Text

Amends 134 & 113 to Licenses DPR-70 & DPR-75,respectively, Providing Adminstrative Changes Associated W/Reactor Trip Sys Instrumentation
	ML20113H737
Person / Time
Site:	Salem
Issue date:	07/29/1992
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20113H738	List: ML20113H737; ML20113H740;
References
	NUDOCS 9208050224
	Download: ML20113H737 (20)
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UNITED STATES l

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/: 1 NUCLEAR REGULATORY COMMISSION NASHINGTON, D C,20555

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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPAtu DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COM[LAfd DOCKET NO. 50-271 SALEM HUCLEAR GENERATING STATION. UNIT N0. 1 AMENDMENT TO FACILITY lO ERATING LICENSI Amendment No. 134 License No. DPR-70 1.

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

A. _ The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated May 6, 1992, 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 amenoment 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 set forth in 10 CFR Chapter I; 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 chans as to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:

l, 920B050224 920729-DR.ADOCK 0500 2

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1 (2) Igchnical Specifications and Environmental Protection Plan The-Technical Specifications contained -in Appendices A and B, as revised:through Amendment No.134, _ are hereby incorporated in the license. The licensee shall operate the facility in accordance with

.the' Technical Specifications.

3, This license amendment is _ effective as of.its date of issuance and shall be-implamented within 120 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

%L W. fliYAw Charles L. Miller, Director

~

Project Dire:torate 1-2 Division of Reactor Projects - I/II Office of-Nuclear Reactor Regulation

Attachment:

ChangesJto the Technical Specifications Date of Issuance: _ July 29. 1992 l:

.a i

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. O ATTACHMENT TO LICENSE AMENDMENT NO. 134 f_AClllTY OPERATING LICENSE NO OPR-70 DOCKET NO. 50-271 Revise Appendix A as follows:

Eqm.ove Paaes Lnsert Paaes 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-10 3/4 3-10

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l' TABLE 3.3-1 REACTOR TRIP SYSTEM INSfRUMENTATION e-E N

MINIMUM

~

TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT.

OP CHANNELS TO TRIP OPERABLE MODES ACTION

~j 1.

Manu;tl Reactor Trip 2

1 2.'

1,2 and'*

12' 2.

Power. Range, Neutron Flux 4

2 3

1,2 2

3.

Power Range, Neutron Flax 4

2 3'

1,2 2

i High Positive-Rate 4.

Power Range, Neutron Flux 4

2 3

1,2 2

High Negative Rate 5

Intermediate Range, Neutron Flux 2

1 2

1,2 and

3-

[

6.

Source Range, Neutron Flux A.

Startup 2

1 2

2## and

4 B.

Shutdown 2

0 1

3,4, and 5 5

7.

Overtemperature AT 4

2 3

1,2 6

8.

Overpower AT 4

2-3 1,2 6

9.

Pressurizer Pressure-Low 4

2 3

1, T_

6 10.

Pressurizer Pressure--High 4

2 3

1,2 6

E a

a n

(A3 Zu o

r.

[

. TABLE 3.3-1~fContinued)

. REACTOR TRIP SYSTEM INSTRUMENTATION 5p.

MINIMUM TOTAL NUMBER CHANNELS CHANNEL 3 APPLICABLE

. FUNCTIONAL UNIT-OF CHANNELS TO TRIP OPER.BLE MODES ACTION 11.

Pressurizer Water' Level--High 3

2-2' 1,2 7#

12, Loss of Flow - Single Loop 3/ loop 2/ loop in

.2/ loop in 1

7#

(Above P-8) any oper-

'each oper-ating loop sting loop 13.

Loss of Flow - Two' Loops

.3/ loop 2/ loop in 2/ loop in 1

7#

(Above P-7 and below P-8) two oper-each oper-ating leeps ating loop 14.

Steam Generator Water Level--

3/ loop 2/ loop in 2/ loop in 1,2 7#

1 Low-Low any oper-each oper-

'r' ating loopo ating loop w

15.

