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Proposed Tech Specs Adding Reactor Vessel Level Instrumentation Sys to Tech Spec Tables 3.3-11 & 4.3-11 & Table Notation Pages Associated W/Tech Spec 3.3.3.7,accident Monitoring Instrumentation
	ML18093A480
Person / Time
Site:	Salem
Issue date:	10/29/1987
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18093A479	List: ML18093A478; ML18093A480;
References
	NUDOCS 8711020418
	Download: ML18093A480 (15)
	v • d • e

INSTR l.MENTAT ION ACCirENT MONITORING INSTRl.MENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be operable.

APPLICABILITY:

MOIES 1, 2, and 3.

ACTION:

a.

As shown in Table 3.3-11.

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 OPERAS LE by performance of the CHANNEL CHECK and CHANNEL CA LISRAT ION operations at the frequencies shown in Table 4.3-11.

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U1 TAB IE 3.3-11 ACCIIENT MONITORING INSTRlJt1ENTATION INSTRlJo1ENT.

REQUIRED NO. OF CHANNELS

1. Reactor Coolant Outlet Temperature -

2 THOT (Wide Range) 2 *. Reactor Coolant Inlet Teq>erature -

2 TcoLD (Wide Range).

3. Reactor Coolant Pressure (Wide Range) 2

4. Pressurizer Water Level

5. Steam Line Pressure

6. Steam Generator Water Range)

Level (Narr<M

7. Steam Generator Water Level (Wide Range)

8. Refueling Water Storage Tank Water Level

9. Boric Acid Tank Solution Level IO. Auxiliary Fee<Mater Flow Rate lI. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator 2

2/Steam Generator 2/Steam Generator 4 (l/Steam Generator) 2 2 (I/tank) 4 (I/Steam Generator) 2*

2/va l ve**

MIN IMtJ.1 NO. OF CHANNELS ACTION I

l~ 2 I

1, 2 I

I, 2 l/Steam Generator 1, 2 1/Steam Generator I, 2 3 (I/Steam Generator) 1, 2 1

I, 2 I ( 1/tank) 3 3 (I/Steam Generator) 4, 6 I

4, 6 1

1, 2

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I Ul Ul TABl£ 3.3-11 (Continued)

ACCI((NT MONITORING INSTRU4ENTATION REQUIRED MINIMLM NO. OF NO. OF INSTRLMENT CHANNELS CHANNE l5 ACTION

13. PORV Block Valve Position Indicator 2/val ve**

1 1, 2

14. Pressurizer Safety Valve Position 2/val ve**

1 1, 2 Indicator

15. Containment Pressure - Narrow Range 2

1 I, 2

16. Containment Pressure - Wide Range 2

1 1, 2

17. Containment Water Level -

2 1

7, 2 Wide Range

18. Core Exit Thermocouples 4/core quadrant 2/core quadrant 1, 2

19. Reactor Vessel level Instrumentation 2

1 7, 8 System (RVLIS)

(*)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 OPERABl£ wide range Reactor Coolant Pressure and Temperature along with Steam Tables as described in ACTION 5.

(**)Total number of channels to be two (2) with one (1) of the channels being any one (1) of the following alternate means for determining PORV, PORV Block, or Safety Valve position: Tailpipe Temperatures for the valves, Pressurizer Relief Tank Teq>erature Pressurizer Relief Tank Level OPERABl£.

I I.

I

TAB LE 3.3-11 (continued)

TAB LE NOTATION ACTION 1 With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTOOWN 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 3.3-11, 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 SHUTOOWN 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 3.3-11, operation may proceed provided that the Boric Aci.d 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 3.3-11, operation 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 OPERABLE Auxiliary Feectwater Flow Rate channel.

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

a. Reactor Coolant Outlet Temperature - T HOT (Wide Range)

b.

Reactor Coolant Pressure (Wide Range)

SA LEM -

UN IT 1 3/4 3-56

TABLE 3.3-11 (continued)

TAB LE NOTATION ACTION 6 With the number of OPERABLE channels less than the Minimum Number of

_ channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTOOWN 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_3.3-11, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTOOWN).

ACTION 8 With the number of OPERABLE Channels one less than the Minimum number of channels shown in Table 3.3-11, either 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:

1.

