

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH c

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE0UIRED-5 H

1.

APRM a.

Upscale (Flow Biased)

NA S/U(

~

b.

Inoperative NA S/U('"'IQ("

R* "

1 I

.Q NA

1. 2. 5 c.

Downscale NA S/U(')

d.

Upscale (Fixed)

NA S/U('"'IQ """

NA 1 ~

l

.0 R(

2. 5 2.

ROD BLOCK HONITOR a.

Upscale NA S/U(".Q R(

l

I b.

Inoperative NA S/U(.0 NA l('

c.

Downscale NA S/U(.0 R(

1S) l 3.

SOURCE RANGE MONITORS o

a.

Detector not full in NA S/U((*' W(*

NA

2. 5 2

b.

Upscale NA S/U( lW(*

NA

2. 5 a

c.

Inoperative NA S/U(.W(*

NA

2. 5 d.

Downscale NA S/U

.W(*

NA

2. 5 4.

INTERMEDIATE RANGE MONITORS W[g('".W(*

NA 2

a.

Detector not full in-NA S

NA NA 5

b.

Upscale NA S/U(

.W'd' M-2 NA

.W NA 5

m c.

Inoperative NA S/U(".W(*

NA 2

5, NA W

M 5

a.

2 d.

Downscale.

NA S/U(.W(*

NA 2

Ei.

NA W

NA 5

5.

SCRAM DISCHARGE VOLUME g

gg a.

Water Level - High NA Q.

R

~ 1. 2. 5*) ~

- ~

M L

.M c

a

..?

L TABLE 4.3.5 5-1 e

CONTR0_ ROOM EMERGENCY VENTILATION SYSTEM INSTRUliENTATION SURVEILLANCE REQUIREMENTS CHANNEL I

' FUNCTION.

CHANNEL FUNCTIONAL

. CHANNEL-CHECK TEST CALIBRATION 1.

CHLORINE ISOLATION:

,.i a.

Local NA-M A

Detect. ion Trip ~

System-b.~

Remote NA M

A Detection Trip System i

2. RADIATION PROTECTION-Control Building 0

0 R

I Air Intake

3. CONTROL ROOM ENVELOPE SM0KE PROTECTION:

a.

Zone 4 NA ~

6 months (a).

b.

Zone 5 NA 6 months (a) 3

-i

.(a)

See Surveillance Requirement 4.7.2.d.2 I

.t I

f BRUNSWICK - UNIT 1 3/4 3-64c-Amendment No.J57,J7#,175L

~

. -. - - ~

INSTRUMENTCION x

3/4 3.6 ATWS RECIRCULATION PUMP TRIP (RPT) SYSTEM INSTRUMENTATION LIMITING CONDITION'FOR OPERATION 3.3.6.1 The ATWS-RPT system instrumentation channels shown in Table 3.3.6.1-1 I shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY: OPERATIONAL CONDITION 1.

ACTION:

a.

With an ATWS-RPT system instrumentation trio setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6.1-2, declare the instrument channel inoperable until the t

channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels Per Trip System requirement:

1.

Verify that a sufficient number of channels remain OPERABLE or are in the tri aped condition to maintain ATWS-RPT trip capability for both Trip unctions within one hour, and 2.

Restore the inoperable channel (s) to OPERABLE status or place the inoperable channel (s) in the tripped condition within 14 days.

c.

With trip capability for one ATWS-RPT Trip Function not maintained, restore trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

With trip capability for both ATWS-RPT Trip Functions not maintained, restore trip capability for one Trip Function within one hour.

Otherwise, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.6.1.1 Each ATWS-RPT system instrumentation channel shall be demonstrated I

OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST. and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.6.1-1.

4.3.6.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of-all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

l l

BRUNSWICK - UNIT 1 3/4 3-88 Amendment No. JJp,J N,175

TABLE 3.3'6 1-1L ATWS RECIRCULATION' PUMP TRIP SYSTEM INSTRUMENTATION MINIMUM TRIP FUNCTION 0PERABLECHANNE(S PER TRIP SYSTEM *)

1.

Reactor Vessel Watsr Level - Low.-Level 2 2

2.

Reactor Vessel Pressure - High 2

l l

t

- i 1

When a channel is placed in an inoperable status solely for performance of' required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains ATWS-RPT capability.

'8RUNSWICK - UNIT 1 3/4 3-89 Amendment No. 139,175 1

. J

-, ~.

-1

~'

~ TABLE af3 6.1-'1.

ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-

' CHANNEL

. CHANNEL ~

FUNCTIONAL ~

CHANNEL

~

. TRIP FUNCTION CHECK TEST CALIBRATION, Ll.

Reactor Vessel Water Level -

Low. Level 2 Transmitter:

NA")

NA -

R*

Trip Logic:

D

'O O

l-

-2.

Reactor Vessel Pressure - High

~

Transmittsr:

NA"'

NA-

.R*

Trip Logic:

D Q'

Q

' l' i

l i

4 l

i o

')

'l The transmitter channel check is satisfied by the tra unit channel check.

A separate transmitter check is not required.

j Transmitters are exempted from the quarterly channel calibration.

I BRUNSWICK - UNIT 1 3/4 3-91 Amendment No. 49,175;

.t s

INSTRUMENTATION 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATICN LIMITING CONDITION FOR OPERATION 3.3.7 The reactor core isolation cooling (RCIC) system actuation instrumentation channels shown in Table 3.3.7-1 shall be OPERABLE with their I

trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.7-2.

APPLICABILITY: OPERATIONAL CONDITIONS 1. 2, and 3 with reactor steam dome pressure greater than 113 psig.

ACTION:

With a RCIC system actuation instrumentation channel trip setpoint a.

less conservative than the value shown in the Allowable Values column of Table 3.3.7-2. declare the channel inoperable until the channel is-restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b.

With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.7-1.

SURVEILLANCE REQUIREMENTS 4.3.7.1 Each RCIC system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and C N NEL CALIBRATION operations at the frequencies shown in Table 4.3.7.1-1.

4.3.7.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

I BRUNSWICK - UNIT 1 3/4 3-92 Amendment No. ypp.175

R E

R TABLE 3.3.7-1 n

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION

.E.

MINIMUM

~

OPERABLECHANNEl.,j FUNCTIONAL UNIT PER TRIP SYSTEM' ACTION

1. Reactor Vessel Water Level - Low. Level 2 2

50-

2. Reactor Vessel Water Level - High 2"

51

3. Condensate Storage Tank Water Level - Low")

2"'

52 oE Y8 (a) When a channel is placed in an inoperable status solely for performance of required Surveillances entry -

into associated ACTIONS may be delayed as follows:

kg (1) For up.to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Unit 2.

Rg.

(2).For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Units 1 and 3. provided the Functional Unit maintains RCIC actuation capability.

zO i

(b) One trip system with two-out-of-two logic.

g (c) One trip system with one-out-of-two logic.

L (d) Provides signal to RCIC pump suction valves only.

s

TABLE 3.3.7-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM

' ACTUATION INSTRUMENTATION

~

ACTIONS ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system. ) lace the inoperable channel (s) and/or.

that trip system in tie tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or I declare the RCIC system inoperable, b.

For both trip systems, declare the RCIC system inoperable.

CTION 51 - With the number of OPERABLE channels one less than required by-the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channel (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise declare the RCIC system inoperable.

ACTION 52 - With the number of OPERABLE channels less than required by the tiinimum OPERABLE Channels per Tria System requirement, place at least one inoperable channel in t1e trip)ed condition within 24-hours or declare the RCIC system inopera)le.

P BRUNSWICK - UNIT 1 3/4 3-94 Amendment No. Up,175

~

r m

l E

p; TABLE 4.3.7.1-1 x

REACTOR CORE-ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS' Eq CHANNEL CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL UNIT CHECK TEST CALIBRATION 1.

Reactor Vessel Water Level - Law. Level 2 Transmitter:

NA

NA R'b' Trip Logic:

D 0-0 l

2.

Reactor Vessel Water Level - High

~

R'"

Transmitter:

NA

NA' Trip Logic:

D Q

Q l

a2 3.

Condensate Storage Tank Level - Low NA Q

Q l

a h

N i

A Eb (a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check y

is not required.

5 (b) Transmitters are exempted from the quarterly channel calibration.

.1 w

g 2 m e.

e es As

-- "- 12

'3/4: 3 INSTRUMENTATION

. BASES

=3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:

a.

Preserve the integrity of the fuel cladding.

b.

Preserve the integrity of the reactor coolant system, Minimize'the energy which must be adsorbed following a loss-of-coolant-c.

accident, and prevent inadvertent criticality.

