Text

Amends 138 & 116 to Licenses DPR-70 & DPR-75,respectively, Containing Administrative Changes Re ESFAS Instrumentation, to Provide Consistency & Ensure Technical Accuracy Between Units
	ML20127B743
Person / Time
Site:	Salem
Issue date:	01/05/1993
From:	Chris Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20127B747	List: ML20127B743; ML20127B756;
References
	NUDOCS 9301130099
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _. _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ -

les acog\\

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UNITED STATFS n

3 i

NUCLEAR REGULATORY COMMISSION

k f

WASHINoToN, o C. 20%6 k,

/

PUBLIC SERVICE ELECTRIC & GAS COMPhiY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY QOCKET NO. 50-272 SALEM f{UCLEAR GENERATING STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No.138 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 1

Company and Atlantic City Electric Company (the licensees) dated August 14, 1992, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act), anc 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 Commissien; 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 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 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:

SO 00$ o!ooO!72 P

PDR

i (2) ltchttitAl.JnecificationLADLinvironmental Protection Plan The Technical Specifications contained in Apaendices A and B, as revised through Amendment No.138

, are here'y incorporated in the a

l iterre.

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 aA d. wL Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nucicar Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of 1ssuance: January 5, 1993 l

i

\\

I A1TACHMENT TO LICENSE AMENDMENT NO.138 FAClllTY OPERATING LICENSE NO. OPR-70 1

DOCKET NO. 50-272 Revise Appendix A as follows:

Remove Paoes lnsert Paaes 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-20a 3/4 3-20a 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-22a 3/4 3-24 3/4 3-24 3-4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-31a 3/4 3-31a 3/4 3-32 3/4 3-32 3/4 3-32a 3/4 3-32a 3/4 3-33 3/4 3-33 3/4 3-34

-3/4 3-34

i T

i TABLE 3.3-3 m

i ENGINEERED SAFETY FEATUPE ACTUATION SYSTEM INSTRUMENTATION M*

l' r

MINIMUM a

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL 7 NIT OF CHANNELS TO TRIP OPERABLE MODFS ACTION j

w HE i

1.

SAFETY' INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION i

2 a.

Manual Initiation 2

1 2

1,2,3,4 18 j

b.

Automatic Actuation Logic 2

1 2

1,2,3,4 13 c.

Containment Pressure-High 3

2 2

1,2,3 14*

I i

a I

d.

Pressurizer Pressure-Low 3

2 2

1,2,3#

14*

l 4

j-e.

Differential Pressure Between 3/ steam line 2/ steam line 2/ steam 1,2,3##

14*

I.

Steam Lines - High any steam line Y

line s

(

Y f.

Steam Flow in Two Steam 2/ steam line 1/ steam line 1/ steam 1,2,3##

14*

i 5

Lines-High any 2 steam line lines COINCIDENT WITH EITIER i

T

--Low-Low 1T floop 1T in 1T 1,2,3##

14*

1. 9

- 9 any"I91 oops inin?

3 loops OR, COINCIDENT WITH i

l Steam Line Pressure-Low 1 pressure /

1 pressure 1 pressure 1,2,3##

14*

loop any 2 loops any 3 loops I

3.

l n

$e Z

.-W C3

I 1

f I

i r

i N

Y l

L This page is intentionally left blank.

1 4

e E

t r

+

)

SALEM - UNIT 3-3/4 3-16 Amendment No. 138-

- t

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4 eshi

,= w b w 5 e Nwn E.U w w E,e.,*-.

w,,'v,.% E -om'-~

v h e, se y - ve h r,

, w-v +

-ew,-~-

-% -- n

-g

-w-e -v

-nwrew-y, v-~-

w,-,-w-,--wwwyv.

ye- +-. - --

m E

Y t

tn.

[

TABLE 3.3-3 fcontinued1 i,

E

'ENGINEEPED SAFETY FEATURE ACTUATION SYSTEM INSTFUMENTATION 1

i 8

l-e

' MINIMUM

[

3 TOTAL NO.

CHANNELS CHANNELS APPLICABLE I

- 4 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i

h 2.

CONTAINMENT SPRAY a.

Manual 2 sets of 2 I set of 2 2 sets of 2 1,2,3,4 18-f 1-I

{

b.

Automatic Actuation Logic 2

1 2

1,2,3,4 13 l

l i

c.

Containment' Pressure--High-High 4

2 3

1,2,3 16 f

j

3..

CONTAINMENT ISOLATION i

j,:

l a.

Phase "A" Isolation i

1)

Manual.

2 1

2 1,2,3,4 18 I

l s

L Y'

2) From Safety Injection 2

1' 2

1,2,3,4 13 a

f.

U Automatic Actuation Logic

[

I t

L t'

Ne 3

- 0.

J s

t t

e

[

o I

i 2o j.

bJ CD -

)

F:

r a

?-

1 -.

TABLE 3.3-3 tCentinued) 1 L$

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION I

c..

