Text

Proposed Tech Spec Adding Accident Monitoring Instrumentation & Radiation Monitoring Instrumentation,Per NUREG-0737 & Generic Ltr 83-37
	ML20093M038
Person / Time
Site:	Salem
Issue date:	09/21/1984
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18092A330	List: ML18092A329; ML20093M038;
References
	RTR-NUREG-0737, RTR-NUREG-737 GL-83-37, NUDOCS 8410190341
	Download: ML20093M038 (47)
	v • d • e

-

LTABLE-3.3-3 (Continued) j j0

' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM -INSTRUMENTATl'N N

MINIMUM sc

~

TOTAL NO.

' CHANNELS CHANNELS APPLICABLE i

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION a

2s b.

Phase "B" Isolation

1) Manual 2 sets of 2 1 set of 2 2 sets of 2 1, 2, 3,'4 18

2) Automatic 2

1 2

1, 2, 3,.4 13 Actuation Logic

3) Containment 4

2 3

1,2,3 16 Pressure--High-High 1"

c.

Purge and Exhaust Isolation ta de

1) Manual 2

1 2

1,2,3,4 17 m

2) Containment Atmo-per table 3.3-6 sphere Radioactivity-High 4.

STEAM LINE ISOLATION a.'

Manual 1/ steam line 1/ steam line 1/ operating 1, 2, 3 18 steam line b.

Automatic Actuation 2

1 2

1,2,3 13 Logic c.

Containment Pressure--

4 2

3 1,2,3 16 High-High 8410190341 840921 PDR ADOCK 05000272 P

PDR

L.-

TABLE 3.3-4 (Continued) ek us

-ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP'SETPOINTS-9 I

S ALLOWABLE VALUES-y FUNCTIONAL UNIT

' TRIP SETPOINT 2.

Containment Atmosphere per Table 3.3-6 Gaseous Radioactivity 4

STEAM LINE ISOLATION a.

Manual Not Applicable Not Applicable b.

Automatic Actuation Logic Not Applicable Not Applicable c.

Containment Pressure--High-High 5 23.5 psig 5 24 psig 5

d.

Stear. Flow in Two Steam Lines --

< A function defined as

< A function defined as.

Tollows: A Ap corresponding Tollows: A Ap corresponding HighCoincidentwithTavYow--low-low or Steam Line Pressure--

to 407. of full steam flow to 44% of full steam flow y

w betweem 0% and 20% load between 0% and 20% load and and then a'Ap increasing then a Ap increasing linearly linearly to a Ap correspond-to a Ap corresponding to ing to 110% of full steam 111.5% of full steam flow at flow at full load full load

> 543*F

-> 641 F TaNO psig steam line TaNO psig steam line pressure pressure 9

TABLE 4.3r2 -(Centinued)-

'f m

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 9

~ CHANNEL MODES IN WHICH FUNCTIONAL UNIT CHANNELS CHANNEL FUNCTIONAL SURVEILLANCE 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 b.

Phase "B" Isolation

1). Manual N.A.

N.A.

R 1, 2, 3, 4

2) Automatic Actuation Logic N.A.

N.A.

M(2)'

1, 2, 3, 4

3) Containment Pressure--

S R

M(3) 1, 2, 3 a

High-High w

,ontainment Ventilation Isolation C

c.

1) Manual N.A.

N.A.

R 1, 2, 3, 4 -

2) Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4

3) Containment Radioactivity --

per table 4.3-3 High L-

TABLE 3.3-6 m

R'ADIATION M0hiTORING INSTRlMENTATION-E MINIMUM g.

, INSTRUMENT CHANNELS APPLICABLE

. ALARM /TRI P E ASUREMENT-OPERABLE MODES SETPOINT

~ 4GE ACTION f

s

~

8 1.

AREA MONITORS e--

< 15 mR/hr -

10 104 nR/hr 19 a.

Fuel Storage Area - RS/R9 1

b.

Containment Area - R44 2

1, 2, 3 & 4 3103 R/hr

'l.

- 10 R/hr.

23 2.

PROCESS MONITORS a.

Containment

1) Gaseous Activity a)

Purge & Pressure -

l#

6 1 2 x' background 101 - 106 cpm 22 & 23 Vacuuin Relief and' m

N Isolation - R12a 1, 2, 3, 4 & S per Specification b) RCS Leakage 3.3.3.9 101 - 106 cpm 20

^

y Detection - R12a 1, 2, 3 & 4 N/A

2) Air Particulate Activity a)

Purge & Pressure -

1 6

1 2 x background 101 - 106 cpm 22 Vacuum Relief Isolation - Rila b) RCS Leakage 1, 2, 3 & 4 N/A 101 - 106 cpm 20 Detection - Rila b.

Noble Gas Effluent Monitors 3 23

1) Medium Range Auxiliary 1

1, 2, 3 & 4 1 3.0 x 10-2 uCi/cm3 10-3 _ 101 uCi/cm Building Exhaust System (Alarm only)

(Plant Vent) - R45B 2 uCi/cm3 10 106 uCi/cm3 23

2) High Range Auxiliary 1

1, 2, 3 & 4 1 1.0 x 10 Building Exhaust System (Alarm only)

(Plant Vent) - R4SC

With fuel in the storage pool or building.

The unit vent sampling monitor (R-41c) may also function in this capacity when the purge / pressure-vacuun relief isolation valves are open.

'~

.,_, 9 e,.

m TABLE 3.3-6 (CONTINUED) lE RADIATION MONITORING INSTRlMENTATION S

E MINIMUM INSTRUMENT CHANNELS APPLICABLE

. ALARM /TRI P MEASUREMENT g

OPERABLE MODES SETPOINT RANGE ACTION?

2.

PROCESS MONITORS h.