Steam /Feedwater Flow Mismatch 2/ loop-level

.1/ loop-level 1/ loop-level 1,2 7#

and Low Steam Generat'sr Water and 2/ loop-coincident and 2/ loop-Level flow mismatch with flow mismatch 1/ loop-riow or 2/ loop-mismatch in level and same loop 1/ loop-flow mismatch l

16.

Undervoltage - Reactor 4-1/ bus 1/2 twice 3

1 6

Coolant Pumps 17.

Underfrequency - Reastor 4-1/ bus 1/2 twice 3

1 6'

Coolant Pumps

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.,. '.. - {f lU IABLE 3,3-1 (Continuedi a

REACTOR' TRIP SYSTEM INSTRUMENTATION' E

N MINIMUM

~

TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTICI.AL UNIT OF CHANNELS TO' TRIP OPERABLE MODES ACTION' 18.

Turbine Trip a.

Low'Autostop Oil. Pressure 3

2 2

1 7#

b.

Turbine Stop Valve Closure 4

4 3

1 7#

'19.

Safety Injection Input from ESF 2

1 2

1,2 1

20.

Reactor Coolant Pump Breaker 1/ breaker 2

1/ breaker 1

11 Position Trip (above P-7) per opera-ting loop R:

21. Reactor Trip Breakers 2

1 2

1,2 1###, 14

~

3*,4*,5*

13 Y

=

22. Automatic Trip I.ogic 2

1 2

1,2 1

3*,4*,5*

13 5

2 an

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TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control tod drive system capable of. rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

High voltage to detector may be de-energized above P-6.

1. 1. If ACTION Stat antered as a result of Reactor Trip 3reaker (RTB) or Reac-(RTBB) maintenance testing results

a I f g iteria, NRC reporting shall be made exceeding the j#> ~

T sc within 30 da) ib

e. cification 6.9.2:

j

' U7 T,1 \\G.dj \\

p 1.

A RT8 e A A ' ng any surveillance test with lese jg ph;/ys

7 eight added to the breaker trip bar.

than or ffpy h '4,[4v,y.

,ilure that results in the overall O. !

a 2.

A RTB (G-reactor trip e. # -(

nee exceeding the Technical Specification limit, hCIION STATEMENTJ With the number of chaarols OPERABLE one less than required ACTION 1 by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within G hours; however, one channel may be bypasoed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for aurveillance testing pe* epecifict. tion 4.3.1.1 provided the other channel in OPERABLE.

ACTION 2 -

With the number of OFERABLE channels one less than thu Total Number of Channels, STARTUP and/or POWER OPERATION may protaid provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within I hour.

b.

The Minimum Channels CPERABLE requirement is met; hcwever, one additional channel may bo bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

c.

Either, THERMAL POWER is restricted to S 75% of RATED THERMAL POWER and the Power Range, N2utron Flux trip l

setpoint is reduced to S 8b% of RATED THERMAL POWER within 4 ' urs; or, the QUADRANT POWER TILT RATIO it monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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SALEM UNIT 1 3/4 3-5 Amendment no. 134

.e A-TABLE 3.3-1 (Continued) rg

' ACTION (3 With the number of channels OPERABLE one less than required

-by the Minimum Channels OPERABLE requirement and with the THERMAL POWER levels a.

.Below P-6, restoro the inoperable channel to 0PERABLE status prior to increasing THERMAL' POWER above the P-6 Setpoint.

b..

Above P-6 but below 5% of RATED THERMAL POWER, restore D

t he inoperable. channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL P0WER, POWER OPERATION may continae.

ACTION 4 -

With the number of channels OPERABLE one 1 sus than required by the Minimuni Channels OPERABLE requirement and with the THERMAL POWER levels a.

Below P-6, restore the inoperable channel to OPERhBLE status prior to increasing YHERMAL POWER above the P-6 Setpoint.

b.

Above P-6, operation may continue.

ACTION With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requiremente of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once pe-J2 hours thereafter.

ACTION 6 -

With: the number of -OPERABLE channel s one less than the

--Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

- The inoperable channel-is placed'in-the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

~

b.

The Minimum Channels OPERABLE requirement is met-however,.or.e additional channel may be bypassed for ur to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specificaticn 4.3.1.1.