MINIMUM i

d TOTAL NO.

CHANNELS CHANNELS APPLICABLE r

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION l'

w r

b.

. Phase "B" Isolation

'f 1

1). Manual.

2 sets of 2 1 set of 2 2 sets of 2 1,2,3,4 18 1

1 2

1,2,3,4 13 j

2) Automatic Actuation Logic 3 ) '. Containment'Pressu- -High-High 4

2 3

1,2,3 16 c.

Containment ventilat ".~ ' solation

' Ii; i

i 1}'. Manual 2

1 2

1,2,3,4 17 s

t s

2)- Automatic. Actuation Logic 2

1 2

1,2,3,4 13 w

. l I

+

5

3) Containment Atmosphere Gaseous per table 3.3-6 l

,[

Radioactivity-High l-2 3"

.(

i

.g o

3.

a 3

o d

3

. r+.

Z O. :

{

s-C.45 I

CD 4

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i

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am

m TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION t

c MINIMUM d

t'i' SD.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT FELS TO TRIP OPERABLE MODES ACTION 4.

STEAM LINE ISOLATION l

l a.

Manual 2/ steam line 1/ steam line 1/ operating 1,2,3 23 steam line t

b.

Automatic Actuation Logic 2***

1 2

1,2,3 20 c.

' Containment Pressure--High-High 4

2 3

1,2,3 16 l

d.

Steam Flow in Two Steam 2/ steam line 1/ steam line 1/ steam line 1,2,3##

14*

Lines--High any 2 steam

{

lines Y

COINCIDENT WITH EITHER

-n T

--Low-Low 1T

/ loop 1T in 1T in 1,2,2##

14*

1. 9

"#9 any 191 oops any 391 oops OR, COINCIDENT WITH l

Steam Line Pressure-Low I pressure /

1 pressure 1 pressure 1,2,3##

14*

loop any 2 loops any 3 loops i

i

!w k

n e

P t

I co

m TABLE 3.3-3 (Continued)

' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

~

c.

MINIMUM d'

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL' UNIT OF CHANNELS TO TRIP OPERt.BLE MODES ACTION il 5.

TURBINE TRIP & FEEDWATER ISOLATION a.

Steam Generator Water level--

3/ loop 2/ loop in 2/ loop in 1,2,3 14*

High-High any operating each operating loop loop 6.

SAFEGUARDS EQUIPMENT 3

2 3

1,2,3,4 13 CONTROL SYSTEM (SEC) 7.

UNDERVOLTAGE, VITAL BUS

- s a.

Loss of Voltage 1/ bus 2

3 1,2,3 14*

a.

Y b.

Sustained Degraded Voltage 3/ bus 2/ bus 3/ bus 1,2,3 14*

1 i

a a

4 a

bd LJ 00 i

'm

m TABLE 3.3-3 (Continued 1 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMEffTATION I

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE E

OF CHAMNELS TO TRIP OPERABLE MODES ACTION y

FUNCTIONAL UNIT 8.

AUXILIARY FEEDWATER a.

Automatic Actuation Logic **

2 1

2 1,2,3 20 b.

Manual Initiation 1/ pump 1/ pump 1/ pump 1,2,3 22 c.

Steam Generator Water Level--Low-Low 1

i.

Start Motor Driven Pumps 3/stm. gen.

2/stm. gen.

.1,2,3 14*

any stm. gen.

li.

Start Turbine Driven Pumps 3/stm. gen.

2/stm. gen.

1,2,3 14*

^

generator any 2 stm.

Y gen.

o d.

Undervoltage - RCP Start 4-1/ bus 1/2 x 2 3

1,2 19 Turbine - Driven Pump a.

S.I.

Start Motor-Driven Pumps See 1 above (All S.I.

initiating functions and requirements) f.

Trip of Main Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2 21*

Start Motor Driven Pumps g.

Station Blackout See 6 and 7 above (SEC and U/V Vital Bus) 5 aa E

z h

C en

.._m

=

..__s TABLE 3.3-3 fContinued)

TABLE NOTATION Trip function may be bypassed in this MODE below P-ll.

Trip function may be bypassed in this HODE below P-12.

The provisions of Specification 3.0.4 are not applicable.

Applies to Functional Unit 8 items e and d.

The automatic actuation logic includes two redundant solenoid operated vent valves for each Main Steam Isolation valve. One vent valve on any one Main Steam Isolation Valve may be isolated without affecting the function of the automatic actuation logic provided the remaining seven solenoid vent valves remain operable. The isolated MSIV vent valve shall be returned to OPERABLE status upon the first entry into MODE 5 following determination that the vent valve is inoperable.

For any condition where more than one of the eight solenoid vent valves are inoperable, entry into ACTION 20 is required.

ACTION STATEMENTS ACTION 13 -

With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 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 4.3.2.1.1.