Noble Gas Effluent Monitors

3) Main Steamline 1/

1, 2, 3 & 4

< 10 nR/hr 1 - 104 nR/hr 23 Discharge (Safety MS Line Talarmonly)

Valves and Atmospheric Steam Dumps) - R46 l

4) Condenser Exhaust' 1

"1, 2, 3 & 4

< 1.27 x 104 cpm 1 - 106 cpm 23 System - Ris Talarm only)

N 9

9 9

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 19 -

With the number of channels OPERABLE less than n

. required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 22 -

With the number of channels OPERABLE less than required by the Minimun Channels OPERABLE requirement, comply with the ACTION requirements of Speci fication 3.9.9.

ACTION 23 -

With the number of OPERABLE Channels less than required by the Minimum Channels OPERARLE requirements, initiate the preplanned alternate method of monitoring the appropriate a

parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperabl'e Channel (s) to j

OPERABLE status within 7 days of the event, j

or i

2) prepare and subnit a Special Report to the Commission pursuant to Specification 6.9.2 I-within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SALEM - UNIT 1 3/4 3-37 0

e

i

~s[,3 W

TABLE 4.3-3 x:

R

$}

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE CNIREMENTS E

3:

- CHANNEL MODES IN WHICH INSTRUMENT CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE c:::

CHECKS CHECKS CAllBRATION TEST RE CEIRED Ei 1.

AREA MONITORS a.

Fuel Storage Area - RS/R9 S

M R

Q b.

Containment Area - R44 S

M R

Q 1, 2, 3 & 4 2.

PROCESS MONITORS a.

Containment Monitors

1) Gaseous Activity a)

Purge' & Pressure S

M R

Q 1,2,3,4,6&t Vacuum Relief Isolation - R12a b) RCS Leakage S

M R

Q 1, 2, 3 & 4 t'

Detection - R12a a

2) Air Particulate Activity ca a)

Purge & Pressure -

S M

R Q

1, 2, 3, 4 & 6 m

Vacuum Relief isolation - Rlla b) RCS Leakage S

M R

Q 1, 2, 3 & 4 Detection - Rlla b.

Noble Gas-Effluent Monitors

1) Medium Range Auxiliary S

M R

0 1, 2, 3 & 4 Building Exhaust System (plant vent) - R45B

2) High Range Auxiliary-S M

R Q

1, 2, 3 & 4 Building Exhaust System (plant vent) - R45C

With fuel in the storage pool or building.

e

.*:.. g un TABLE 4.3-3 (CONTINUEU)-

E g

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

c CHANNEL.

MODES'IN WHICH b

INSTRUMENT CHANNELS SOURCE CHANNEL'

. FUNCTIONAL SURVEILLANCE d

CHECKS CHECKS CAllBRATION TEST REQUIRED

~

H 2.

PROCESS MONITORS b.

Noble Gas Effluent Monitors

3) Main Steamline 0:scharge S

M R

Q 1, 2, 3'A 4 (Safety valves A atmospheric dumps) - R46

4) Condenser Exh. Sys. - R15

-S M

R Q

1, 2,'3 & 4 5

w 1

4 e

D o

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-11a and Table 3.3-11b chall be operable.

APPLICABILITY: - MODES 1, 2, and 3.

ACTION:

a.

As shown in Table 3.3-11a and' Table 3.3-11b.

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.3.7 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK AND CHANNEL CALIBRATION-operations at the frequencies shown in Table 4.3-11.

9 6

SALEM - UNIT 1 3/4 3-53 L

TABLE 3.3-lla ACCIDENT MONITORING INSTRUMENTATION TOTAL NO.

REQUIRED 0F NO. OF INSTRUMENT CHANNELS CHANNELS ACTION 4 (1/1oop) 2 1;

1.

Reactor Coolant Outlet Temperature -

T HOT (Wide Range) 2.

Reactor Coolant Inlet Temperature -

4 (1/ loop) 2 1

T COLD (Wide Range) 3.

Reactor Coolant Pressure (Wide Range) 2 2

1.

4.

Pressurizer Water Level 3 (hot) 2 1

y 5.

Steam Line Pressure 3/ Steam Generator 2/ Steam Generator 1

Y 6.

Steam Generator Water Level (Narrow 3/ Steam Generator 2/ Steam Generator l'

T Range) 7.

Steam Gene.ator Water Level (Wide 4/(1/ Steam Generator) 4 (1/ Steam Generator) 1 Range) 8.

Refueling Water Storage Tank Water 2

2 1

Level 9.

Boric Acid Tank Solution Level 2 (1/ tank) 2 (1/ tank )

3

10. Auxiliary Feedwater Flow Rate 4 (1/ Steam Generator) 4 (1/ Steam Generator) 4

11. Reactor Coolant System Subcooling 2*

2*

5 Margin Monitor 12.

PORY Position Indicator 2/ valve **

2/ valve **

1

7

.s..

c' +

~.

l m

g_

TABLE 3.3-11a (CONTINUED)

ACCIDENT MONITORING INSTRUMENTATION I

C TOTAL NO.

REf)UIRED l

8 0F NO. OF INSTRUMENT CHANNELS CHANNELS ACTION r

13. PORV Block Valve Position Indicator 2/ valve **

2/ valve **

1

14. Pressurizer Safety Valve Position 2/ valve **

2/ valve **

1' Indicator

15. Containment Pressure - Narrow Range 4

2 1

16. Containment Pressure - Wide Range 2

2 7

R

17. Containment Water Level -

2 2

7-Wide Range

18. Core Exit Thermocouples 65 4/ core quadrant 1

(*) Total number of channels is considered to be two (2) with one (1) of the channels being manual calculation by licensed control room personnel using data from OPERABLE wide ran<}e Reactor Coolant Pressure and Temperature along with Steam Tables as described in ACTION 5.

(**) Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of,the following alternate means of determining PORV, PORV Block, or Safety Valve position:

Tailpipe Temperatures for the valves, Pressurizer Relief fank Temperature Pressurizer Relief Tank Level Operable.

l

TABLE 3.3-11b ACCIDENT MONITORING INSTRUMENTATION TOTAL NO.