This specification )rovides the limiting conditions for operation necessary to preserve tie ability of the system to perform its intended' I

function even during periods when instrument channels may be out of service because of maintenance. When necessary, one channel may be made inoperable for brief intervals to conduct the required surveillance tests.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30851P-A. " Technical Specification Improvement Analyses for BWR Reactor Protection System." Harch 1988 and MDE-81-0485. Rev. 1. " Technical Specification Imarovement Analysis for the Reactor. Protection System for Brunswick Steam Electric Plant. Units 1 and 2." August 1994, as modified by' BWROG-92102. Letter from C. L. Tully (BWROG) to B. K. Grimes (NRC)

"BWR Owners' Group (BWROG) Topical Reports on Technical Specification Improvement Analysis for BWR Reactor Protection Systems - Use for Relay and Solid State Plants (NEDC-30844 and NEDC-30851P)." November 4, 1992.

The reactor protection system is made up of two independent trip systems.

There are usually four channels to monitor each parameter, with two in each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both trip systems will produce a reactor scram.

The system meets the intent of IEEE-279 for nuclear power plant protection systems.

1 The measurement of response time at the specified frequencies provides assurance that the )rotective, isolation, and emergency core cooling functions associated with eac1 channel are completed within the time limit assumed in the accident analysis.

No credit was taken for those channels with response

)

times indicated as not applicable.

i Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements, provided such tests demonstrate the total 1

channel response time as defined. Sensor response time verification may be demonstrated by either 1) inplace, onsite, or offsite test measurements, or 2) utilizing replacement sensors with certified response times.

The bases for the trip settings of the reactor protection system are discussed in the bases for Specification 2.2.

BRUNSWICK - UNIT 1 B 3/4 3-1 Amendment No.175

m INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures ~ the efSctiveness of the instrumentation used to mitigate the consequences of accideat.s by prescribing the trip settings for isolation of the reactor systems. When necessary. one channel ma inoperable for brief intervals to conduct required surveillance. y be Some of the' trip settings have tolerances explicitly stated where both the high and low values are critical and may have a substantial effect on safety.

The setpoints of other instrumentation where only the high or low end of the setting has a direct bearing on the safety, are established.at a level away from the normal o systems involved.perating range to prevent inadvertent actuation of the 1

I Specified surveillance intervals and allowed out-of-service times-were established based on the. reliability analyses documented in GE reports NEDC-30851P-A. Supplement 2. " Technical Specification Improvement Analysis for j

BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation." March 1989 and NEDC-31677P-A. " Technical Specification Improvement Analysis' for BWR Isolation Actuation Instrumentation." July 1990 as modified by OG90-579-32A.

l Letter to Millard L. Wohl (NRC) from W. P. Sullivan and J. F. Klapproth (GE).

" Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation Instrumentation Analysis." June 25. 1990 and supplemented by GE letter report GENE-A31-00001-02. " Assessment of Brunswick Nuclear Plant Isolation Actuation Instrumentation Against NEDC-31677P-A Bounding Analyses."

August 1994.

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the operator's ability to control. This specification provides the tri) point I

settings that will ensure effectiveness of the systems to provide tie design protection. Although the instruments are listed by system, in some cases the same instrument is used to send the start signal to several systems at the same time. The out-of-service times for the instruments are consistent with the requirements of the specifications in Section 3/4.5.

Specified surveillance intervals and allowed out-of-service times were l

established based on the reliability analyses documented in GE reports NEDC-30936P-A Parts 1 and 2. "BWR Ownt:rs' Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)." December 1988 and RE-011. Rev.1. " Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Brunswick Steam Electric Plant. Units 1 ?, 2." August 1994.

as modified by OG90-319-320. letter from W. P. Sullivan and J. F. Klapproth i

(GE) to Millard L. Wohl (NRC). " Clarification of Technical Specification Changes Given in ECCS Actuation Instrumentation Analysis." March 22. 1990.

l 1

BRUNSWICK - UNIT 1 B 3/4 3-2 Amendment No.175 l

t

x+

y-INSTRUMENTATION

. BASES 3/4.3.4 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4. Rod Program Controls, and Section 3/4.2.

Power Distribution Limits. The trip lo the inputs'will result in a rod block. gic is arranged so that a trip in any one of Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE re> ort NEDC-30851P-A.

Supplement 1. " Technical Specification Improvement Analysis for BdR Control Rod Block Instrumentation." October 1988.

3/4.3.5 MONITORING INSTRUMENTATION 3/4.3.5.1 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capabili is required to permit comparison of the measured response to that used in the desi basis for the facility.

BRUNSWICK - UNIT 1 B 3/4 3-2a Amendment No. 175 l

INSTRUMENTATION BASES 3/4.3.5 5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

Surveillances (Continued) instrumentation continues to o)erate properly between each CHANNEL CALIBRATION. The CHANNEL CHECC frequency is consistent with that performed for other radiation monitors with isolation functions.

The CHANNEL FUNCT.IONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the radiation actuation instrumentation.

The quarterly frequency of the L

CHANNEL FUNCTIONAL TEST was established based on Reference 7 and is consistent with that performed for other radiation monitors with isolation functions.

The CHANNEL CALIBRATION verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to ensure consistency with the system assumptions (Reference 5).

The frequency of the calibration is consistent with the frequency of calibration of other radiation monitors with isolation functions.

Chlorine Protection The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the s)ecific actions to be satisfied by the chlorine isolation instrumentation. T1e monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent with the testing frequencies performed by other utilities with this type of instrumentation.

The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the sensor when the sensor is replaced. The test verifies the calibration of the existing sensor prior to removal and performs an installation calibration of the new sensor, including a complete channel calibration with the new sensor installed, to verify the channel responds to the measured parameter within the necessary range and accuracy. The CHANNEL CALIBRATION leaves the channel adjusted to ensure consistency with the system assumptions (Reference 6).

The chlorine detectors use an am)erometric sensor consisting of a platinum l

cathode and silver anode joined )y an electrolytic salt bridge all enclosed 1

in a permeable membrane. This design eliminates the majority of the maintenance required on previous detectors.

The detectors have been in service at other facilities and have provided reliable service.

The annual replacement and calibration are based on a manufacturer recommendation.

The adequacy of the replacement interval has been confirmed through discussions with other utilities.

Smoke Protection The CHANNEL FUNCTIONAL TEST for the Smoke Protection instrumentation is consistent with the testing performed in accordance with the existing Fire Detection Instrumentation requirements.

CHANNEL CALIBRATION is performed in accordance with the requirements of the CREVS specification (4.7.2).

BRUNSWICK - UNIT 1 B 3/4 3-3d Amendment No. 167,175

INSTRUMENTATION BASES.

3/4.3.5.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

References

,1. 10 CFR 50. Appendix A. General Design Criterion 19.-Control Room.'

2. Regulatory Guide 1.95. Revision 1. Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release.

3. Updated FSAR. ' Brunswick Steam Electric Plant. Units 1 & 2.

4. NUS-3697. Revision 2. February 1983. Control Building Habitability Analysis.

5. CP&L Calculation 01534A-248. Control Room Radiation Monitor Setpoint Evaluation.

6. BNP Design Basis Document (DBD)-37. Control Building Heating. Ventilation, and Air Conditioning System.

7. GENE-770-06-1-A. " Bases For Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

BRUNSWICK - UNIT 1 B 3/4 3-3e Amendment No. J57,175

~.

INSTRUMENTATION BASES-3/4.3.6 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The ATWS recirculation pump trip system has been added at the suggestion of ACRS as a means of limiting the consecuences of the unlikely occurrence of a failure to scram during an anticipatec transient The response of the plant to this aostulated event falls within the envelobe of study events given in General Electric Company Tropical Report NED0-10349. dated March, 1971.

Specified surveil]ance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-1-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications."

December 1992.

3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report GENE-770-06-2P-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

t

)

l l

l BRUNSWICK - UNIT 1 B 3/4 3-6 Amendment No.68,175 l

1

.pn ath,4,?*f

- p

/

UNITED STATES -

> I ~'

'E NUCLEAR REGULATORY COMMISSION

) '

--f g

- WASHINGTON, D.C. 20555-0001

.j

- - - - /

4, CAROLINA POWER & LIGHT COMPANY. et al.

i DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT.' UNIT-2

, AMENOMENT TO FACILITY OPERATING LICENSE-Amendment No. 206 License No. DPR-62 1

1.