Operation may proceed provided the Required Channels shown in Table 3.3-11 for the Reactor Coolant System Subcooling Margin Monitor and the Core Exit Thermocouples are OPERABLE.' With the number of OPERABLE channe 1 s for the Reactor Coo 1 ant Sy stem Subcooling Margin Monitor and the Core Exit Thermocouples shown in Table 3.3-11 less than the Required Number of Channels, follow the associated Action Statement, and

2.

Restore the system to OPERABLE status at the next scheduled CHANNEL CA LIB RAT ION (which sha 11 be perf orrned upon the next entry into MODE 5, COLD SHUTOOWN).

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2.

3.

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5.

6.

7.

8.

9.

TAB LE 4. 3-11 SURVEILLANCE REQUIREMENTS FOR ACCictNT MONITORING INSTRLMENTATION CHANNEL INSTRLMENT CHECKS Reactor Coolant Outlet Teq>erature -

M THoT (Wide Range)

Reactor Coolant Inlet Teq>erature -

M TcoLD (Wide Range)

Reactor Coolant Pressure (Wide Range)

M Pressurizer Water Level M

Steam Line Pressure M

Steam Generator Water Level (Narrow M

Range)

Steam Generator Water Level (Wide M

Range)

Refueling Water Storage Tank Water M

Level Boric Acid Tank Solution Level M

10. Auxiliary Fee<Mater Flow Rate SU#

11. Reactor Coolant System Subcooling M

Margin Monitor

CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST R

NA R

NA N/A*

NA

Auxiliary Feedwater System is used on each startup and fl ow rate i ndi cation is verified at that I

time.

The instruments used to develop RCS subcooling margin are calibrated o~ an 18 month cycle; the monitor will be compared quarterly with calculated subcoolinq marqin for known ~P~ values.

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i:ii TABlf 4.3-11 (CONTINUED~

t"1 tr:!

SURV[ I LLANCE RE001RtMtNTS FOR

s:

ACC I CENT MONITOR ING INSTR l.MtNT~ IlON CHANNEL q

CHANNEL CHANNEL FUNCTIONAL z

INSTRLMENT CHECK CA LIB RAT ION TEST H

8

12.

PORV Position Indicator M

NA Q

13.

PORV Block Valve Position Indicator M

NA Q

14. Pressurizer Safety Valve Position M

NA R

Indicator

15. Containment Pressure - NarrCM Range M

NA NA w

16. Containment Pressure - Wide Range M

R NA

~

w I

17. Containment Water Level -

M R

NA U1 Wide Range PJ

18. Core Exit Thermocouples M

R NA

19. Reactor Vessel Level Instrumentation M

R NA System (RV LIS)

REVISED PAGES -

UNIT NO. 2

INSTR LMENTAT ION ACC Il:ENT MON !TOR ING INSTR l.MENTAT ION LIMITING CONDITION FOR OPERATION

(.'>

3.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be operable.

APPLICABILITY:

MOIES 1, 2, and 3.

ACTION:

a.

As shown in Table 3.3-11.

b.

The provisions of Specification 3.0.4 are not applicable.

SURVE I Ll.ANCE REQUIREMENTS 4.3.3.7. Each accident monitoring instrumentation channel shall be demonstrated OPE RAB LE by performance of the CHANNEL CHECK and CHANNEL CA LIBBAT ION operations at the frequencies shown in Table 4.3-11.

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I U1 TAB LE 3. 3-11 ACClrENT MONITORING INSTRLMENTATION INSTRLMENT I. Reactor Coolant Outlet Temperature -

THOT (Wide Range)

2. Reactor Coolant Inlet Tenperature -

TcoLo (Wide Range)

3. Reactor Coolant Pressure (Wide Range)

4. Pressurizer Water Level

5. Steam Line Pressure

6. Steam Generator Water Level (Narr<M Range)

7. Steam Generator Water Level (Wide Range)

8. Refueling Water Storage Tank Water le\\'.el

9. Boric Acid Tank Solution Level IO. Auxiliary Feec:Mater Flow Rate II. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator REQUIRED NO. OF CHANNELS 2

2 2

2 2/Steam Generator 2/Steam Generator 4 (I/Steam Generator) 2 2 (I/tank) 4 (I/Steam Generator) 2*

2/va l ve**

(

MIN IML.f.1 NO. OF CHANNELS I

I I

I I/Steam Generator

.I/Steam Generator 3 (I/Steam Generator)

I I (I/tank) 3 (I/Steam Generator)

I.