MINIMUM r

0F NO. OF INSTRUMENT CHANNELS CHANNELS ACTI0'N 1.

Reactor Coolant Outlet Temperature -

4 (1/ loop) 1 2

T HOT (Wide Range) 2.

Reactor Coolant Inlet Temperature -

4 (1/ loop) 1 2

l T COLD (Wide Range) 3.

Reactor Coolant Pressure (Wide Range) 2 1

2 4.

Pressurizer Water Level 3 (hot) 1 2

R 5.

Steam Line Pressure 3/ Steam Generator 1/ Steam Generator 2

y 6.

Steam Generator Water Le. vel (Narrow 3/ Steam Genarator 1/ Steam Generator 2

1 3

Range) 7.

Steam Generator Water Level (Wide 4/(1/ Steam Generator) 3 (1/ Steam Generator) 2 Range) 8.

Refueling Water Storage Tank Water 2

1 2

Level, 9.

Boric Acid Tank Solution Level 2 (1/ tank) 1 (1/ tank) 3

10. Auxiliary Feedwater Flow Rate 4 (1/ Steam Generator) 3 (1/ Steam Generator) 6

11. Reactor Coolant System Subcooling 2*

1 6

Margin Monitor

12. 90RV Position Indicator 2/ valve **

1 2

~

TABLE 3.3-llb (CONTINUED) 3 t'

ACCIDENT MONITORING INSTRUMENTATION TOTAL NO.

MINIMUM w-OF NO. OF U

INSTRUMENT CHANNELS CHANNELS ACTION

13. PORV Block Valve Position Indicator 2/ valve **

l' 2

14. Pressurizer Safety Valve Position 2/ valve **

1 2

Indicator

15. Containment Pressure - Narrow Range 4

1 2

16. Containment Pressure - Wide Range 2

1 2

w 2

];

17. Containment Water Level -

2 1

s Wide Range h

18. Core Exit Thermocouples 65 2/ core quadrant

~2 a

(*) Total number of channels is considered to be two (2) with one'(1) of the channels being manual calculation by licensed control room personnel using data from OPERABLE wide range Reactor Coolant Pressure and Temperature along with Steam Tables as described in ACTION 5.

(**) Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:

Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level Operable.

i 1

1 i

4 i

n TABLE 3.3-11a & b (continued)

' TABLE NOTATION ACTION 1 Witn tne' number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-11a, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 2 With the number'of OPERABLE accident monitoring channels less than the MINIMUM Number of Channels shown 'in Table 3.3-11b, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11a, operation may proceed provided that the Boric Acid. Tank associated with the remaining OPERABLE channel satisfies all requirements of

~

Specification 3.1.2.8.a.

ACTION 4 With the number of OPERABLE channels one-less than the Required Number of Channels shown in Table 3.3.11a, operations may proceed provided that an OPERABLE Steam Generator Wide Range Level channel is available as an alternate means of indication for the Steam Generator with no OPERATABLE Auxiliary Feedwater Flow Rate channel.

ACTION 5 With the number of. OPERABLE channels less than the Required Number of Channels show'in Table 3.3-11a, operation may proceed provided that Steam Tables are available in the Control Room and the following Required Channels shown in Table 3.3-11a are OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:

a.

Reactor Coolant Outlet Temperature - TH0T (WideRange)

~ b.

Reactor Coolant Pressure (Wide Range)

SALEM - UNIT 1 3/4 3-56 L

c

=..

f'~

t TABLE 3.3-11a & b (continued)

' TABLE NOTATION

-ACTION 6 With the number of OPERABLE channels less than the 4

Minimum Number of channels shown in Table 3.3-11b, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' ACTION 7 With the number of OPERABLE channels one less than

~

the Required Number of Channels shown in Table 3.3-11a, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTDOWN).

4 e

SALEM - UNIT 1 3/4 3/56a

TABLE 4,3-11 SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHANNEL CHANNEL FUNCTIONA g

INSTRUMENT CHECKS CAllBRATION TEST g

~

1.

Reactor Coolant Outlet Temperature -

M R

NA T HOT (Wide Range) 2.

Reactor Coolant inlet Temperature -

M R

NA T COLD (Wide Range)

-3. Reactor Coolant Pressure (Wide Range)

M R

NA 4.

Pressurizer Water Level M

R NA M

R-NA 5.

Steam Line Pressure 6.

Steam Generator Water Level (Narrow M

R NA g

Range)

Y 7.

Steam. Generator Water level (Wide M

R NA Range) 8.

Refueling Water Storage Tank Water M

R NA Level 9.

Boric Acid Tank Solution Level M

R NA

10. Auxiliary Feedwater Flow Rate SU#

R NA

11. Reactor Coolant System Subcooling M

N/A*

NA Margin Monitor

Auxiliary Feedwater System is used on each startup and flow rate indication is verified at that time.

The instruments used to develop RCS subcooling margin are calibrated on an 18 month cycle; the monitor will be compared quarterly with calculated subcooling margin for known input values.

TABLE'4.3-11 (CONTINUED)

SURVEILLANCE REQUIREMENTS FOR ACCIDENT MONITORING INSTRUMENTATION i

E N

CHANNEL H

CHANNEL CHANNEL FUNCT10NAl INSTRUMENT CHECK CAllBRATION TEST

12. PORY Position Indicator -

M NA Q

13. PORY Block Valve Position Indicator M

NA Q

14. Pressurizer Safety Valve Position M

NA -

R Indicator

15. Containment Pressure Narrow Range M

NA NA

16. Containment Pressure - Wide Range M

R NA 5

17. Containment Water Level -

M R'

NA

^

Y Wide Range

18. Core Exit Thermocouples M

R NA h

P e

e

t.

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION The radioactive gaseous effluent monitoring 3.3.3.9 instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of The alarm / trip setpoints Specification 3.11.2.1 are not exceeded.

of these channels shall be determined in accordance with the (0DCM).