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

1 A.

The application for amendment filed by Carolina Power & Light Company (the licensee), dated October 28, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set l

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:

-i 1

T' F

I i

e 4

y-~

'(2)'

Technical Specifications The Technical-Specifications contained in Appendices A and B, as -

revised through Amendment No. 206, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

-3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.

)

FOR THE NUCLEAR REGULATORY COMMISSION

/ \\s 3s t

3 i

(ULLLtd Q~h William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of. Nuclear. Reactor Regulation

(

Attachment:

Changes to the Technical Specifications Date of Issuance: March 30, 1995 t

+

k L

r t

ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. 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.

Remove Paaes Insert Paaes 3/4 3-1 3/4 3-1 3/4 3-la

'3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-5 3/4 3-5 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-17a 3/4 3-17a 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 4

3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32

\\

3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 g

3/4 3-43 3/4 3-43 3/4 3-44 3/4 3-44 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-46 3/4 3-49 3/4 3-49 3/4 3-51 3/4 3-51 3/4 3-64c 3/4 3-64c 3/4 3-88 3/4 3-88 3/4 3-90 3/4 3-90 3/4 3-92 3/4 3-92 3/4 3-93 3/4 3-93 3/4 3-95 3/4 3-95 3/4 3-98 3/4 3-98 3/4 3-99 3/4 3-99 3/4 3-100 3/4 3-100 3/4 3-101 3/4 3-101 3/3 3-103 3/4 3-103 B 3/4 3-1 B 3/4 3-1 B 3/4 3-2 8 3/4 3-2 B 3/4 3-2a B 3/4 3-3d B 3/4 3-3d B 3/4 3-3e B 3/4 3-3e B 3/4 3-6 B 3/4 3-6 8 3/4 3-7 B 3/4 3-7

~3/J 3 INSTRU9ENTATION 3/4.3!1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

. LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum. the reactor protection system instrumentation channels shown in Table'3.3.1-1 shall be OPERABLE.

Set points and interlocks are given:

in Table 2.2.1-1.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION':

With one' channel less than the Minimum Number of OPERABLE Channels per a.

Trip System required by Table 3.3.1-1-in one or more Functional Units, place the inoperable channel and/or that trip system in the tripped condition

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With two or more channels less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.1-l' in one or more Functional Units:

1.

Within one hour, verify sufficient channels remain OPERABLE or in.

i the tripped condition

to maintain trip capability in the Functional Unit, and i

2.

Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the inoperable channel (s) in one trip system and/or that trip system ** in the tripped condition *, and 3.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other trip system to an OPERABLE status or place them in the tripped condition *.

1 Otherwise, take the ACTION required by Table'3.3.1-1 for the Functional Unit.

c.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.1-1 for the Functional Unit'shall be taken.

This ACTION a) plies to that tri) system with the most inoperable channels: if )oth trip systems lave the same number of inoperable channels. the ACTION can be applied to either trip system.

BRUNSWICK - UNIT 2 3/4 3-1 Amendment No. 195,797,206

e 1

3/4 3 INSTRUMENTATICN 3/4 3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.1.1.Each reactor protection system instrumentation channel shall be demonstrated OPERABLE ay the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function'shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function.

Neutron detectors are exempt from response tiime testing.

l i

BRUNSWICK - UNIT 2 3/4 3-la Amendment No. 206

r; TABLE 3.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION Eq APPLICABLE MINIMUM NUMBER m

OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)

ACTION

1. Intermediate Range Monitors:

a.

Neutron Flux - High 2. S'b' 3

1

3. 4 2

2 b.

Inoperative

2. 5 3

1 y

3. 4 2

2

2. Average Power Range Monitor a.

Neutron Flux - High. 15%

2. S'*)

2 3

b.

Flow Biased Simulated Thermal 1-2 4

Power - High c.

Fixed Neutron Flux - High. 120%

1 2-4 d.

Inoperative-

1. 2. 5 2-5 e.

Downscale 1

2 4

[

f.

LPRM

1. 2. 5 (c)

NA a

3. Reactor Vessel Steam Dome Pressure - High

1. 2'*

2 6

[

4. Reactor Vessel Water Level - Low. Level.1

1. 2 2-6 O

[g

5. Main Steam Isolation valve - Closure 1

4 4

h

6. Main Steam Line Radiation - High

- 1, 2'* '

2 7

M

.?

E!

a

.. ~ _. - -,.

. ~ -

p Ey

q TABLE 3.3.1-1 (Continued) n REACTOR PROTECTION SYSTEM INSTRUMENTATION EA APPLICABLE-MINIMUM NUMBER y

OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)

. ACTION.

7.

Drywell-Pressure - High

1. 2(

2 6'

8.

Scram Discharge Volume Water Level - High

1. 2. 5("

2 5

9.

Turbine Stop Valve - Closure l'O 4

8 10.

Turbine Control Valve Fast Closure.

Y Control Oil Pressure - Low.

l'8 2

8 11.

Reactor Mode Switch in Shutdown Position 1.2.3.4.5 1

9 12.

Manual Scram 1.2.3.4.5 1

10 13.

Automatic Scram Contactors 1.2.3.4.5 2

10 I

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n

b TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 10 -

In OPERATIONAL CONDITION 1 or 2. be in at least HOT-SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In 0PERATIONAL CONDITION 3 or 4. lock the reactor mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5. suspend all-o)erations involving CORE ALTERATIONS or positive reactivity c1anges and fully insert all insertable control rods within one hour.

NQIES (a) When a channel is placed in an inoperable status solely-for performance of required Surveillances, entry into associated ACTIONS may be delayed for-up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Functional Unit maintains RPS trip capability.

(b) The " shorting links" shall be removed from the RPS' circuitry prior to and during the time any control rod is withdrawn

and during shutdown margin l

demonstrations.

(c) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.

(d) These-functions are not required to be OPERABLE when the reactor. pressure vessel head is unbolted or removed.

(e) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(

(f) With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(g) These functions are bypassed when THERMAL POWER is less than 30% of RATED THERMAL POWER.

Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

BRUNSWICK - UNIT 2 3/4 3-5 Amendment No.59,EJ,769,206

't

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TABLE 4.3.1-1 n

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS C*

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN hHICH FUNCTIONAL-UNIT CHECK

-TEST

' CALIBRATION (

' SURVEILLANCE REQUIRED

1. Intermediate Range Monitors:

a.

Neutron Flux - High D

S / U("". W(*

R 2

D W

R 3.~ 4.

5--

b.

Inoperative NA W(*

NA 2.3.4.5

2. Average Power Range Monitor:

g W("y("""). W(*

O

-2 a.

Neutron Flux - High 15%

S S/

4, S

Q 5

b.

Flow-Biased Simulated Thermal S

S/U(*). O W('"". Q 1

Power - High S

c.

Fixed Neutron Flux - High. 120%

S S/U ). Q W(, Q 1

-l-d.

Inoperative NA Q("""'

NA

1. 2. 5

'l f

e.

Downscale NA Q

NA 1

l o.

f.

LPRM D

NA (g)

'1. 2. 5

3. Reactor Vessel Steam Dame Pressure --High 2

P Transmitter:

NA"'

NA R("

1. 2 gg Trip Logic:

D 0

-0

1. 2.

.1

I 4.. Reactor Vessel Water Level - Low. Level 1 L

Transmitter:

NA"'

NA R(

1. 2.:

c Trip Logic:

D 0-Q 1, 2 l'

LE

.n r

a n

.. +.

.n,:

. + - - +

,,,, + ~

I 7;

TABLE 4.3.1-1 (Continued) n REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Eq CHAhM L OPERATIONAL 0 CHANNEL FUNCTIONAL CHANNEL.

. CONDITIONS IN WHICH m

FUNCTIONAL UNIT-CHECK TEST CALIBRATION (*)

SURVEILLANCE REOUIRED 5.

Main Steam Line Isolation Valve - Closure NA Q

R*

1

-l 6.

Main Steam Line Radiation - High S

Q"'

Rui 1, 2 1

7.

Drywell Pressure - High Transmitter:

NA*

NA R"'

1. 2 y

Trip Logic:

0 Q

Q

1. 2 l

[

8.

Scram Discharge Volume Water Level - High NA Q

R

1. 2. 5 9.

Turbine Stop Valve - Closure NA Q

R*

l' '

i 10.TurbineControlValveFastCiosure.

Control Oil Pressure ' Low NA

.Q R

- l' '

I

11. Reactor Mode Switch in Shutdown Position.

NA

-R

.NA 1.-2, 3. 4. 5 g

12. Manual Scram NA

-Q NA 1.2.3.4.5 8a

13. Automatic Scram Contactors NA W

NA 1.2.3.4.5l-E E-=

~

M

.U.