ACTION 14 -

With the number of OPERABLE Channels one less than the Total Numbet of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, 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 15 -

NOT USED ACTION 16 -

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within 1. hour; one additional channel may be bypassed for up to l

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

ACTION 17 -

With less than the Minimum Channels _ OPERABLE, operation may l

continue provided the containment purge and exhaust valves are maintained closed.

I I

ACTION 18 -

With the number of OPERABLE Channels one less than the Total Number of Channels, 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 at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SALEM - UNIT 1 3/4 3-21 Amendment No. 138

m..

~-

TABLE 3.3-3 (Continued)

ACTION 19 -

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:

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 requiremahts ls 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 4.3.2.1.1 1

ACTION 20 -

With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing provided the other channel is OPERABLE.

l r

ACTION 21 -

With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:

a.

The inoperable channel is restored to OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or b.

If the affected Main Feedvater Pump is expected to be out l

of service for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the inoperable-channel-is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon the loss of the other Main ll Feedwater Pump.

ACTION 22 -

With the number of OPERABLE channels relating directly with the number of OPERABLE auxiliary feedwater pumps, the ACTIONS of L.C.O.

3.7.1.2 apply.

ACTION 23 -

With the number of OPERABLE channels one less than the Total Number of Channels, 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

l SALEM - UNIT 1 3/4 3-22 Amendment No.

138 l

c.

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATI(!H CONDITION AND SETPOINT EQ'CTION d

P-ll With 2 of 3 pressurizer P-:ll prevents or defeats pressure channels manual block of safety 2 1925 poig.

injection actuation on low pressurizer pressure.

P-12 with 3 of 4 T channels P-12 prevents or defeats

""9 2 545'F.

manual block of safety _

injection actuation high stes.m line flow and low steam line pressure.

With 2 of 4 T channels Allows manual block of

< 541*F.

"9 safety injection actuation on high steam line flow and low steam line pressure.

causes steam line isolation on high steam flow. Affects steam dump blocks.

SALEM - UNIT 1 3/4 3-22a Amondment No. 138 e

--T

tn TABLE 3.3 '[

E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

[

TRIP SETPOINTS 8

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

,. 3 --

l

+

- w 2.

CONTAINMENT SPKAY a.

. Manual Initiation Not Applicable Not Applicable i

b.

Automatic Actuation Logic Not Applicable Not Applicable 0

E c.

Containment Pressure--High-High 6 23.5 psig 6 24 psig i

3.

CONTAINMENT ISOLATION a..

Phase "A* Isolation I

i t

1..

Manual Not Applicable Not Applicable a

e 2.

'From Safety Injection Not Applicable Not Applicable Automatic Actuation Logic j

A I

b.

Phase *B" Isolation

'1.: : Manual Not Applicable Not Applicable 2.

Automatic. Actuation Logic Not Applicable Not Applicable 3.

Containment Pressure --

s 23.5 psig s 24 psig

.High-High c.

Containment Ventilation Isolation

[

3 c.

1.

' Manual Not Applicable Not Applicable et 2.

Automatic Actuation Logic Not Applicable Not. Applicable z-o

3.

Containment Atmosphere Gaseous Per Table 3.3 -

g

.[

Radioactivity l

0) i i

e.

v-i' 4

r-

m TABLE 3.3-4 (Continued)

E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION c

TRIP SETPOINTS

'd*

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

-l 4.

STEAM LINE ISOLATION a.

Manual Not Applicable Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High-High s 23.5 psig 6 24 peig d.

Steam Flow in Two Steam Lines--

6 a function defined as s a function defined as High coincident with follows: A Ap corresponding follows: a Ap corresponding T

-- Low-Low or-to 40% of full steam flow to 44% of full steam flow SEeSm Line Pressure Low between On and 20s load and between 01 and 20s load and

^

then a Ap increasing then a Ap increasing.

Y linearly to a Ap linearly to a Ap corresponding 7

U5 corresponding to 110% of to 111.5% of full steam flow full steam flow at full at full load.

load.

T 2 543*F T

2 541*F avg avg 2 600 psig steam line 2 579 peig steam line pressure pressure i

t t

3 an 00 '

I i

'w

m TABLE 3.3-4 (Continued)

E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

.g G"

FUNCTIONAL UNJJ TRIP SETPOINT ALLOWABLE VALUES l

9 5.

TURBIfC TRIP AND FEEDWATER ISOLATION A.

Steam Generator Water Level --

5 67% of narrow range s 68% of narrow range High-High instrument span each instrument span each steam generator steam generator 1

6.

SAFEGUARDS EQUIPMENT CONTROL Not Applicable Not Applicable SYSTEM (SEC) 7.

UNDERVOLTAGE, VITAL BUS

_i N

a.

Loss of Voltage 2 70% of bus voltage 2 65% of bus voltage A

Y b.

Sustained Degraded Voltage 2 91.6% of bus voltage for 2 91% of bus voltage for 5 13 seconds s 15 seconds

)

8.

AUXILIARY FEEDWATER a.