' ACTION 7 -

'With the number of OPERABLE channels one less than the-Total Number of Channels, STARTUP and/or POWER OPERATION may proceed unti). performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in 1

the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 8 -

NOT USED

~

SALEM - UNIT 1 3/4 3-6 Amendment No. 134 l

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a TABLE 3.3-1 (Continued)

ACTION 9 NvT USED ACTION 10 -

NOT USEO ACTION 11 -

With lees than the Minimum Number of Channcle OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 -

With the number of channals OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip creakers.

ACTION 13 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or o

open the reactor trip breakers within the next hour.

ACTION 14 -

With one of the diverse trip ieatures (Undervoltage or shunt trip att7chment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoper'h\\

and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Thei wer shall not be bypassed while one of the diverse tri; o -tures t

(

is inoperable except for the time required for performing maintenance to restore the breaker to OPERA 3LE status.

RA_q1_Oj! TRIP SYSTEi! IN'ERLOCKS pangNATIOR CONDITION AND SU P9It.T LUFCT*0N P-6 With 2 of 2 Intermediate Rangy P-G prevents or defeats Neutror. Flux Channels < 6x10 the manual block of amps.

source suge reactor trip.

P-7 With 2 of 4 Power Range Neutron P-7 prevento or defeats Flux Channels 2 11% of RATED the automatic block of THERMAL POh2R or 1 of 2 Turbine reactor trip on Low impulse chamber pressure channels flow in more than one 2 a pressure equivalent to 11% of primary coolant loop, RATED THERMAL POWER.

reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressar.

r e

high level, and the opening of more than one reactor coolant pump breaker.

SALEM - UNIT 1 3/4 3-7 Amendment No. 134 1

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TABLE 3.3-2-fContinued)

. REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT

, RESPONSE TIME 12.

Loss;of Flow - Single Loop.(Above P-8)'

s 1.Oloeconds.

13.

Loss of Flow - Two_ Loops (Above P-7.and below P-8) s 1.0 se~;onde 14.

Steam Generator Water Level-- Low-Low 5 2.0 swonds

15. ' Steam /Feedwater Flow Mismatch and Low

.NOT. APP,ICABLE Steam Generator Water Level 16.

Undervoltage-Reactor' Coolant Pumps 5 1.2 seconds 17.

Underfrequency-Reactor Coolant Pumps

& O.6 seconds

}

18.

Turbine Trip A.

Low Fluid Oil Pressure NOT APPLICABLE B.

Turbine Stop Valve NOT APPLICABLE 19.

Safety Injection Input from ESF NOT APPLICABLE

~

20.

Reactor Coolant Pump Breaker Position Trip NOT APPLICABLE 21.

Reactor Trip Breakers NOT APPLICABLE 22.

Auio.natic Trip Logic NOT APPLICABLE E

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tr UNITED STATES c

NUCLEAR REGULATORY COMMISSION WASHINGTON. D C. 20%3

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o PUBLIC SERVICE ELECTRIC & GAS COMPANY m

PHILADELPHIA ELECTRIC COMPANY DELMARVA POER AND LIGHT COMPANY ATLANTIC CJTY ELECTRIC COMPANY DOCKET N0. 50-311 SALEM NELIAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 113 License No. DPR-75 1.

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

A.

The application for amendment filed by the Public Service Electric &

Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated May 6, 1992, complies with the standards ard 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 Commiss. ion; 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 set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of tia public; and E.

The issuance of this amendment is in accordance with 10 CTR 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:

.s-2.-

'(2)l Technical-Soecifications-andEnvironmentalProtectionPl.gn

.-The-Technical Specifications contained in Appendices A and B, as revised through Amendment No. 113,.are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

' U.w lb 0b v

f Charles L.. Miller, Director Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear lleactor Regulation

Attachment:

Changes to_the' Technical Specifications Date of' Issuance:

July 29. 1992 x

l. AIJALHMENT TO LICENSE AMENDMENT NO.113 j

FACIllTY OPERATING LICENSE NO. DPR-7_5 DOCKET N0; 50-311 Revise Appendix'A as follows:-

-Remove Paaes 1Dscrt Paoes 3/4 3-1 3/4 3-1 3/4 3 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3 3/4'3-4 3/4 3-5 3/4 3-5 3/4.3-6 3/4 3-6 3/4 3 3/4 3-7 i

3/4i3 INSTRUMf2I Q19h

-)

d 3/4.3.1 RE' ACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION

......................................s.....................................