TABLE 1 3 1-1-(Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

.N_QTf,3 (a)

Neutron detectors may be excluded from. CHANNEL CALIBRATION.

'(b)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup. if not performed within the previous 7 days.

(c)

The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup. if not performed within the -

previous 7 ' days.

(d)

When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2.

perform the required surveillance within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'after entering-OPERATIONAL CONDITION 2. if not performed within the previous 7 days.

(e)

This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

(f)

This calibration shall consist of the adjustment of the APRM flow-biased simulated thermal power channel to conform to a calibrated flow signal.

I (g)

The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.

(h)

This calibration shall consist of a physical inspection.and actuation of these position switches.

(i)

Instrument alignment using a standard current source.

(j)

Calibration using a standard radiation source.

(k)

The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.

(1)

Transmitters are exempted from the quarterly channel calibration.

1 (m)

Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

(n)

Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance i

provided all control rods are fully inserted and the vessel head bolts j

are tensioned.

(o)

Surveillance is not required when THERMAL POWER is less than 30% of 1

RATED THERMAL POWER.

i

-BRUNSWICK - UNIT 2 3/4 3-9 Amendment No. 33,J05,J60,793, 205,206

INSTRUMENTATION 3/4.3 2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

With an ' isolation actuation instrumentation channel trip setpoint less a.

conservative than the value shown in the Allowable Values column of Table 3.3.2-2. declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

For any isolation actuation Trip Function with less than the Minimum Number of OPERABLE Channels per Trip System required by Table 3.3.2-1:

1.

Within one hour, verify sufficient channels remain OPERABLE or are placed in the tripped condition

to maintain automatic isolation actuation capability for the Trip Function, and 2.

Place the inoperable channel (s) in the tripped condition

within:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions common to RPS Instrumentation, and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not common to RPS Instrumentation Otherwise, take the ACTION required by Table 3.3.2-1.

c.

Deleted.

I d.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases. if the inoperable channel is not restored to OPERABLE status within the required time, the ACTION required by Table 3.3.2-1 for the Trip Function shall be taken.

I BRUNSWICK - UNIT 2 3/4 3-10 Amendment No. 160,292,206

.INSTRUMENTATIO4 l SURVEILLANCE REQUIREMENTS (Continuedt 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation function'shall be

' demonstrated to be within-its limit at'least once per 18 months..Each test-shall include at least one logic train'such that both logic trains are tested at l

?

least once per 36 months and one channel per function such that all channels are

. tested at least once every N times 18 months, where N is the. total number of

. redundant channels in a specific isolation function.

')

I

.l l

' Radiation monitors are exempt from response time: testing.

l i

'I i

1 I

)

i i

BRUNSWICK - UNIT 2 3/4 3-11 No #$,78,97.J31..

1 W nde n"ffe,297,206 JAE JAS,;

'i

1 TABLE 3 3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION

@lTf,5 When handling Irradiated fuel in the secondary containment:.

(a) See Specification 3.6.3.1,. Table 3.6.3-1 for valves in each valve group.

(b): When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed as follows:

(1) For up to'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for Trip Functions with a design that provides-only one channel per trip system.

(2) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for all Trip Functions, provided the Trip Function maintains isolation actuation capability.

(c) Deleted.

1 (d) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.

(e) With reactor steam pressure a 500 psig.

(f) Closes only RWCU outlet isolation valve.

(g) Alarm only.

(h)

Isolates containment purge and vent valves.

(i) Does not isolate E11-F015A.B.

(j) Does not isolate B32-F019 or B32-F020.

(k) Valve isolation depends upon low steam supply pressure coincident with high drywell pressure.

(1) Secondary containment isolation dampers as listed in Table 3.6.5.2-1.

BRUNSWICK - UNIT 2 3/4 3-17a Amendment No. 179,206

3 E

c5 TABLE 4.3.2-1 r

5-ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

CHANNEL

' OPERATIONAL 5

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH...

H TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REOUIRED no

1. PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level -

1.

Low. Level 1 Transmitter:

NA*

NA R*-

'1.~~2. 3 Trip Logic:

D 0

0

1. 2. 3 1.

2.

Low. Level 3 Transmitter:

NA*

NA R*. -

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 l-a1 b.

Drywell Pressure - High ag, Transmitter:

NA*

NA R*

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 c.

Main Steam Line

. I N

1.

Radiation - High D

Q R*

1. 2. 3 i~

2.

Pressure - Low Transmitter:

NA*

NA R(b) 1 Trip Logic:

D Q

Q

_1 1

3.

Flow - High g

Transmitter:

NA*

NA' R*

1 Trip Logic:

D Q

Q.

1 l

2g 4.

Flow - High D

0 0

2. 3.

I A

d.

Main Steam Line Tunnel g

Temperature - High NA Q

R

1. 2. 3 1

e.

Condenser Vacuum - Low m%

Transmitter:

Nq*

NA R*-

1. 2*

Pn?

Trip Logic:

D-Q Q

1. 2*

l 4

f.

Turbine Building Area

.k Temperature - High NA Q

R 1, 2. _ 3 1-R g.

-Main Stack Radiation - High NA Q

R

1. 2. 3 k

h.

Reactor Building Exhaust t

Radiation - High D

Q R

1. 2. 3 l

k

Eg TABLE 4.3.2-1 (Continued) n ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REOUIREMENTS 5

CHANNEL OPERATIONAL H

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH N

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

2. SECONDARY CONTAINMENT ISOLATION a.

Reactor Building Exhaust Radiation - High D

Q R

1.2.3.5. and("

I b.

Drywell Pressure - High Transmitter:

NA(

NA R(b'

1. 2. 3 Trip Logic:

D Q

0

1. 2. 3 I

w E

c.

Reactor Vessel Water Level -

o Low. Level 2 k

Transmitter:

NA(*)

NA R(b'

1. L 3

. Trip Logic:

D 0

0

1. 2. 3 1

m

3. REACTOR WATER CLEANUP SYSTEM ISOLATION a.

A Flow - High NA SA R

1. 2. 3 b.

Area Temperature - High NA SA R

1. 2. 3 f

c.

Area Ventilation A Temperature - High NA SA R

1. 2. 3

{

d.

SLCS Initiation NA R

NA

1. 2 e.

Reactor Vessel Water Level -

Low. Level 2 Transmitter:

NA(')

NA R(6)

1. 2. 3 g

Trip Logic:

D Q

Q

1. 2. 3 1

'g f.

A Flow - High - Time Delay NA SA R

1. 2. 3 g.

Piping Outside RWCU Rooms Area NA SA-R

1. 2. 3 Temperature - High

E m

~

E h;q TABLE 4.3.2-1 (Continued) n ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C5 CHANNEL OPERATIONAL H

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH'.

N TRIP FUNCTION CHECK TEST

. CALIBRATION SURVEILLANCE REQUIRED

4. CORE STANDBY COOLING SYSTEMS ISOLATION a.

High Pressure Coolant Injection System Isolation 1.

HPCI Steam Line Flow - High Transmitter:

NA(*)

NA R(b' 1, 2. ' 3 Trip Logic:

D Q

-Q 1, 2. 3

'I w

2.

HPCI Steam Line Flow - High.

2 Time Delay Relay NA R

R

1. 2.13 3.

HPCI Steam Supply Pressure - Low-NA Q

R

1. 2. 3 l'

4.

HPCI Steam Line Tunnel Temperature --High

-NA-SA R

1. 2. 3 5.

Bus Power ?ionitor NA R

NA

1. 2.-3 6.

HPCI Turbine Exhaust Diaphragm Pressure - High NA:

0 0

1. 2. 3 1

7.

HPCI Steam Line Ambient g

Temperature - High NA SA R

1. 2. 3.

R 8.

HPCI Steam Line Area j

A Temperature - High NA SA R

1, 2. 3

[

9.

HPCI Equipment Area

,o Temperature - High NA SA' R

1.-2._3

.U 10.

Drywell Pressure

=High

?

Transmitter:

. NA(*)

-NA

. R(b) -

1, 2. 3 g

Trip Logic:

D 0

0

-1.

2, 3 i

L a

TABLE 4.3.2-1-(Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c-E CHANNEL OPERATIONAL R

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 7

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

.E,

4. CORE STANDBY COOLING SYSTEMS ISOLATION (Continued)

[

b.

Reactor Core Isolation Cooling System Isolation 1.

RCIC Steam Line Flow - High Transmitter:

NA)

NA R)

L 2. 3 tb Trip Logic:

D -

0 0

1. 2. 3 1

2.