APPLICABILITY: As shown in Table 3.3-13 ACTION:

With a radioactive gaseous effluent monitoring a.

instrumentation channel alarm / trip setpoint less conservative than required by the above specification,,

without delay suspend the release of radioactive gaseous effluents monitered by the affected channel or declare.

the channel inoperable or change the setpoint so it is acceptably conservative.

With less than the minimum number of radioactive gaseous b.

effluent monitoring instrunentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a timely manner, The provisions of Specifications 3.0.3, 3.0.4, and c.

6.9.1.9.b are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall.be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations at the f,requencies shown in Table 4.3-13 SALEM - UNIT 1 3/4 3-64 i

b

,--r--

,.,-,,-.,,,-,-ee n -,

r,w---~~--

n.--,. - --. -n n -,,v -,nc

.g _

..c 3.

TABLE 3.3-13 g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l

e E

~

MINIMUM y

INSTRUMENT CHANNELS OPERABLE APPLICABILITY ACTION 1.

WASTE GAS HOLDUP SYSTEM NobheGasActivityMonitor-Providing a.

Alarm and Automatic Termination of Release 1

-31,

(1-R41C) h.

Oxygen Monitor 1

35-2.

CONTAllMENT PURGE AND PRESSURE - VACUUM RELIEF-R a.

Mohle Gas Activity Monitor - Providing 1

34' Alarn and Automatic Termination of Release

{

(1-R41C or 1-R12A) w 3.

PLANT VENT HEADER SYSTEM #

a.

Noble Gas Activity Monitor (1-R16 or 1-R41C) 1 33 b.

Iodine Sampler 1

36 c.

Particulate Sampler 1

36 d.

Flow Rate Monitor 1

32 e.

Sampler Flow Rate Monitor 1

32

The following process strears are routed to the plant vent where they are ef fectively monitored by the instruments described:

(a) Condenser Air Renoval System (b) Auxiliary Building Ventilation System (c) fuel Handling Building Ventilation Systen (d) Radwaste Area Ventilation System (e) Containeent Purges Action item #34 applies to'the purging of the containment only.

TABLE 3.3-13 (Continuedl TABLE NOTATION

' With the number of channels OPERABLE less than ACTION 31 -

required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

l At least two independent sasples of the a.

tank's contents are analyzed, and At least two technically qualified members b.

of the Facility Staff independently varify the release rate calculations and discharge valving lineup; i

Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels OPERABLE less than ACTION 32 -

required by the Minimum Channels OPERA 8LE requirement, ef fluent releases via this ' pathway nuy continue provided the flow rate is estimated at least one.e per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With the number of channels OPERA 8LE less than ACTION 33 -

required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway rey continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and thess samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With the number of channels CPERABLE less than ACTION 34 -

required by the Minimum Channels OPERA 8LE requirement, immediately suspend PURGING of radioactive effluents via this pathway.

At all times, other than when the line is valved out and locked.

- During waste gas holdup system operation.

- - During containment purges or' containment pressure -

vacuum reliefs.

i i

SALEM - UNIT 1 3/4 3 66 G

j TABLE 3.3-13 (Continued)_

TABLE NOTATION With the number of channels OPERABLE less than ACTION 35 -

required by the Minimum Channels OPERABLE requirement, operation cf the waste gas holdup systen pay continue provided grab samples are collected at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With the mJmber of channels OPERABLE less than ACTION' 36 -

required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously

-collected with auxiliary sampling equipment as required in Table 4.11-2.

9 e

c 3/4 3-67 SALEM - UNIT 1

g

=

l

~

cn

' TABLE 4.3-13

.h RADIDACTIVE GASE00S' EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS c

CHANNEL MODES IN WHIC(

d INSTRUMENT CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE l

~d OPERABLE CHECK CALIBRATICN

-TEST -

REQUIRED H

1.

WASTE GAS HOLDUP SYSTEM a.

Noble Gas Activity Monitor -- Providing Alarm and Automatic Termination of Release P

P R(3)

Q(1)

.(1-R41C) b.

Oxygen Monitor D

N.A.

Q(4)

M 2.

CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF w

a.

Noble Ga Activity Monitor - Providing P

P R(3)

Q(1) 1 Alarm and Automatic Termination of Release (1-R41C or 1-R12A) 3.

PLANT VENT HEADER SYSTEM #

a.

Noble Gas Activity Monitor (1-R16 or 1-R41C)

D M

R(3)

Q(2) b.

Iodine Sampler W

N.A.

W N.A.

N.A.

c.

Particulate Sampler d.

Flow Rate Monitor D

N.A.

R N.A.

e.

Sampler Flow Rate Monitor W.

N.A.

R N.A.

The following process streams are routed to the plant vent where they are ef fectively monitored by the instruments described:

(a) Condenser Air Removal System (b) Auxiliary Building ' Ventilation System (c) Fuel Handling fluilding Ventilation System (d) Radwaste Area Ventilation System (e) Containment Purges

TABLE 4.3-13 (Continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate tnat automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

(Loss of Power) 3.

Instrument indicates a downscale failure.

(Alarm Only)

'(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditi,ons exist:

1.

Instrument indicates measured levels ibove the alarm / trip setpoint.

2.

Circuit failure.

(Loss of Power) 3.

Instrurent indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION was performed using appropriate. liquid or gaseous calibration sources obtained from reputable suppliers. -The activity of the calibration sources were reconfirmed using a multi-channel analyzer which was calibrated using one or more NBS standards.-

(4). The CHANNEL CALIBRATION shall include the use of standard

. gas samples containing a nominal:

1.

One volume percent oxygen, balance nitrogen, and 2.

Four-volume percent oxygen, balance nitrogen.

At all times

- During waste gas holdup system operation.

- *** During containment purge or containment pressure -

vacuum relief.

j

-SALEM - UNIT 1 3/4 3-69 e

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TABLE 3.3-3 (Continued)

~

-m ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g

MINIMUM c:.