I 3.3.1.1 As a minimum,.the reactor trip system instrumentat19n channels and l

interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLI.9ABILIII: As shown in Table 3.3-1.

ACTION:

~

.As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENis

_4.3.1.1.1 Ea,tr reactor trip system instrumentation channel shall be demonstratedTOPERABLE by the performance of the CHANNEL CHECK, CHANNEL-

. l CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at

-the frequencies shown in Table 4.3-1.

4.3.1.1.2 : The logic for the interlocks shall be demonstrated OPERABLE l

prior to each reacter startup unless performed during the preceding 92 days.

The total interlock function shall be demonstrated OPERABLE at least once

per 10_ months during CHANNEI, CALIBRATION testing of each channel affected by interlock operation.

4.3.1.1.3 The. REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip

~

function anall be demonstrated to be within its llmit 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 i

per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channsle in_a specific reactor trip function as shown in the " Total No. of Channels" column of Table-3.3-)

SALEM.- UNIT 2 3/4 3-1 Amendment No.

113

-1 o

TAB 2.E 3 '. 3-1 REACTOR TRIP SYSTEM INSTRUMENTATION U

T MINIMUM

. TOTAL NUMBER CHANNELS CHANNELS APPLICABLE c-FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION h

1.

Manual Reactor Trip 2

1 2

1,2 and

12 m

2.

Power Range, Neutron Flux 4

2 3

1,2 2

3.

Power Range, Neutron Flux 4

2 3

1,2 2

High Positive Rate 4.

Power Range, Neutron Flux, 4

2 3

1,2 2

High Negative Rate 5.

Intermediate Range, Neutron Flux 2

1 2

1,2 and

3 6.

Source Range, Neutron Flux A.

Startup 2

1 2

2##, and

4 w2 B.

Shutdown 2

0 1

3,4 and 5 5

Y 7.

Overtemperature AT 4

2 3

1,2 6

8.

Overpower AT 4

2 3

1,2 6

9.

Pressurizer Pressure-Low 4

2 3

1,2 6

10.

Pressurizer Pressure--High 4

2 3

1,2 6

4 h"

a R

n W

s N

l _

TABLE'3.3-1 (continued 1 REACTOR TRIP SYSTEM ~ INSTRUMENTATION w

MINIMUM e

TOTAL NUMBER CHANNELS CHANNELS' APPLICABLE y>

FUNCTIONAL UNIT OF CHANNELS-TO TRIP OPERABLE.

MODES ACTION N

11.

Pressurizer Water Level 3

2^

2 1,2 7# -

s

--High 12.

Loss of Flow - Single Loop.

3/ loop "2/ loop in 2/ loop in

-1 7#

(Above P-8) any oper-each oper-ating loop.

ating loop 13.

Loss of Flow - Two Loops 3/ loop--

2/ loop-in-2/ loop in 1

-7#-

(AL.ve P-7 and below P-8) two oper-each'oper-ating loops ating loop 14.

Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1,2 7#

Level--Low-Low any oper-each oper-y ating loops ating loop a,

[

15.

Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop-level 1,2 7#.

Mismatch and Low Steam and coincident and Generator Water. Level 2/ loop-flow with 2/ loop-flow mismatch 1/ loop-flow mismatch or I

mismatch in 2/ loop-level l

same Icop and 1/ loop-flow mismatch 16.

Undervoltage-Reactor 4-1/ bus

'l/2 twice-3 1

'6 Coolant Pumps l

l

17..Underfrequency-Reactor 4-1/ bus 1/2 twice 3

1 6

Coolant Pumps 5

2it

.O w

i m.

wm_;_t

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TABLE 3.3-1 (continued)

REACTOR TRIP SYSTEM INSTRUMENTATION-

$i MINIMUM

.)