RCIC Steam Line High - Flow Time Delay Relay NA R

R

1. 2. 3 3.

RCIC Steam Supply Pressure - Low NA 0

Q

1. 2. 3 i

R 4.

RCIC Steam Line Tunnel

]

Temperature - High NA SA R

1. 2. 3 5.

Bus Power Monitor NA R

NA

1. 2. 3 6.

RCIC Turbine Exhaust Diaphragm Pressure - High NA Q

R

1. 2. 3 1

7.

RCIC Steam Line Ambient Temperature - High NA SA R

1. 2. 3 8.

RCIC Steam Line Area g

A Temperature - High NA SA R

1. 2. 3 a

M 9.

RCIC Equipment Room Ambient a

Temperature - High NA SA R

1. 2. 3-5

10. RCIC Equipment Room A Temperature - High NA SA R

1. 2. 3

11. RCIC Steam Line Tunnel Tempera-

g ture - High Time Delay Relay NA SA' R

1. 2. 3 cn 12.

Drywell Pressure - High Transmitter:

NA(*)

NA R*)

1, 2. 3 Trip Logic:

D Q

Q

1. 2. 3 l

=

E

("

g TABLE 4.3.2-1 (Continued) n ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C5 CHANNEL OPERATIONAL H

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH N

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

5. SHUTDOWN COOLING SYSTEM ISOLATION a.

Reactor Vessel Water Level -

Low Level 1 Transmitter:

NA(*)

NA R(b)

1. 2. 3 Trip Logic:

D.

Q Q

1. 2. 3 l

b.

Reactor Steam Dome Pressure - High NA Q

R

1. 2. 3 I

w Y

M F

8a 8-

4?@

L L

TABLE 4.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS U01fl (a) The transmitter channel check is satisfied by the trip unit channel check.

A separate transmitter check is not required (b) Transmitters are exempted from the quarterly channel calibration.

1 (c) Deleted.

I (d) Testing shall verify that the mechanical vacuum pump trips and the mechanical vacuum pump line valve closes.

(e) When reactor steam pressure a 500 psig.

(f) When handling irradiated fuel in the secondary containment.

I BRUNSWICK - UNIT 2 3/4 3-32 Amendment No. EO,77,78,97,770, 174,JE9,779,206

-INSTRUMENTATION 1/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentdtion channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints I.

set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2.

APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

a.

With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2. declare the channel inoperable until the channel.is I

restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.

The provisions of S OPERATIONAL CONDITIgecification 3.0.3 are not applicable in c.

N5 SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in able 4.3.3-1 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

4.3.3.3 The ECCS RESPONSE TIME of each ECCS function shall be demonstrated to be within the limit at least once per 18 months, Each test shall ir.clude at least one locic train such that both logic trains are tested at least once per 36 months an2 one channel per function such that all channels are tested at least once every N times 18 months, where N is the total number'of redundant channels in a specific ECCS function.

BRUNSWICK - UNIT 2 3/4 3-33 Amendment No. 57,120,12d,I60, 202,206

r F;

TABLE 3.3.3-1 n

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E

U MINIMUM APPLICABLE OPERABLE CHANNELg OPERATIONAL m

PER TRIP FUNCTION,

TRIP FUNCTION CONDITIONS ACTION

1. CORE SPRAY SYSTEM a.

Reactor Vessel Water Level - Low Level 3 4

1.2.3.4.5 30 I

b.

Reactor Steam Dome Pressure - Low (Injection Permissive) 4 1.2.3.4.5 30 I

c.

Drywell Pressure - High 4

1. 2. 3

-30 1

d.

Time Delay Relay 1/ pump 1.2,3.4.5 31 l

e.

Bus Power Monitor")

1/ bus 1.2.3.4.5 32

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.

Drywell Pressure - High 4

1, 2. 3 30 I

b.

Reactor Vessel Water Level - Low. Level 3 4

1, 2. 3. 4(b) 5(b) 30 I c.

Reactor Vessel Shroud Level (Drywell Spray Permissive) 1/ valve

1. 2. 3. 4(b) 5(b) 31 1

a d.

Reactor Steam Dome Pressure - Low (Injection Permissive) jig 1.

RHR Pump Start and LPCI Injection Valve Actuation 4

1. 2. 3. 4(b) 5(*)

30 I

g 2.

Recirculation Loop Pump Discharge Valve Actuation 4

1. 2. 3. 4(b). 5(b) 30 l

l f

e.

RHR Pump Start - Time Delay Relay 1/ pump

1. 2. 3. 4(b) 5(b) 31 l

EM f.

Bus Power Monitor")

1/ bus

1. 2. 3. 4(b). 5(b) 32 LE FaN LE

~

1

.m

- ~

l k

TABLE 3.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION k

MINIMUM APPLICABLE

-OPERABLECHANNELgi

.0PERATIONAL-H N

TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION

3. HIGH PRESSURE COOLANT INJECTION SYSTEM a.

Reactor Vessel Water Level - Lov. Level 2 4

1. 2. 3 30 I b.

Drywell Pressure - High 4

1. 2. 3 30- 1.

c.

Condensate Storage Tank Level - Low 2(*)

1. 2. 3 33 d.

Suppression Chamber Water Level - High 2(

1. 2. 3 33 e.

Bus Power Monitor (*

1/ bus

1. 2. 3 32

4. AUTOMATIC DEPRESSURIZATION SYSTEM a.

ADS Inhibit Switch 2

1. 2. 3 36 l'

b.

Reactor Vessel Water Level - Low. Level 3 4

1. 2. 3

36. I c.

Reactor Vessel Water Level - Low. Level 1 2

1. 2. 3 36 l g

a d.

-ADS Timer 2

1. 2. 3 36 l

<%g e.

Core Spray Pump' Discharge Pressure - High (Permissive) 4

1. 2. 3

-36 l-y f.

RHR (LPCI MODE) Pump Discharge. Pressure - High (Permissive) 2/ pump

1. 2. 3

-36 l E?E g.

Bus Poe r Monitor (*

1/ bus 1, 2.~3 32

%?4

'?

lii:y

TABLE 3 3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION t

ACTIONS ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

I

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , verify sufficient channels remain OPERABLE or are placed in the tripped condition to maintain automatic ECCS actuation capability for the Trip Function, and b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place all inoperable channels that do not cause the Trip Function to occur in One tripped condition.

Otherwise, declare the associated ECCS inoperable.

ACTICN 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare I the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify I

bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the associated ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Tri) Function requirement

) lace at I least one inoperable channel in t1e tri aned condition wit 11n one hour or declare the HPCI system inoperaale.

I ACTION 34 - With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, verify within one hour that a sufficient number of channels remain OPERABLE to maintain actuation capability of either ADS Trip System A or ADS Trip System B and restore the inoperable channels to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, declare ADS inoperable.

s BRUNSWlCK - UNIT 2 3/4 3-37 Amendment No. 46,EJ,78.97.JEP 206 9

i TABLE 3.3.3-1 (Continued):

' EMERGENCY CORE'C00 LING SYSTEM ACTUATION INSTRUMENTATION

.i NOTES

(a).When a channel:is placed in an inoperable status solely for: performance of-required Surveillances.: entry:into associated ACTIONS may be delayed for-up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 'provided the Trip Function or. the redundant Trip Function

~,

maintains ECCS actuation capability.

-(b) Not applicable when two core spray system subsyst' ems are OPERABLE per Specification 3.5.3.1.

(c) Provides: signal to HPCI pump suction valves only.

(d) Alarm only.

l (e) Required when ESF equipment'is required to be OPERABLE.

2 l

I i

5 I

i i

1 1

1

)

q l

--BRUNSWICK - UNIT 2 3/4 3-38 AmendmentNo.{g6lg{8.97.160.