Automatic Actuation Logic Not Applicable Not Applicable I

b.

Manual Initiation Not Applicable Not Applicable I

c.

Steam Generator Water Level--

2 16% of narrow range 2 14.8%.of narrow range

' Low-Low instrument span each instrument span each steam generator steam generator f

d.

Undervoltage - RCP 2 70% RCP bus voltage 2 651. RCP bus voltage o

i a

t e.

S.I.

See 1 above (All S.I.

setpoints) l g

1 o

f.

Trip of Main Feedwater Pumps Not Applicable Not Applicable f

t g.

Station Blackout See 6 and 7 above (SEC and Undervoltage, Vital Bus) l

' a:

a

.h

(

e

~

rn TABLE 4.3-2 t1 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS cZ CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE CHECK CALIBRATION TEST REOUIRED FUNCTIONAL UNIT 1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

Manual Initiation N.A.

N.A.

R 1,2,3,4

b. Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3,4

c. Containment Pressure-High S

R M(3) 1,2,3 d.

Pressurizer Pressure--Low S

R M

1,2,3 w

b e.

Differential Pressure Between S

R M

1,2,3 Y

Steam Lines--High U

f. Steam Flow in Two Steam S

R M

1,2,3 Lines--High coincident with T

--Low-Low or S$Nm Line Pressure-Low 2.

CONTAINMENT SPRAY

a. Manual Initiation N.A.

N.A.

R 1,2,3,4

b. Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3,4

c. Containment Pressure--High-High S

R M(3) 1,2,3 b

m l3 Da a

u

tn TABLE 4.3-2 (Continued)

' ENGINEERED SAFETT FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS d

CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE l

FUNCTIONAL UN Q CHECK CALIBRATION TEST REOUIRED 3.

CONTAINMENT ISOLATION a.' Phase'"A" Isolation 1.

Manual N.A.

N.A.

R 1,2,3,4 2.

From Safety Injection N.A.

N.A.

M(2) 1,2,3,4 Automatic Actuation Logic Y

b. Phase "B" Isolation a

Y 1.

' Manual N.A.

N.A.

R 1,2,3,4 0

2.

Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3,4 i

3.

Containment. Pressure--

S R

M(3) 1,2,3 High-High

c. Containment Ventilation Isolation

+

1.

Manual N.A.

N.A.

R 1,2,3,4 L

2.

' Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3,4 3.

Containment A*mosphere Caseous Per table 4.3-3

' Radioactivity - High, o,

'a z

'P t;

e

~

c, TABLE 4.3-2 (Continued)

E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION c

SURVEILLANCE REOUIREMENTS 5"

CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST BEOUIRED

.[

4.

STEAM LINE ISOLATION r

a.

Manual N.A.

N.A.

R 1,2,3 b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3 I

c.

Containment Pressure--

.S R

M(3) 1,2,3 High-High d.

Steam Flow in Two Steam S

R M

1,2,3 Lines--High Coincident with Y

T-

--Low-Low or Steam Line PN0sure--Low 5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water S

R M

1,2,3 i

Level---High-High 6.

SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC) LOGIC y

a.

Inputs N.A.

N.A.

M(6) 1,2,3,4 l

b.

Logic, Timing and Outputs *.

N.A.

M(1) 1,2,3,4 l

7.

UNDERVOLTAGE, VITAL BUS

&f I

a.-

Loss of Voltage S

R M

1,2,3 f

b.

Sustained Degraded Voltage S

R M

1,2,3 U

m

tn TABLE 4.3-2 (continued)

M 3

e ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION c

SURVEILLANCE REOUIREMENTS d

9 CHANNEL MODES IN WHICH CHANNEL

-CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED 8.

AUXILIARY FEEDWATER

.a.

Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3 l

b. Manual Initiation N.A.

N.A.

M(5) 1,2,3

c. Steam Generator Water S

R M

1,2,3

'Leve1--Low-Low..

d. Undervoltage - RCP S

R M(2) 1,2 s

e. S.I.

See 1 above (All S.I.

surveillance requirements)

f. Trip of Main Feedwater hEDPS N.A.

N.A.

R 1

g. Station Blackout.

See 6b and 7 above (SEC and U/V Vital Bus) 8.

EP

.8a

.Z

?

e

- IA)1LE_4. 3-2 iContinued)-

TABLE NOTATION Outputs are up to, but not including, the output relays.

(1)

Each logic channel shall be tested at least once per 62 days on a-STAGGERED TEST BASIS. The CHANNEL FUNCTION TEST of each logic channel-chall verify that its associated diesel generator automatic load sequence timer is OPERABLE with the interval between each load block within 1 second of its design interval.

(2)

Each train or logic channni shall be tested at least every 62 days on a staggered basis.

(3)

The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by 2

applying either a vacuum or pressure to the appropriate side of the transmitter.

(4)

NOT USED (5)

The CHANNEL FUNCTIONAL TEST shall be conducted in conjunction with tho l

SORVEILLANCE REQUIREMENT OF 4.7.1.2.a.