TOTAL NO.-

CHANNELS CHANNELS APPLICABLE 3

FUNCTIONAL UNIT OF CHANNELS TO TRIP

'0PERABLE MODES ACTION a

w h.

Phase "B" Isolation

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

2) Automatic 2

1 2

1,2,3,4 13 Actuation Logic

3) Containment 4

2 3

1,2,3 16 Pressure--High-High

.c.

Containment Ventilation R

lsolation a

1) Manual 2

1 2

1,2,3,4 17 w

5

2) Automatic Actuation 2

1 2

1,2,3,4 13 Logic

3) Containment Atmo-per table 3.3-6 sphere Gaseous Radioactivity-High 4.

STEAM LINE ISOLATION a.

Manual 2/ steam line 1/ steam line 1/operati ng 1, 2, 3 21 steam line b.

Automatic Actuation 2

1 2

1, 2, 3 20 logic c.

Containment Pressure--

4 2

3 1,2,3 16 High-High

. =,

TABLE'3.3-4 (Continued)

. EI ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E'

x e-c

_ FUNCTIONAL UNIT TRI P SET POINT ALLOWABLE VALUES e

2.

Containment Atmosphere per Table 3.3-6 j;

w Gaseous Radioactivity 4.

STEAM LINE ISOLATION a.

Manual Not Applicable Not Applicable b.

Automatic Actuation Logic.

Not Applicable Not Applicable 1[

c.

Containment Pressure--High-High

< 23.6 psig

< 24 psig z.

w d.

Steam Flow in Two Steam Lines --

< A function defined as

< A function defined as A

follows: A Ap corresponding foll ows: A Ap corresponding High Coincident with Tor Steam Line Pressure--$ow-- low-low av to 40% of full steam flow to 44% of full steam flow betweem 0% and 20% load between 0% and 20% load and and then a Ap increasing then a Ap increasing linearly linearly to a Ap correspond-to a 4p corresponding to ing to 110% of full steam 111.5% of full steam flow at flow at full load full load

-> 541 F

> 543*F Ta500 psig steam line Ta500 psig steam line pressure pressure 4

a i

1

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE' ACTUATION SYSTEM INSTRUMENTATION.

m SURVEILLANCE REQUIREMENTS E'

1 CHANNEL MODES IN WHICH jj FUNCTIONAL UNIT.

CHANNELS CHANNEL FUNCTIONAL SURVEILLANCE CHECKS CALIBRATION TEST REQUIRED s-

"3

~

3.

CONTAINMENT 1 SOLATION-

.u a.

Phase "A" Isolation

1) Manual N.A.

N.A.

R 1, 2, 3, 4

2) From Safety injection h.A.

N.A.

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

Phase "B" Isolation fh

1) Manual N.A.

N.A.

R 1, 2, 3, 4 y

2). Automatic Actuation Logic N.A.

N.A.

M(2) 1, 2, 3, 4

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

2) Automatic Actuation Logic N.A.

N.A.

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

i

3) Containment Radioactivity --

per table 4.3-3 l

High l

4 k

1 3

l t

m

tn

' TABLE 3.3-6 g

g RADIATION MONITORING INSTRUMENTATION :

MININUM H

INSTRUMENT CHANNELS APPLICABLE ALARM /TRI P MEASUREMENT i

8 OPERABLE MODES SET POINT -

RANGE ACTION N

1.

AREA MONITORS

< 15 mR/hr 10 104 nR/h.

r.

23

a. - Fuel Storage Area - RS/R9 1

.107 R/h r 26 b.

Containment Area - R44 2

1, 2, 3 & 4

]103 R/hr 1

x 2.

PROCESS MONITORS a.

Containment

1) Gaseous Activity l

Vacuum Relief and

-< 2 x background a)

Purge & Pressure-1#

6 101 - 106 cpm 26 j

R Isolation - R12a 1, 2, 3, 4 & b per Specification j

b) RCS Leakage 3.3.3.9

^

u Detection R12a 1, 2, 3 & 4 N/A 101 - 106 cpm 24 j

u i

2) Air Particulate Activity a)

Purge & Pressure 1

6

< 2 x background 101 - 106 cpm 26 i

Vacuum Relief Isolation - Rlla f

b) RCS Leakage 1, 2, 3 & 4 N/A 101 - 106 cpm 24-Detection - Rlla i

b.

Noble Gas Effluent ~ Monitors

1) Mediur.i Range Auxiliary 1

1, 2, 3 & 4

< 3.0 x 10-2 uCi/cm3

'10-3 _ 101 uCi/cm3 26 Building Exhaust System

_ (Alarm only) j (Plant Vent) - R45B

2) High Range Auxiliary.

I l, 2, 3 & 4

< l.0 x 102 uCi/cm3 10-1 _ loS uCi/cm3 26 Building Exhaust System (Alarm only)

(Plant Vent) - R4bC i

i

With fuel in the storage pool or building.

The unit vent sampling monitor (R-41c) may also function in this capacity when the purge / pressure-vacuum relief isolation valves are open.

i-

' TABLE 3.3 (CONTINUED) tn RADIATION MONITORING INSTRUMENTATION i

j 9

MINIMUM ~

INSTRUMENT CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT OPERABLE MODES SETPOINT RANGE ACTION l.

y

2.. PROCESS MONITORS b.

Noble Gas Effluent Monitors i

3) Main Steamline 1/

1, 2, 3 & 4 10 mR/hr 1 - 104 nR/hr 26 Discharge (Safety '

MS Line (alarm only)

Valves and Atrospheric Steam Dumps) - R46

4) Condenser Exhaust-1 1,2,384

< 7.12 x 104 cpm 1 - 106 cpm ~

26 System - R15 (alarm only) l 5

a w

1 1

3 i

I

l

. ~.