V

s e

E TABLE 4.3.3-l' n

7 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS-

!E CHANNEL OPERATIONAL

B CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION

. SURVEILLANCE REQUIRED-m

1. CORE SPRAY SYSTEM l

a. Reactor Vessel Water Level Low. Level 3 Transmitter:

NA

NA R(b' 1.2.3.'4.5 Trip Logic:

D Q

Q 1.2.3.4.5-l

'b. Reactor Steam Dome Pressure - Low k'

Transmitter:

NA

NA R(b' 1.2.3.4.5

~

Trip Logic:

D Q

Q 1.2.3.4.5 l

as

c. Drywell Pressure - High Transmitter:

NA(*)

NA R(b)

1. 2. 3' Trip Logic:

D Q

Q

1. 2. 3 i

d. Time Delay Relay NA R

R

1. 2. 3.-4. 5

e. Bus Power Monitor NA R

NA 1, 2. 3. 4._5 k

2. LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM s

a. Drywell Pressure - High Transmitter:

NA)

NA R(b'

1. 2. 3 Trip Logic:

D Q

Q

1. 2. 3 I

zO mi

b. Reactor Vessel Water Level -

8*

Low. Level 3 Transmitter:

NA

NA R(*)

1.2.3.4(*

5(*

4 Trip Logic:

D Q

Q

1. 2.'3. 4(** 5(*

I n

b

c. Reactor. Vessel Shroud Level U

Transmitter:

NA(*)

NA R(b)

-1. 2. 3. 4(*. 5(*

b Trip Logic:

0 Q

Q

1. 2. 3. 4'*. 5(*

I

7 i

k TABLE 4.3.3-1 (Continued)-

n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C5 CHANNEL OPERATIONAL ~

CHANNEL FUNCTIONAL CHANNEL.

CONDITIONS IN WHICH N

TRIP FUNCTION CHECK TEST

- CALIBRATION

' SURVEILLANCE REQUIRED LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Continued) d.

Reactor Steam Dome Pressure - Low NA

NA R(b)

1. 2. 3. 4(*. 5(*

1. RHR Pump Start and LPCI

.1, 2. 3. 4(*.- 5(*

I Injection Valve Actuation D

Q Q

2. Recirculation Loop Pump g

Discharge Valve Actuation D

Q Q

1. 2. 3. 4(*. 5(*

l' n

e.

RHR Pump Start - Time Delay. Relay

-NA R

.R

1. 2. 3. 4(*. 5(* -

y A

f.

Bus Power Monitor.

NA R

NA

'1. 2. 3. 4(*. 5(*

3. HIGH PRESSURE COOLANT INJECTION SYSTEM a.

Reactor Vessel Water Level -

Low. Level 2 Transmitter:.

NA(*)

NA

'R(b'

1. 2. 3 g

Trip Logic:

D 0

0

1. 2. 3 1

E b.

Drywell-' Pressure - High Transmitter:

NA(

NA

.R(b)

'1. 2. 3~

Trip Logic:

D Q

Q

1. 2. 3 l'

c.

Condensate Storage Tank Level

. Low NA 0

Q

'1. 2. 3 l-mf d.

Suppression Chamber Water Level-High NA Q

.Q.

1.'2.'3 i

N 8

e.

Bus Power Monitor.

NA R

.NA

1. 2. 3 "

u x.

+

a w

w v

m v

+-

U

,.3

.t*

w

,y

- - - +

w n-

- g

~

w E

p; TABLE 4.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS-C 5

CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH N

TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

4. AUTOMATIC DEPRESSURIZATION SYSTEM

a. ADS Inhibit Switch D(

'R NA

1. 2.~ 3'

b. Reactor Vessel Water Level -

Low. Level 3 Transmitter:

NA(#

NA R(

LL3 Trip Logic:

D Q

Q 11, 2. 3 l

a

c. Reactor Vessel Water Level -

. w A

Low. Level 1 u,

Transmitter:

NA(

NA R(*'

1. 2. 3.

Trip Logic:

D Q

Q

1. 2. 3 l-

d. ADS Timer.

NA R

R

1. 2. 3

e. Core Spray Pump Discharge.

Pressure - High NA Q

Q-

1. 2. 3 -~

l B'

f. RHR-(LPCI MODE) Pump Discharge 8-Pressure - High NA 0

0

1. 2. 3-

<o A

g. Bus Power Monitor

-NA R

NA

-l'. 2. 3 EF

?

- M

?

E!

cn t

.-.m---...-t m

.a,..-,e,

.,,w w

w

- -,*w-'

,m a y y-w

,y.r-r m

m

4 E

p; TABLE 4.3.3-1 (Continued) n EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c-5 CHANNEL

-CONDITIONS IN WHICH' OPERATIONAL CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION CHECK TEST-CALIBRATION

. SURVEILLANCE REQUIRED

5. LOSS OF POWER

a. 4.16 kv Emergency c,us NA NA R

1. 2. 3. 4").' 5")

Undervoltage (Loss of Voltage)

b. 4.16 kv Emergency Bus NA M

R

1. 2. 3. 4"). 5")

w2 undervoltage (Degraded Voltage) a k

ia E?L (a) The transmitter channel check is satisfied by the trip unit channel check.

O A separate transmitter check is not required.

L (b) Transmitters are exem)ted from the quarterly channel calibration..

I 3

(c) The ADS Inhibit Switcles shall be maintained in the Automatic position.

g (d) Required when ESF equipment is required to be OPERABLE.

8

TABLE'3.3.4-1 (Continued)

CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION HDIES

-(a) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS'may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains control rod a

withdrawal-block capability.

(b) This function is bypassed if detector is reading >100 cps or-the IRM channels are on range 3 or higher.

(c) This function is bypassed when the associated IRM channels are on range 8 or higher.

(d) A total of'6 IRM instruments must be OPERABLE.

(e) This function is bypassed when the IRM channels are on range 1.

(f) When (1)' THERMAL POWER is greater than or ecual to 30% of RATED THERMAL POWER and less than 90% of RATED THERMAL P0kER and MCPR is less than 1.70, or (2) THERMAL POWER is greater than or equal to 90% of RATED THERMAL POWER and MCPR is less than 1.40; (g)

With any control' rod withdrawn.

Not ap per Specification 3.9.10.1 or 3.9.10.2.plicable to control rods removed (h) This signal is contained in the Channel A logic only.

i BRUNSWICK - UNIT 2-3/4 3-49 Amendment No.7@S.J45.16@.

768,206 L

jg TABLE 4.3.4-1

-c CONTROL ROD WITHDRAWAL % LOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9

CHANNEL

. CHANNEL CONDITIONS IN WHICH-OPERATIONAL CHANNEL FUNCTIONAL c

TRIP FUNCTION CHECK TEST CALIBRATION-

. SURVEILLANCE REQUIRED 5

H 1.

APRM a.

Upscale (Flow Biased)

NA S/U(')

b.

Inoperative

.NA S/U(*"'IQ("

R(""

1

.l N

.Q NA-

1. 2. 5 c.

Downscale NA S/U( 0 """

NA 1

l.

d.

Upscale (Fixed).

NA S/U(*('3.0 R(')

2. 5 2.

R00 BLOCK MONITOR-a.

Upscale NA S/U.Q R(')

.1(S) l b.

Inoperative NA S/U(.0 NA l'i' c.

Downscale NA S/U(').0 R(

1(S) l' 3.

SOURCE RANGE MONITORS a.

Detector not full in NA S/U(

(*

NA

2. 5 a

b.

Upscale NA S/U(

(*

NA

2. 5

-5 c.

Inoperative NA S/U(

(*

NA

2. - 5 d.

Downscale NA S/U(')

(*

NA

2. 5 4.

INTERMEDIATE RANGE MONITORS' a.

Detector not full in NA S[)['"*.W(*

NA 2

NA W

NA 5-b.

Upscale NA S/U(.W(*

NA 2

NA W

NA 5

c.

Inoperative NA S/U(.W(*

NA 2

NA W

NA 5

d.

Downscale NA S/U(*).W(*

NA 2

g a

5.

SCRAM DISCHARGE VOLUME B-a a.

Water Level - High NA Q

R

- 1. 2. 5'h)

?4 OF T2 B, P o

m

=

,, ~.

TABLE 4.3.5.521

~ CONTRO_ ROOM EMERGENCY VENTILATION SYSTEM y

INSTRUMENTATION SURVEILLANCE REQUIREMENTS -

.(

I CHANNEL CHANNEL FUNCTIONAL-CHANNEL

. FUNCTION CHECK TEST CALIBRATION' 1.

CHLORINE ISOLATION:

a; Local NA M

A Detection' Trip System-b.

Remote NA M

A Detection: Trip System

-2. RADIATION PROTECTION:

Control Building-D 0

R l

Air Intake

3. CONTROL ROOM ENVELOPE SM0KE PROTECTION:

a.

Zone 4 NA 6 months (a) b.

Zone 5:

NA 6 months (a) 4

- (a)

See Surveillance Requirement 4.7.2.d.2 i

d f

o BRUNSWICK - UNIT 2 3/4 3-64c

-Amendment No, 192,295,206

-INSTRUMENTATION l

3/4.3.6 RECIRCULATION PUMP TRIP (RPT) ACTUATION INSTRUMENTATION-ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.1 The ATWS-RPT s shall be OPERABLE with ystem instrumentation channels shown in Table 3.3.6.1-1 I their trip setpoints set consistent with the values shown in the_ Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION:

a.