1 ACTION I, 2 e

I, 2 I, 2 I, 2 1, 2 I, 2 I, 2 1, 2 3

4, 6 5, 6 1, 2

(*)Total number of channels is considered to be two (2) with one (I) 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 to be two (2) with one (I) of the channels being any one (I) of the following alternate means for determining PORV, PORV Block, or Safety Valve position: Tailpipe Tenperatures for the valves, Pressurizer Relief Tank Tenperature Pressurizer Relief Tank Level OPERABLE.

r'

TABLE 3.3-11 (~ontinued)

TAB LE NOTATION ACTION 1 With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-11, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in HOT SHUTOOWN 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 Mfnimum Number of Channels shown in Table 3.3-11, 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 SHUTOOWN 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 3.3-11, 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 3.3-11, operation 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 ao OPE RAT AB LE Auxiliary Feedwater Fl ow Rate Channel.

ACTION 5 With the number of OPERABLE channels less than the Required Number of

Channels shown in Table 3.3-11, operation may proceed provided that Steam Tables are available in the Control Room and the following Required Channels shown in Table 3.3-11 are OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:

a. Reactor Coolant Outlet Temperature - THQT (Wide Range)

b.

Reactor Coolant Pressure (Wide Range)

SALEM - UNIT 2 3/4 3-Slb

TAB lf 3.3-11 (continued)

TAB lf NOTATION ACTION 6 With the number of OPERABLE channels less than the Minimum Number of channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERAS LE status within 7 days, or be in HOT SHUTOOWN withi.n 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 3.3-11, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTOOWN).

ACTION 8 With the.number of OPERABLE Channels one less than the Minimum number of channels shown in Table 3.3-11, either 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:

1. Operation may proceed provided the Required Channels shown in Table 3.3-11 for the Reactor Coolant System Subcooling Margin Monitor and the Core Exit Thermocouples are OPERABLE.

With the number of OPERABLE channels for the Reactor Coolant System Subcooling Margin Monitor and the Core Exit Thermocouples shown in Table 3.3-11 less than the Required Number of Channels, follow the associated Action Statement, and

2.

Restore the system to OPERABLE status at the next scheduled CHANNEL CALIBRATION (which shall be performed upon the next entry into MO DE 5, COLD SHUT OOWN).

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I Ul IV TAB Lf 4.3-11 SURVEILLANCE REQUIREMENTS FOR ACCictNT MONITORING INSTRIJltENTATION CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRLMENT CHECKS CALIBRATION

1. Reactor Coolant Outlet Temperature -

M R

THoT (Wide Range)

2. Reactor Coolant Inlet Temperature -

M R

TcoLD (Wide Range)

3. Reactor Coolant Pressure (Wide Range)

M R

4. Pressurizer Water Level M

R

5. Steam Line Pressure M

R

6.

Ste~m Generator Water Level (Narrow M

R Range)

7.

Steam Generator Water Level (Wide M

R Range)

8. Refueling Water Storage Tank Water M

R Level

9. Boric Acid Tank Solution Level M

R

10. Auxiliary Fee<Mater Flow Rate SU#

R

11. Reactor Coolant System Subcooling M

N/A*

Margin Monitor

Auxiliary Fee<Mater System is used on each startup and flCM rate indication is verified at that time.

TEST NA NA NA NA NA NA NA NA NA NA NA

The instruments used to develop RCS subcooling margin are.calibrated or:i an 18 month cycle; the monitor will' be compared quarterly with calculated subcooling margrn for known rnput values.

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13.

14.

15.

16.

,17.

18.

19.

TAB I.I 4. 3-11 (CONT INLE D}

SURVtI[lANCt R~QDIRtMtNTS FOR ACCICENT MONITORING INSTRLMtNTAilON CHANNEL INSTRIJt1ENT CHECK PORV Position Indicator M

PORV Block Valve Position Indicator M

Pressurizer Safety Valve Position Indicator M

Containment Pressure - Narrow Range M

Containment Pressure - Wide Range M

Containment Water Level -

M Wide Range Core Exit Thermocouples M

Reactor Vessel Level Instrumentation M

System (RV LIS)

CHANNEL

CALIBRATION NA NA NA NA R

R R

R CHANNEL FUNCTIONAL TEST Q

Q R

NA NA NA NA NA 1l *-

t*

ML18093A480

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