^

TABLE.3.3-6 (Continued)_

\\

j TABLE NOTATION With the number of channels OPERABLE less than ACTION 23f-required by the Minimun Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With the number of channels OPERABLE less than ACTION 24 -

required hy the Minimum Channels GPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

With the number of channels OPERABLE less than ACTION 25 -

required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

With the number of OPERABLE Channels less than i

ACTION 26 -

required by the Minimum Channels OPERABLE requirements,. initiate the preplanned alternate i

method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) eithe~r restore the inoperable Channel'(s) to OPERABLE status within 7 days of the event,

'or i

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining

'the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

SALEM - UNIT 2 3/,4 3-40

~

e 9

h

--m^

r e-y,--

m r-,g-,,-

,,w---

e-

---e c-

--w------w,-w,

,-v-++,

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ow,w--a-

-w,www---,-n-r-,n,-,---

~

'l g.

TABLE 4.3-3 u)

RADI ATION MONITORING INSTRUMFNTATION ' SURVEILLANCE RE 0ulREMENTS E-CHANNEL MODES IN WHICH c

INSTRUMENT CHANNELS SOURCE

. CHANNEL FUNCTIONAL

-SURVEILLANCE E!

CHECKS CHECKS CALIBRATION TEST RE QUIRED "3

1.

AREA MONITORS w

.a.

Fuel Storage Area - RS/R9 S

M R

Q.

b.

Containment Area - R44 S

M R

Q 1, 2, 3 & 4' 2.

PROCESS MONITORS a.

Containment Monitors c

1)

Gaseous Activity a)

Purge & Pressure S

M R

Q 1, 2, 3, 4, 5 & 6 u,

];

Vacuum Relief Isolation - R12a I'

b) RCS Leakage S

M R

Q 1, 2, 3 & 4 Detection - R12a

2) Air Particulate Activity a)

Purge & Pressure' -

S M

R Q

1, 2, 3, 4 & 6 Vacuum Relief Isolation - Rila 1, 2, 3 & 4 b) RCS Leakage S

H R

Q Detection - Rlla b.

Noble Gas Effluent Monitors

1) Medium Range Auxiliary S

M R

Q 1, 2, 3 & 4 Building Exhaust System

~ (plant vent) - R45B

2) High Range Auxiliary S

M R

Q 1, 2, 3 & 4 Building Exhaust System (plant vent) - R45C

With fuel in the storage pool or building.

TABLE 4.3-3 (CONTINUED)

N 3: '

RADIATION MONITORING INSTRUMENTATION S'JRVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH -

U INSTRUMENT CHANNELS SOURCE CHANNEL FUNCTIONAL-SURVEILLANCE-CHECKS CHECKS CAllBRATION TEST REQUIRED u

2.

PROCESS MONITORS b.

Noble Gas Effluent Monitors

3) Main Steanline Discharge S

M R

Q 1, 2, 3 & 4 (Safety valves &

atmospheric damps) - R46 5

4) Condenser Exh. Sys. - R15 S

M R

Q 1, 2, 3 & 4 j

a Y

9 l

i 4

4 I

4

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION

- LIMITING-CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown. in Table 3.3-11a and Table 3.3-11b shall be operable.

' APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

As shown in Table 3.3-11a and Table 3.3-11b.

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.7

-Each accident monitoring instrumentation channel shall-be demonstrated.0PERABLE by - performance of, the CHANNEL CHECK AND CHANNEL CALIBRATION operations-at the frequencies shown in Table 4.3-11.

f s

b SALEM - UNIT 2-3/4 3-50

.4:

~

TABLE 3.3-11a, ACCIDEN1 MONITORING INSTRUMENTATION TOTAL NO.

REQUIRED 0F NO. OF-INSTRUMENT CHANNELS CHANNELS ACTION 1.

Peactor Coolant Outlet Temperature -

'4 (1/ loop) 2 1

I HOT (Wide Range) 2..

Reactor Coolant Inlet' Temperature -

4 (1/ loop) 2 1

.T COLD (Wide Range)

, 3.

Reactor Coolant Pressure (Wide Range) 2.

2-1 4.

Pressurizer Water Level 3 (hot) 2 1.

}

5.

. Steam Line Pressure 3/ Steam Generator 2/ Steam Generator 1

Y 6.

Steam Generator Water Level (Narrow 3/ Steam Generator 2/ Steam Generator 1

Range) 7.

Steam Generator Water Level (Wide 4/(1/ Steam Generator) 4 (1/ Steam Generator) 1 Range')

8.

Refueling Water Storage Tank Water 4

2 1~

Level 9.

Boric Acid Tank Solution' Level 2 (1/ tank) 2 (1/ tank) 3 10.

Auxiliary Feedwater Flow Rate 4 (1/ Steam Generator.)

4 (1/ Steam. Generator) 4

11. Reactor Coolant System Subcooling 2*

2*

5 Margin Monitor 12.

PORV Position Indicator 2/ valve **

2/ valve **

.1

1 TABLE 3.3-11a (CONTINUED) un

>e ACCIDENT MONITORING INSTRUMENTATION TOTAL NO.

REQUIRED C

0F NO. OF 8

CHANNELS CHANNELS ACTION INSTRUMENT w

13. PORV Block Valve Positinn Indicator 2/ valve **

2/ valve **

1

14. Pressurizer Safety Valve Position 2/ valve **

2/ valve **

1 Indicator

15. Containment Pressure - Narrow Range 4-2 1

16.

Containment Pressure - Wide Range 2

2 7

);

17. Containment Water Level -

2 2

7-i u>

Wide, Range i

65 4/ core quadrant 1

p

18. Core Exit T;iermocouples 9

(*) Total number of channels is considered to be two (2) with one (1) of the channels being manual

~

calculation by licensed control room personnel using data from OPERABLE wide range Reactor Coolant i

Pressure and Temperature along with Steam Tables as described in ACTION 5.

4 I

(**) Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block,dpr Safety Valve position:

l Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature, Pressurizer Relief Tank o

Level Operable.

i l

J

k TABLE 3.3-11b 9-ACCIDENT MONITORING INSTRUMENTATION TOTAL NO..

MINIMUM N

OF N0. OF.

l INSTRUMENT CHANNELS' CHANNELS ACTION

1. leactor' Coolant Outlet Temperature -

4 (1/ loop) 1 2.