(6)

Inputs from Undervoltage, Vital Bus, shall be tested monthly.

Inpute f rom Solid State Protection System shall be tested every 62 days on a STAGGERED TEST BASIS.

138 SALEM - UNIT 1 3/4 3-34 Amendment No.

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4 g

3.:' " D UNITED STATES E

NUCLEAR REGULATORY COMMISSION

d,,*. <

s, f WASHINGTON, D.C. 20566 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 o

License No. DPR 1.

The Nuclear Regulatory Commission (the Comission 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 August 14, 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' 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 the public;. and E.

The issuance of this amendment is in accordence 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 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:

l

,n

a,

(2) Technical Specif.ications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.116,- 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 h6 I

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

Attachment:

Changes to the Technical Specifications Date of Issuance: January 5, 1993

e, ATTACHMENT TO llCENSE AMENDMENT NO. 116 FACIllTY OPERATING llCENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:

Remove Paaes Insert Paaes 3/4 3-14 3/4 3-14 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16

~

3/4 3-17 3/4 3-17 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 3/4 3-23a 3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37

INSTRUMENTATI_QH 3/4.3.2 ENGINEEBED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.

APPLICABILITY: As shown in Table 3.3-3.

h hCTION:

With an ESFAS instrumentation channel trip setpoint less conservative a.

than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CRANNEL CALIBRATION and CHANNEL FUNCTIONAL TEET operations for the MODES and at frequencies shown in Table 4.3-2.

l 4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS 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 channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

SALEM - UNIT 2 3/4 3-14 Amendment No.

116 i

?

TABLE 3.3-3 m

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION i

M2 MINIMUM c

TOTAL NO.

CHANNELS CHANNELS APPLICABLE C

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1-1.

SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.

Manual Initiation 2

1 2

1,2,3,4 18 b.

Automatic Actuation Logic 2

1 2

1,2,3,4 13 c.

Containment Pressure-High 3

2 2

1,2,3 14*

t i

d.

Pressurizer Pressure-Low 3

2 2

1,2,3#

14*

e.

Differential Pressure Between 3/ steam line 2/ steam line 2/ steam 1,2,3##

~ 14*

Steam Lines - High any steam line

{

line Y

f.

Steam Flow in Two 2/ steam line 1/ steam line 1/ steam 1,2,3##

14*

b Steam Lines-High any 2 steam line lines COINCIDENT WITH EITHER 4

f, T

--Low-Low 1T

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

14*

- 9

- 9 any E91 oops in$ny 3 loops OR, COINCIDENT WITH Steam Line Pressure-Low 1 pressure /

1 pressure 1 pressure 1,2,3##

14*.

loop any 2 loops any 3 loops a

E e

8

~

W Ch E

5 W

~

,--~- -.... -.- _..

. v.

t This page is intentionally left blank.

SALEM

-UNIT 2 3/4 3-16

' Amendment no. 116

=4 g--

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y-sy w

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--ge-a p-

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-p-es-no 1m F**

W er

9 TABLE 3.3-3 (Continued) m ENGINEERED SAFETY'FERTURE ACTUATION SYSTEM INSTRUMENTRTION

td Q

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE e

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION g-2.

CONTAINMENT SPRAY n

4 a.

Manual 2 sets of 2 1 set of 2 2 sets of 2 1,2,3,4 18 s

b.

Automatic Actuation Logic 2

1 2

1,2,3,4 13 c.

Containment Pressure--High-High 4

2 3

1,2,3 16 3.

CONTAINMENT ISOLATION l

a.

Phase "A"' Isolation

1) Manual 2

1 2

1,2,3,4 18.

N 2)

From Safety Injection 2

1 2

1,2,3,4 13-4 Autornatic Actuation Logic 4

i i

f t

I t?

E m

k k

~

TABLE 3.3-3 (Continuedi ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION M3 MINIMUM k

c TOTAL NO.

CHANNELS CHANNELS APPLICABLE 3

' FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION d

4.

STEAM LINE ISOLATION a.

Manual

?/ steam line 1/ steam line 1/ operating 1,2,3 23 i

steam line

+

b.

Automatic Actuation Logic 2 ***

1 2

1,2,3 20 I

c.

Containment Pressure--

4 2

3 1,2,3 16 High-High d.

Steam' Flow in.Two 2/ steam line 1/ steam line 1/ steam line 1,2,3##

14*

I Steam Lines--High any 2 steam

{

lines Y

COINCIDENT WITH EITHER G

T

--Low-Low-1T

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

14*

""9

""9 any 391 oops any 391 oops OR, COINCIDENT WITH t

Steam Line Pressure-Low I pressure /

1 pressure 1 pressure 1,2,3##

14*

loop any 2 loops any 3 loops 4

4 l

e i

D j

4 u

Z W

oi' 5

4

TABLE 3.3-3 (Continued) m ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION s

MINIMUM i

TOTAL NO.