With an ATWS-RPT system instrumentation trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6.1-2. declare the instrument channel inoperable until the l

channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b.

With the number of OPERABLE channels less than' required by the Minimum

- OPERABLE Channels Per Trip System requirement:

1.

Verify that a sufficient number of channels remain OPERABLE or are in the tri3 ped condition to maintain ATWS-RPT trip capability for both Trip runctions within one hour, and 2.

Restore the inoperable channel (s) to OPERABLE status or place the inoperable channel (s) in the tripped condition within 14 days.

c.

With trip capability for one ATWS-RPT Trip Function not maintained, restore trip capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d.

With trip capability for both ATWS-RPT Trip Functions not maintained.

l restore trip capability for one Trip Function within one hour.

1 Otherwise, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

BRUNSWICK - UNIT 2 3/4 3-88 Amendment No.

9#, 160, 206

i TABLE 3.3 6.1-1

.ATWS RECTRCULATION PUMP TRIP SYSTEM INSTRUMENTATION MINIMUM 4.

OPERABLECHANNE('j JTRIP FUNCTION PER TRIP SYSTEM 1.

Reactor Vessel Water Level.

L(we, Level 2 2

2.

Reactor VesselfPressure - High 2

i i

e k

i When.a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for i

up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains ATWS-RPT capability.

l BRUNSWICK - UNIT 2 3/4 3-90 Amendment No.

94, 160, 206 l

s TABLE 4.3.611-1

-ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL.

CHANNEL

_ TRIP FUNCTION

-CHECK TEST CALIBRATION 1.

Reactor Vessel Water Level:-

Low. Le' vel 2 Transmitter:

NA(*)

NA

-R(*)

Trip Logic:

D Q

Q

-I-2.

ReactorVesseiPressure-High

~

Transmitter:

NA(')-

NA.

R(b) -

l Trip Logic:

D Q

Q 1

(a) The transmitter channel check is satisfied by the trip unit channel check.

A separate transmitter check is not required.

(b) Transmitters are exempted from the quarterly channel calibration.

I BRUNSWICK - UNIT 2 3/4 3-92 Amendment No.

160, 206 grgtion-6-29-89

A INSTRUMENTATION END-0F-CYCLE RECIRCULATION PUMP' TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION.FOR OPERATION-3.3.6.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels shown in Table 3.3.6.2-1 shall be OPERABLE with their-trip setpoints set consistent with the values shown in the Trip Set)oint

. column of Table 3.3.6.2-2 and with the END-0F-CYCLE RECIRCULATION PJMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.6.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER and the MCPR limits obtained from the COLR for use with Specification 3.2.2.1 require EOC-RPT.*

ACTION:

a.

With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values Column of Table 3.3.6.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the. Trip Setpoint value.

b.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the ino condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . perable channel (s) in the tripped I

c.

With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:

1.

If the operable chanr:els consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I 2.

If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip system operable.

s d.

With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or take the ACTION required by Specification 3.2.2.1.

e.

With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or take the ACTION required by Specification 3.2.21.

The provisions of Specification 3.0.4 are not applicable.

BRUNSWICK - UNIT 2 3/4 3-93 Amendment No.

160, 205, 206-9 m

~

TABLE 3.3.6.2-1 1

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION l

MINIMUM OPERABLE CHANNELS TRIP FUNCTION PER TRIP SYSTEM (*)

1.

Turbine Stop Valve - Closure 2(b) 2.

Turbine Control Valve - Fast Closure 2(b) b

(*)

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the Trip Function maintains EOC-RPT capability.

(*)

These functions are bypassed when turbine first stage 3ressure is equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

BRUNSWICK - UNIT 2 3/4 3-95 Amendment No. 16, 206

TABLE 4.3.6.2.1-1 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION TEST CALIBRATION 1.

Turbine Stop Valve - Closure 0(')

R I-2.

Turbine Control Valve - Fast Closure 0(*)

R I

4 I

(a) Including trip system logic testing.

BRUNSWICK - UNIT 2 3/4 3-98 Amendment No. 160, 206

m INSTRUMENTATION-3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7 The reactor core isolation cooling (RCIC) system actuation instrumentation channels shown in Table 3.3.7-1 shall be OPERABLE with their I

trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.7-2.

APPLICABILITY: OPERATIONAL CONDITIONS 1. 2. and 3 with reactor steam dome pressure greater than 113 psig.

ACTION:

With a RCIC system actuation instrumentation channel trip setpoint a.

less conservative than the value shown in the Allowable Values column of Table 3.3.7-2. declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.7-1.

SURVEILLANCE REQUIREMENTS 4.3.7.1 Each RCIC system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.1-1.

4.3.7.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

j BRUNSWICK - UNIT 2 3/4 3-99 Amendment No.

160, 206

i i

h2 pq TABLE'3.3.7-1 x

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION EiZ MINIMUM-no OPERABLE CHANNELS FUNCTIONAL UNIT PER TRIP SYSTEM

ACTION 1.

Reactor Vessel Water Level - Low. Level 2 2

50 2.

Reactor Vessel Water Level - High 2*)

51 3.

Condensate Storage Tank Water Level - Low"'

2")

52 ca 3;

4 ca E

o 1

i a

((

(a) 14 hen a channel is placed in an ino)erable status solely for performance of required'Surveillances.

P entry into associated ACTIONS may )e delayed as follows:

(1) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functional Unit 2.

(2) For up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 'for Functional Units 1 and 3 provided the Functional Unit maintains RCIC-30 actuation capability.

P (b) One trip system with two-out-of-two logic.

(c).One trip system with one-out-of-two logic.

n3 S'

~(d) Provides signal to-RCIC pump suction valves only.

.m

c FABLE 3.3.7-1 (Continued)

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTIONS ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a.

For one trip system, ) lace the inoperable channel (s) and/or

.that trip system in tie tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months I

or declare the RCIC system inoperable, b.

For both trip systems, declare the RCIC system inoperable.

ACTION 51 - With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement.

restore the inoperable channel (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, declare the RCIC system inoperable.

ACTION 52 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Tri) System requirement. place at least one inoperable channel in tie tripaed condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the RCIC system inoperaale.

BRUNSWICK - UNIT 2 3/4 3-101 Amendment No. 160, 206 u

E TABLE 4.3.7.1-1

~nn REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS E

CHANNEL CHANNEL FUNCTIONAL-CHANNEL y

FUNCTIONAL UNIT CHECK

' TEST CALIBRATION 1.

Reactor Vessel Water Level - Low. Level 2 Transmitter:

NA(

NA R(6' Trip Logic:

D Q

Q l

2.

Reactor Vessel Water Level - High Transmitter:

NA(')

NA R(b) '

Trip Logic:

D Q

Q l

a a

a 3.

Condensate Storage Tank Level - Low NA Q

Q l

G w

8

$a E

(a) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter

,a check is not required.

'"g (b) Transmitters are exempted from the quarterly channel calibration.

1

3/4.3 INSTRUMENTATTON

. BASES-3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:

a.

Preserve the integrity of the fuel cladding.

b.

Preserve the integrity of the reactor coolant system.

c.

Minimize the energy which must be adsorbed following a loss-of-coolant accident.. and prevent inadvertent criticality.

This specification )rovides the limiting conditions for operation necessary to preserve t1e ability of the system to perform its intended function even during periods when instrument channels may be out of service.

because of maintenance. When necessary, one channel may be made inoperable for brief intervals to conduct the required surveillance tests.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE re) orts NEDC-30851P-A. " Technical Specification Improvement Analyses for 3WR Reactor Protection System." March 1988 and MDE-81-0485. Rev. 1. " Technical Specification Imarovement Analysis for the Reactor Protection System for Brunswick Steam. Electric Plant. Units 1 and 2." August 1994, as modified by BWROG-92102. Letter from C. L. Tully (BWROG) to B. K. Grimes (NRC). "BWR 1

Owners' Group (BWROG) Topical Reports on Technical Specification Improvement Analysis for BWR Reactor Protection Systems - Use for Relay and Solid State Plants (NEDC-30844'and NEDC-30851P)." November 4, 1992.

The reactor protection system is made up of two independent trip systems.

There are usually four channels to monitor each parameter with two in each trip system.

The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both tri) systems will produce a reactor scram. The system meets the intent of IEEE-279 for nuclear power plant protection systems.

The measurement of response time at the specified frequencies provides assurance that the arotective, isolation, and emergency core cooling functions associated with eac1 channel are completed within the time limit assumed in the accident analysis.