T HOT (Wide Range) 1 2

j 2.- Reactor Coolant Inlet Temperature -

4 (1/ loop)

T COLD (Wide Range)

3.. Reactor Coolant Pressure (Wide Range) 2 1

2 i

4.

Pressurizer Water Level 3 (hot) 1 2

g E.

Steam Line Pressure 3/ Steam Generator 1/ Steam Generator 2

)

Y 6.

Steam Generator Water Level (Narrow 3/ Steam Generator 1/ Steam Generator 2

j g

Range) 7.

Steam Generator Water Level. (Wide 4/(1/ Steam Generator) 3 (1/ Steam Generator) 12 Range) 8.

Refueling Water Storage Tank Water 4

1 2

l Level 9.

Boric Acid Tank Solution Level 2 (1/ tank) 1 (1/ tank )

3

- 10. Auxiliary Feedwater Flow Rate 4 (1/ Steam Generator) 3 (1/ Steam Generator) 6 i

11. Reactor Coolant System Subcooling 2*

1 6

Margin Monitor

12..PORV Position Indicator 2/ valve **

1 2

e O

TABLE 3.3-llb (CONTINUED)

~'

hI, ACCIDENT MONITORING INSTRUMENTATION 5

TOTAL NO.

MINIMUM N

OF~

NO. OF INSTRUMENT CHANNELS CHANNELS ACTION 13.

PORV Block Valve Position Indicator 2/ valve **

1 2

14. Pressurizer Safety Valve Position 2/ valve **

1 2

Indicator

15. Containment Pressure - Narrow Range 4

1

.2

16. Containment Pressure - Wide Range 2

1 2

~

17. Containment Water Level -

2 1

2 4[

Wide Range a

y

18. Core Exit Thermocouples 65 2/ core quadrant-2 j

$o

(*) Total number of channels is considered to be two (2) with one (1) of the channels being manual dalculation by licensed control room personnel using data from OPERABLE wide range Reactor Coolant l

Pressure and Temperature along with Steam Tables as described in ACTION 5.

(**) Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alternate means of determining PORV, PORV Block, or Safety Valve position:

4 Tailpipe Temperatures for the valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level Operable, L

r'

~.

4 TABLE 3.3-11a & b (continued)

TABLE NOTATION ACTION 1-With the number of OPERABLE accident enitoring channels less than the Required Numbar of Channels shown in Table 3.3-11a, restore the inoperable channel (s) to OPERABLE status within 7 days, or be

. in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 2 With the number of OPERABLE accident monitoring channels less than the MINIMUM Number of Channels shown in Table 3.3-11b, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

r ACTION 3.

With the numbe'r of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11a, operation may proceed provided that the Boric Acid Tank associated with the remaining 0PERABLE channel satisfies all requirements of Speci fication 3.1.2.8.a.

ACTION 4 With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3.11a, operations may proceed provided that an.

OPERABLE Steam Generator Wide Range Level channel is available as an alternate means of indication for the Steam Generator with no 0PERATABLE Auxiliary Feedwater Flow Rate channel.

ACTION 5 With the number of OPERABLE channels less than the Required Number of Channels show in Table 3.3-11a,

- operation may proceed provided-that Steam Tables are available in the Control Room and the following Required Channels shown in Table 3.3-11a are

- OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:

a.

Reactor Coolant Outlet Temperature - TH0T (WideRange) b.

Reactor Coolant Pressure (Wide Range) o l

i SALEM - UNIT 2 3/4 3-51d e-v--

c

.---g y-v4y,#

, - - - ---m.---+,,ew-e-w-s-

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

,,,,e--,-

.+

w+3,

TABLE 3.3-11a & b (continued)

TABLE NOTATION ACTION 6 With the number of OPERABLE channels less than the Minimum Number of channels shown in Table 3.3-11b, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in HOT SHOT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 7 With the number of OPERABLE channels one less than

'the Required Number of Channels shown in Table 3.3-11a, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTDOWN).

l

-SALEM - UNIT 2 3/4 3-51e L_

q

.3

~ [';

1

. [, c TABLE 4.3 41, SURVEILLANCE REQUIREMENTS FOR

. ACCIDENT MONITORING INSTRUMENTATION CHANNEL

~ CHANNEL CHANNEL FUNCTIONA INSTRUMENT CHECKS CALIBRATION

~ TEST H w

1.. Reactor: Coolant Outlet Temperature

~ M R

NA -

T HOT (Wide Range) 2.

Re' actor Coolant Inlet Temperature -

.M R

NA' T COLD (Wide Range) 3.

Reactor Coolant Pressure (Wide Range).

M R'

.NA 4.

Pressurizer Water Level M

R NA.

5.

Steam Line Pressure M.

R NA 6.

Steam Generator Water Level (Narrow M

R NA y

Range) e b

y 7.

Steam Generator Water Level (Wide M

R NA g

Range) 8.

Refueling Water Storage Tank Water M

R NA Level 9.

Boric Acid Tank Solution Level M

R NA

10. Auxiliary Feedwater Flow Rate SU#

R NA

11. Reactor Coolant System Subcooling M

N/A*

NA' Margin Monitor

Auxiliary Feedwater System is used on each startup and flow' rate indication is verified at that time.

The instruments used to develop RCS subcooling margin are calibrated on an 18 month cycle; the monitor will be compared quarterly with calculated subcooling margin for known input values.

i.

Div

_,..-a f.

TABLE 4.3-il:(CONTINUED)

~

g SURVEILLANCE REQUIREMENTS FOR ~

ACCTUENT MONITORING INSTRllMENTATION.

CHANNEL CHANNEL CHANNEL FUNCTIONA INSTRUMENT CHECK CAllBRATION

' TEST.

i

'12 ' PORV. Position Indicator M

NA Q-

13. PORV Block Valve Position Indicator M

NA iQ l'4.