CHANNELS CHANNELS APPLICABLE c

d FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES

&CTION e

5. TUFCINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water 3/ loop 2/ loop in 2/ loop in I,2,3 14*

1evel--High-High any operating each operating loop loop 6.

SAFEGUARDS EQUIPMENT CONTROL 3

2 3

1,2,3,4 13 SYSTEM (SEC) 7.

UNDERVOLTAGE, VITAL BUS a.

Loss of Voltage I/ bus 2

3 1,2,3 14*

N b.

Sustained Degraded Voltage 3/ bus 2/ bus 3/ bus 1,2,3 14*

Y u

O 1

I, aa a

z

.O as h

TABLE 3.3-3 (Continued)'

m f

-ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.

M3 e

MINIMUM

c TOTAL NO.

CHANNELS CHANNELS APPLICABLE 3

FUNCTIONAL' UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION e

8.

AUXILIARY FEEDWATER

e.. - Automatic Actuation Logic **

2 1

2 1,2,3 20

,b.

Manual Initiation 1/ pump 1/ pump 1/ pump 1,2,3 22 c.

Stm. Gen. Water Level-Low-Low

i. Start Motor Driven Pumps 3/stm. gen.

2/stm. gen.

1,2,3 14*

any stm. gen, 11.-

Start Turbine Driven Pumps 3/stm. gen.

2/stm gen.

2/stm. gen.

1,2,3 14*

(

any 2 stm.

s gen.

Y U$

d.

Undervoltage - RCP Start 4-1/ bus 1/2 x 2 3

1,2 19 Turbine - Driven Pump e.

S.I.

Start Motor-Driven Pumps.

See 1 above (All S.I. initiat[ng functions and requirements) f.

Trip of Main Feedwater Pumps

2/ pump 1/ pump 1/ pump 1,2 21*

' Start Motor-Driven Pumps 9

Station Blackout' See (i and 7 above (SEC and UV Vital Bus) 9.

SEMIAUTOMATIC TRANSFER TO RSCIRCULATION E

a.

RWST Level Low 4

2

'3,

1,2,3 16

.. m I-b.

_ Automatic Actuation Logic; 2

1 2

1,2,3 13 0e

. 7.

o, I

l i

.ym.

.m XABLE 3.3-3 (Continued)

TABLE NOTATION I

Trip function may be bypassed in this MODE below P-ll.

Trip function may be bypassed in this MODE below P-12.

The provisions of Specification 3.0.4 are not applicable.

Applies to Functions,1 Unit 8 items e and d.

The automatic actuation logic includes two redundant solenoid operated vent valves for each Main Steam Isolation Valve.

One vent valve on any one Main Steam Isolation valve may be isolated without affecting the function of the automatic actuation logic provided the remaining seven solenoid vent valves remain operabla. The isolated MSIV vent valve shall be returned to OPERABLE status upon the first entry into MODE $ following determination that the vent valve is inoperable.

For any condition where more than one of the eight solenoid vent valves are inoperable, entry into ACTION 20 is required.

ACTION STATEMENTS ACTION 13 -

With the number of OPERABLE Channels one'less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 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 4.3.2.1.1 provided the l.

Other channel is OPERABLE.

ACTION 14 -

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 15 -

NOT USED ACTION 16 -

With the number of OPERABLE Channels one less than the Total

-Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated by CHANNEL CHECK within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; 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 l

Specification 4.3.2.1.1.

I ACTION 17 -

With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are maintained closed.

ACTION 18 -

With the number of OPERABLE Channels one less than the Total Number of Channels, restore the incperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the-following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SALEM - UNIT 2 3/4 3-22 Amendment No.

116

TABLE 3.3-3 (Continued)

ACTION 19 -

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 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 requirements 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 4.3.2.1.1.

ACTION 20 -

With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 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 I hour for surveillance testing provided the other channel is OPERABLE.

ACTION 21 -

With the number of OPERABLE che.nnels one less than the Minimum Number of Channels, operation may proceed provided that either:

a.

The inoperable channel is restored to OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b.

If the affected Main Feedwater Pump is expected.to be out of service for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the inoperable channel' is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon loss of the other Main Feedwater Pump.

ACTION 22 -

With the Number of OPERABLE channels relating directly with l

the number of OPERABLE. auxiliary feedwater pumps, the ACTIONS of L.C.O.

3.7.1.2 apply.

ACTION 23 -

With the number of OPERABLE channels one less than the Total l

Number of Channels, 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 at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SALEM - UNIT 2 3/4 3-23 Amendment No, 116

7ABLE 113-3 fcontinued).

0 ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATION-CONDITION AND SETPOINT EVNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats pressure channels 2 1925 manual block of safety psig.

injection actuation on low pressurizer pressure.

P-12 With 3 of 4 T che.nnels P-12 prevents or defeats

9 2 545'F.

manual block of safety injection actuation high steam line flow and low steam line pressure.