No credit was taken for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) inplace, onsite, or offsite test measurements, or 2) utilizing replacement sensors with certified response times.

The bases for the trip settings of the reactor protection system are discussed in the bases for Specification 2.2.

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

206

INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the trip settings for isolation of the reactor systems. When necessary, one channel ma inoperable for brief intervals to conduct required surveillance. y be Some of the trip settings have tolerances explicitly stated where both the high and low values are critical and may have a substantial effect on safety.

The setpoints of other instrumentation where only the high or low end of the setting has a direct bearing on the safety. are established at a level away from the normal o systems involved.perating range to prevent inadvertent actuation of the Specified surveillance intervals and allowed out-of-service times were established based on reliability analyses documented in GE reports NEDC-30851P-A. Supplement 2. " Technical S)ecification Improvement Analysis for BWR Isolation Instrumentation Common to R3S and ECCS Instrumentation." March 1989 and NEDC-31677P-A " Technical Sp'ecification Improvement Analysis for BWR Isolation Actuation Instrumentation. July 1990, as modified by OG90-579-32A.

Letter to Millard L. Wohl (NRC) from W. P. Sullivan and J. F. Klapproth (GE).

" Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation Instrumentation Anal

25. 1990 and supplemented by GE letter report GENE-A31-00001-02. "ysis " June Assessment of Brunswick Nuclear Plant Isolation Actuation Instrumentation Against NEDC-31677P-A Bounding Analyses "

August 1994.

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the operator's ability to control.

This specification provides the tri) point settings that will ensure effectiveness of the systems to provide tie design protection. Although the instruments are listed by system in some cases the same instrument is used to send the start signal to several systems at the same time.

The out-of-service times for the instruments are consistent with the requirements of the specifications in Section 3/4.5.

Specified surveillance intervals and allowed out-of-service times were established based on the reliability analyses documented in GE reports NEDC-30936P-A. Parts 1 and 2. "BWR Owners' Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)," December 1988 and RE-011. Rev.1. " Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Brunswick Steam Electric Plant. Units 1 & 2." August 1994, as modified by OG90-319-320. letter from W. P. Sullivan and J. F. Klapproth (GE) to Millard L. Wohl (NRC)

" Clarification of Technical Specification Changes Given in ECCS Actuation Instrumentation Analysis." March 22, 1990.

'l

)

BRUNSWICK - UNIT 2 B 3/4 3-2 Amendment No.

206 l

INSTRUMENTATION BASES i

3/4.3.4 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the recuirements of the specifications.in Section 3/4.1.4. Rod Program Controls

. anc Section 3/4.2. Power Distribution Limits. ~ The. trip logic is arranged so that a trip in any one of the inputs will result in a rod block.

Specified surveillance intervals and allowed out-of-service times were established based.on the reliability analyses documented in GE report NEDC-30851P-A Supplement 1. " Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation." October 1988.

3/4.3.5 MONITORING INSTRUMENTATION 3/4.3.5.1 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumention ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of.the measured response to that used in the design basis for the facility.

t I

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

206 l

INSTRUMENTATION BASES 3/4.3.5.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM (Continued)

Surveillances (Continued) instrumentation continues to operate properly between each CHANNEL CALIBRATION. The CHANNEL CHECK frequency is consistent with that performed for other radiation monitors with isolation functions.

The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

The Control Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the radiation actuation instrumentation.

The quarterly frequency of the CHANNEL FUNCTIONAL TEST l

was established based on Reference 7 and is consistent with that performed for other I radiation monitors with isolation functions.

The CHANNEL CALIBRATION verifies the channel res)onds to the measured Jarameter within the necessary range and accuracy.

CHANNE. CALIBRATION leaves t1e channel adjusted to ensure consistency with the system assumptions (Reference 5). The frequency of the calibration is consistent with the frequency of calibration of other radiation monitors with isolation functions.

Chlorine Protection The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. The Control Building HVAC DBD (Reference 6) defines the specific actions to be satisfied by the chlorine isolation instrumentation. The monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent with the testing frequencies performed by other utilities with this type of instrumentation.

The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the sensor when the sensor is replaced.' The test verifies the calibration of the existing sensor prior to removal and performs an installation calibration of the new sensor. including a complete channel calibration with the new sensor installed, to verify the channel res)onds to the measured Sarameter within the necessary range and accuracy.

The CHANNE CALIBRATION leaves t1e channel adjusted to ensure consistency with the system assumptions (Reference 6).

The chlorine detectors use an amperometric sensor consisting of a platinum cathode and silver anode joined by an electrolytic salt bridge, all enclosed in a permeable membrane. This design eliminates the majority of the maintenance required on previous detectors.

The detectors have been in service at other facilities and have provided reliable service.

The annual replacement and calibration are based on a manufacturer recommendation. The adequacy of the replacement interval has been confirmed through discussions with other utilities.

Smoke Protection The CHANNEL FUNCTIONAL TEST for the Smoke Protection instrumentation is consistent with the testing performed in accordance with the existing Fire Detection Instrumentation requirements. CHANNEL CALIBRATION is performed in accordance with the requirements of the CREVS specification (4.7.2).

BRUNSWICK - UNIT 2 B 3/4 3-3d Amendment No. 192, 206

INSTRUMENTATION BASES 3/4.3.5.5 CONTROL Room EMERGENCY VENTILATION SYSTEM (Continued)

References 1.

10 CFR 50. Appendix A. General Design Criterion 19. Control Room.

2.

Regulatory Guide 1.95. Revision 1. Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release.

3.

Updated FSAR.' Brunswick Steam Electric Plant. Units 1 & 2.

4.

NUS-3697. Revision 2. February 1983. Control Room Habitability Analysis.

5.

CP&L Calculation 01534A-248. Control Room Radiation Monitor Setpoint Evaluation.

6.

BNP Design Basis Document (DBD)-37. Control Building Heating. Ventilation, and Air Conditioning System.

7.

GENE-770-06-1-A " Bases for Changes to Surveillance Test Intervals and Allowed-Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

BRUNSWICK - UNIT 2 8 3/4 3-3e Amendment No. 192, 206

INSTRUMENTATION BASES

)

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION (Continued)

The initial CHANNEL CALIBRATION for the instruments associated with footnote (b) to Table 4.3.5.9-1 shall be performed using National Bureau of Standards traceable sources which will verify that the detector operates properly over its intended energy range and measurement range.

For instruments which were operational prior to this specification being implemented, previously established calibration procedures may be substituted for this requirement. Subsequent CHANNEL CALIBRATIONS will be performed using.

sources that have been related to the initial calibration in order to ensure

.that the detector is still 03erationa'1 but the sources need not span the full ranges used in the initial C MNNEL CALIBRATION.

3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within an envelope of study events given in General Electric Company Topical Report NED0-10349, dated March, 1971.

The end-of-cycle recirculation pump trip (EOC-RPT) system is a part of the Reactor Protection System and is a safety supplement to the reactor trip. The purpose of the E0C-RPT is to recover the loss of thermal margin which occurs at the end-of cycle, The physical phenomenon involved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the

'ntrol rods add negative scram reactivity.

Each E0C-RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting pressurization events. The-two events for which the E0C-RPT protective feature will function are closure of the turbine-stop valves and fast closure of the turbine control valves.

A fast closure sensor from each of two turbine control valves provides input to one E0C-RPT system; a fast closure sensor from each of the other two turbine control valves provides input to the second E0C-RPT system.

Similarly, a )osition switch for each of two turbine stop valves )rovides input to one E0C-RPT system; a position switch for each of the otler two turbine stop valves provides input to the other E0C-RPT system.

For each E0C-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for closure of the turbine stop valves.

The operation of either logic will actuate the E0C-RPT system and trip both recirculation pumps.

Each_EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled. The manual bypasses and the automatic operating bypass at < 30% of RATED THERMAL POWER are annunciated in the control room.

t Specified surveillance intervals and allowed out-of-service time were established based on the reliability analyses documented in GE report GENE-770-06-1-A. " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

December 1992.

BRUNSWICK - UNIT 2 B 3/4 3-6 Amendment No.

58, 206

' INSTRUMENTATION BASES 3/4.3.7 ' REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is

.provided to initiate actions to assure adequate core cooling in the event of-reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core i

cooling equipment, Specified surveillance: intervals and allowed out-of-service times were established based on the reliability analyses documented in GE report

. GENE-770-06-2P-A " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications." December 1992.

l BRUNSWICK - UNIT 2-B 3/4 3-7 Amendment No.

11, 206 I

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