TOTAL NUMBER-

. CHANNELS CHANNELS APPLICABLE c

FUNC*lTONAL UNIT OF CHANNELS TO TRIP

-OPERABLE MODES ACTIOM u

18. Turbine Trip a.

Low Autostop. Oil' Pressure 3

2 2

1 7#

-l b.

Turbine stop Valve Closure 4

4-3 1

7#-

19. Safety Injection Input from ESF

.2 1

2 1,2 1

20. Reactor Coolant Pump Breaker 1/ breaker 2

1/ breaker 1

Il Position Trip (above P-7) per opera-ting loop-

21..Peactor Trip Breakers 2

1 2

1,2 1###, 14

'3*,4*,5*

13

22. Automatic Trip Logic 2

1 2

1,2 1-y 3*,4*,5*

13 a

e a

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IbBLE 3.3-1 (continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control red drive system capable of rod withdrawal.

The provisions of Specification 3.0.4 h g v i

High voltage to cetector may be de-er c 1[) (I tot, l[7

1. 1. If ACTION Statement 1 la entered as a

-Breaker f,A.ng (RTB) or Reactor Trip Bypase Breaker f

results exceeding the following accep %,gy a "R # a t,'<4

>rting chall be made within 30 days in accor

/V n 6.9.2 1.

A RTB or RTBB trip failure during any surveillance test with less than or equal to 300 grams of weigF added to the breaker trip bor.

2.

A RTB or RTBB time response failure that results in the overall reacter trip system time response exceeding the Technical Specification limit.

ACTION STATEMENTS ACTION 1

.th the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1 provided the other channel is OPERABLE.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

T@

g a.

The inoperable channel is placed in the tripped condition p

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

c.

Either, THERMAL POWER is restricted to 6 75% of RATED THERMAL POWEH and the Power Range, Neutron Flux trip setpoint is reduced to s 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d.

The QUADRANT POWER TILT RATIO, as indicated by the remaining th-ee detectors, is verified consistent with the normalized symmetric power distribution obtained by using the movable in-core detectors in the four pairs of symmetric thimble locations at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when THERMAL POWER is greater than 75% of RATED THERMAL POWER.

SALEM - UNIT 2 3/4 3-5 Amendment No.113

l-.+'

TABLE 3.3-1 (Continued)

With the number of channels OPERABLE one less than required l

I ACTION 3 by the Minimum Channels OPERABLE requirement and with the THERMAL POWER levelt a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above P-6, but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

c.

Above 5% of RATED THERMAL POWER, POWER OPERATION may continue.

d.

Above 10% of._nTED THERMAL POWER, the provisions of Specification 3.0.3 are not applicable.

With the number of channels OPERABLE one less than required ACTION 4 by the Minimum Channels OPERABLE tequirement and with the THERMAL POWER levels a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above P-6, operation may cc-tinue.

ACTION 5 -

With tho number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

With the number of OPERABLE channels one less than the ACTION 6 Total Number of Channels, STARTUP and/or POWER OPERATION may prosted provided the following conditions are satisfied a.

The inoperable char.nel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , b.

The Minimum Channel OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

With the number of OPERABLE channels one lese than the ACTION 7 Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition with I hour.

SALEM - UNIT 2 3/4 3-6 Amendment No. 113

.o TABLE 3.3-1 (Continued) l 6

ACTION 8 -

NOT USED ACTION 9 NOT USED ACTION 10 -

NOT VSED ACTION 11 -

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 13 -

With the number of OPERABLE channels one less than the 7,

Minimum Channels OPERABLE requirement, restore the e

inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

ACTION 14 -

With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and be L.

at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

EEhCTOR TRIP SYSTEM INTERLOCKS EESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Rangg P-6 prevents or defeats Neutron Flux Channels < 6xlO the manual block of amps.

source range reactor trip.

P-7 With 2 of 4 Power Range Neutron P-7 prevents or defeats Flux channels 2 11% of RATED the automatic block of THERMAL POWER or 1 of 2 Turbine reactor trip on: Low impulse chamber pressure flow in more than one channels 2 a pressure equivalent primary coolant loop, to 11% of RATED THERMAL POWER.

reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.

SALEM - UNIT 2 3/4 3-7 Amendment No. 113

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