With 2 of 4 T channels Allows manual block of "9

< 541*F.

safety injection actuation on high steam line flow and low steam line pressure.

causen steam line isolation on high steam flow. Affects steam dump blocks.

SALEM - UNIT 2 3/4 3-23a Amendment No.

116

TABLE 3.3-4

'g e

ENGINEEFED SAFETY FEATUPE ACTUATION SYSTEM INSTPUMENTATION l

TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWAPLE VALUES c=

w d

2.

CONTAINMENT SPRAY n

a.

Manual Initiation Not Applicable Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High-High s 23.5 poig 6 24 psig 3.

CONTAINMENT ISOLATION a.

Phase A"

Isolation 1.

Manual Not Applicable Not Applicable w

N 2.

From Safety Injection Not Applicable Not Applicable Automatic Actuation Logic t.n b.

Phase *B-Isolation 1.

Manual Not Applicable Not Applicable 2.

Automatic Actuation Logic Not Applicable Not Applicable 3.

Containment Pressure --

s 23.5 psig s 24 psig High-High Centainment ventilation Isolation c.

E 1.

Manual Not Applicable Not Applicable e

D I

2.

Automatic Actuation Lugic Not Applicable Not Applicable Ov Per Table 3.3-6 W

3.

Containment Atmosphere Gaseous

$f Radioactivity w

w O

TABLE 3.3-4 tny ENGINEEFED SAFETY FEATURE ACTUATION SYSTEM INSTPUMENTATION y

TRIP SETPOINTS

.g.

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

-5

3 4.

STEAM LINE ISOLATION u

a.

Manual Not Applicable Not Applicable b.

Autorptic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure-High-High s 23.5 psig 6 24 psig d.

Steam Flow in Two Steam Lines-

$ a function defined as 6 a function defined as High Coincident with folicws: 'A Sp corresponding follows: ap corresponding I

T-

-- Low-Low or to 40s of full steam flow to 44% of full steam flow-S$b Line Pressure-Low between Os and 201L Icad and between On and 201L load and then a op increasing then a op increasing linearly

(

linearly to a ap to a ap corresponding to

'^

corresponding to 110% of 111.5% of full steam flow at Y

full steam flow at full full load.

M load.

T 2 543'F T

2 541'F avg avg 2 600 psig steam line 2 579 psig steam line pressure pressure 5.

TURBINE TRIP AND FEEDWATER ISOLATION a.

Steam Generator Water Level--

s 67% of narrow range s 681L of narrow range High-High instrument span each steam instrument span each generator steam generator 3

6._

SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC) Not Applicable not applicadi, o.

B

$n Z

?

O rn

~

- m.

~,

- - - -.. ~.., -., - -

t-I i

j TABLE 3.3-4 4

I UI l'

M-ENGINEERED SAtr.11 FEATURE ACTUATION SYSTEM INSTRUMENTATION l

f.

TRIP SETPOINTS i

y

.-3 1

e FUNCTIONAL UNIT' TRIP SETPOINT ALLOWABLE VALUES 5:

I' 7.

UNDERVOLTAGE, VITAL BUS l

- u t

i a.

Loss of voltage 2 70% of bus voltage 2 65% of bus voltage b.

Sustained Degraded voltage 2 91.6% of bus voltage for 2 91% of bus voltage for

[

q s 13 seconds s 15 seconds

.}

F 8.

AUXILIARY FEEDWATER f

i

}

a.

' Automatic Actuation Logic Not Applicable Not Applicable 4

+

)

j ;

b.

Manual Initiation Not Applicable Not Applicable i

t 4

'w 2 16% of narrow range 2 14.8 % of narrow range s

c.

' Steam Generator Water Level-s e

Low-Low instrument span each instrument span each w

6 steam generator steam generator t

i-u k

4" d.

Undervoltage - RCP 2 70% RCP bus voltage 2 65% RCP bus voltage f

1 i

t j

e.

S.I.

See 1 above (all S.I. setpoints) f.

Trip of Main Feedwater IbT Not Applicable Not Applicable f

I l

?

I l

g.

. Station. Blackout See 6 and 7 above (SEC and Undervoltage, Vital: Bus) f i.

9.

SEMIAUTOMATIC TRANSFER 7U RECIRCULATION i

1

- :p..

?

l g

a.

RWST' Low Level 15.25 ft. above 15.25 t 1 ft. above 3

Instrument taps instrument taps I

(D

- a b.

' Automatic Actuation Logic Not Applicable Not Applicable z

O 5

i r

H 9-*-

O..

g i

r

-y-

_~.

w n +

-,r-..

,,.---.m---.-

m

+-re-

TABLE 4.3-2 (Continued) tn i se ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 4

b SURVEILLANCE REQUIREMENTS i

x t

CHANNEL MODES IN WHICH ca: '

CHANNEL CHANNEL FtJNCTIONAL SURVEILLANCE L

L q

- U FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED E

l w

}_

3.