Pressurizer Safety Valve Position M

NA R'

Indicator

15. Containment Pressure - Narrow Range M

NA NA

16. Containment Pressure - Wide Range M

R NA s

17. Containment Water Level -

M R

NA.

Y Wide Range U*

18. Core Exit Thermocouples M

R NA 4

e t

=

o i

4

. x.*

,. ;_. g

.. +.

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints

- of these channels shall be determined in accordance with the (00CM).

APPLICABILITY: As shown in Table 3.3-13

' ACTION:

a.

With a radioactive gaseous effluent monitoring 4

instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is ac'ceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring ' instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to return the instrument to operable status within 30 days and, if unsuccessful, explain in the next semi-annual radioactive effluent release report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3,'3.0.4, and 6.9.1.9.b are not applicable.

(

i l'

SURVEILLANCE REQUIREMENTS l

4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by-performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL yj' CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

i j

SALEM - UNIT 2 3/4 3-59 i

I-l w~

w

,,.,,----.-~r-.u,

,,,-,,,n,n

..,,,,e,n,,

,,,am..,n,,

.---,----wen,-,r,-

.,,,,..,,,.,n_.,,.,.,

l v

e.*

. TABLE 3.3-13 G

3:

'RADI0 ACTIVE' GASEOUS EFFLUENT MONITORING INSTRUMENTATION I.

'S MINIMUM-M

. INSTRUMENT'

CHANNELS UPERABLE-APPLICABILITV ACTIO N '-

I 1.

WASTE GAS HOLDUP SYSTEM a.

Noble G~as Activity Monitor -'Providing 31.

Alarm and Automatic Termination of Release l'

(2-R41C) b.

Oxygen Monitor 1

35 2.

CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF 34

a.. Noble Gas Activity Monitor - Providing 1

R Alarm and Automatic Termination of Release (2-R41C or 2-R12A).

I w

l 1

3.

PLANT VENT HEADER SYSTEM #,

1 o

a.

Noble Gas Activity Monitor (2-R16 or 2-R41C) 1 33

]

i b.

Iodine Sampler 1

36.

I f

c.

Particulate Sampler 1

36 d.

Flow Rate Monitor 1

32 e.

Sampler Flow Rate Monitor 1

32.

l l

The following process streams are routed to the plant vent where. hey are effectively monitored by j

the instruments described:

I (a) Condenser Air Removal System 1

(b) Auxiliary Building Ventilation System (c) Fuel Handling Building Ventilation System (d) Radwaste Area Ventilation System (e) Containment Purges l

Action item #34 applies to the purging of the containment only.

c.. m.

*-- ja.=._

. TABLE 3.3-13 (Continusd).

TABLE NOTATION ACTION 31 -

.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE

. requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:

~

a.

At least two independent samples of the tank's contents are -analyzed, and b.

'At least two technically qualified members of the Facility Staff independently verify

- the release rate calculations and discharge valving lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 32 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE.

requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once'per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 33 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via. this pathway-nmy continue provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 34 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGIt:G of radioactive effluents via this pathway.

At all tines, other than when the line is valved out and locked.

- During waste gas holdup system operation.

i i

- - During containment purges or containment pressure -

i vacuum reliefs.

SALEM -' UNIT 2 3/4 3-61 I

I 1

y -

r +- -

,..~,-r.---

y-.-,w.-,yv,,,__,-,,-,-

.--.--.,w,--...w_-+,-,e-

-.,_---,-,-i.-e-._,..._-

e a s

_a

- p,;.,

TABLE 3.3-13 (Continued)

TABLE NOTATION ACTION 35 -

With the number of channels 0PERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the waste gas holdup system ney continue provided grab samples are collected at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 36 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway rey continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2 O

e SALEM - UNIT 2 3/4-3-62

c; i,

TABLE 4.3-13 t'

RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

CHANNEL MODES IN WHIC E

INSTRUMENT CHANNELS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE y

OPERABLE CHECK Call 8 RAT 10N TEST REQUIRED 1.

WASTE GAS HOLOUP SYSTEM y

a.

Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release P

P R(3)

Q(1)

(2-R41C) b.

Oxygen Monitor D

N.A.

Q(4)

M 2.

CONTAINMENT PURGE AND PRESSURE - VACUUM RELIEF l

a.

Noble Gas Activity Monitor - Providing P

P R(3)

Q(1)

Alarm and Automatic Termination of Release w

}

(2-R41C or 2-R12A) n Y

3.

PLANT VENT HEADER SYSTEM #

a.

Noble Gas Activity Honitor (2-R16 or 2-R41C)

D M

R(3)

Q(2) j

~

b.

lodine Sampler W

N.A.

N. A.

c.

Particulate Sampler W

N.A.

d.

Flow Rate Monitor D

N.A.

R N.A.

e.

Sampler Flow Rate Monitor W

N.A.

R N.A.

The following process streams are routed to the plant vent where they are effectively monitored by the instruments described:

(a) Condenser Air Removal System (b) Auxiliary Building Ventilation System (c) Fuel Handling Building Ventilation System (d) Radwaste Area Ventilation System (e) Containment Purges

'. - S',A..

, TABLE 4.3-13 (Continued)

TABLE NOTATION

~(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of'this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarn/ trip setpoint.

2.

Circuit failure.

(Loss of Power) 3.

Instrunent indicates a downscale failure.

(Alarm Only)

(2)- The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

(Loss of Power) 3.

Instrunent indicates a. downscale failure.

4.. Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION was performed using appropriate liquid or gaseous calibration sources obtained from reputable suppliers. The activity of the calibration sources were reconfirmed using a multi-channel analyzer which was calibrated using one or more NBS standards.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

One volune percent oxygen, balance nitrogen, and 2.

Four volume percent oxygen, balance nitrogen.

At all times

- During waste gas holdup system operation..

- - During containment purge or containment pressure -

. vacuum reliefs.

SALEM -' UNIT 2 3/4 3-64

-s

ML20093M038

Text

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