CONTAINMENT ISOLATION t

i i

L a.

Phase "A" Isolation i

l i'

1) Manual N.A.

N.A.

R 1,2,3,4

[

]

4 2)

From Safety Injection N.A.

N.A.

M(2) 1,2,3,4 j

Automatic Actuation Logic t

j b.

Phase

B" Isolation

[

u w

1) Manual N.A.

N.A.

R 1,2,3,4 N

i i

f

2) - Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3,4 i

w w

r

)

3). Containment Pressure--

S R

M(3) 1,2,3

[

High-High

{

1 l

c.

Containment ventilation Isolation f

j

1) Manual N.A.

N.A.

R 1,2,3,4 t-j

2) Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3,4 f

3) Containment Atmosphere Per table 4.3-3 j

Caseous Radioactivity - High i

5

s '

4 On i

i i

g-i f

l

Z 0

r i

w 1

i l

i.,

r i

i i.'

9 6

.m

-e...m-

,,,e

\\n-+.

n

,~

e e s

<e

~, - - -

,' ~~~

w

- - - - ~

~--=

=

TABLE 4.3-2 (Coatinued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTPUMINTATION N

SURVEILLANCE PEOUIREMENTS x

e CHANNEL MODES IN WHICH

c 3

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 9

FUNCTIONAL UNIT CHECK CALIBRATION TEST PEOUIRED n

4.

STEAM LINE ISOLATION a.

Manual N.A.

N.A.

R 1,2,3 b.

Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3 c.

Containment Pressure--

S R

M(3) 1,2,3 High-High d.

Steam Flow in Two Steam S

R M

1,2,3 Lines-High coincident with w

T

--Low-Low or Skb Line Pressure-Low g

[

Y w

5.

TURBINE TRIP AND FEEDWATEft ISOLATION a.

Steam Generator Water S

R M

1,2,3 Level-High-High 6.

SAFEGUARDS EQUIPMENT CONTROL SYSTEM (SEC) LOGIC a.

Inputs N.A.

N.A.

M(6) 1,2,3,4 b.

Logic, Timing and Outputs *

'N.A.

N.A.

M(1) 1,2,3,4 l

7.

UNDERVOLTAGE, VITAL BUS 5

g a.

Loss of Voltage S

R M

1,2,3 a3 b.

Sustained Degraded Voltage 5

R M

1,2,3 W

o,

TABLE 4.3-2 (Continued) in f

ENGINEEPED SAFETY FEATUPE ACTUATION SYSTEM INSTRUMENTATION

-Q SURVEILLANCE PIOUIREMENTS_

l I

e c

CHANNEL MODES IN WHICH 5

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE i

i.

6 FUNCTIONAL UNIT CHECK CALIBEATION TEST PEOUIFE f

j u

6 8.

AUXILIARY FEEDWATER t

.i Automatic Actuation Logic N.A.

N.A.

M(2) 1,2,3 a.

4 b.

Manual Initiation N.A.

N.A.

M(5) 1,2,3

[

t c.

Steam Generator Water S

R M

1,2,3 Level--Low-Low 1-j d.

Undervoltage - RCP S

R M

1,2 f

R e.

S.I.

See 1 above (All S.I. surveillance requirements)

I a

Y' f.

Trip of Main N.A.

N.A.

S/U(4) 1,2 i-Feedwater Pumps-I Li g.

Station Blackout See 6 and 7 above (SEC V,5 F/V Vital Bus) t a

f J'

9.

SEMIAUTOMATIC TRANSFER TO RECIRCULATION

'a.

RWST Low Level S

R M

1,2,3 j

j b.

Automatic Initiation Logic N.A.

N.A.

1,2,3,4

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i t

i F-U i

gs 6

9 a

l S

I N

12 O

e w

4, M

h O

IMLLAA2LLihn1111Mtd.1 IMLU12TM12!i Outputs are up to, but not including, the Output Pelays.

(1)

Each logic channel shall be tested at least once per 62 days on a STAGGERED 1EST DASIS. The CilA!4HEL FUNCTION TEST of each logic channel sha ll verif y that its associated diesel generator automatic load sequer ce timer is OPERABLE with the interval between each load block within 1 second of its design interval.

(2)

Each train or logic channel shall be tested at least every 62 days on a STAGGEREE TEST BASIS.

(3) The CHAliNEI TUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmittes.

(4)

If not performed in the previous 92 days.

(5)

The CilANNEl FUNCTIONAL TEST shall be conducted in conjunction with the SUHVEILLAN(E REQUIREMENT of 4.7.1.2.a (6)

Inputh f rori undervolt age, Vital Bus, shall be tested monthly.

Inputs from solid Sts.te Protection System, shall be tested every 62 days on a STAGGERED TEST DASIS.

SALEM - UNIT 2 3/4 3-37 Amendment No.

116

.. J

ML20127B743

Text

Attachment:

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