Text

Proposed Tech Specs Re Reactor Vessel Level Instrumentation Sys
	ML18094B328
Person / Time
Site:	Salem
Issue date:	02/23/1990
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18094B316	List: ML18094B315; ML18094B328;
References
	NUDOCS 9003090235
	Download: ML18094B328 (18)
	v • d • e

REVISED PAGES -

UNIT NO. l

tNSTIHMENTAT ION ACC I !:ENT MONITOR ING-INSTR LMENTATION LIM IT ING CONDIT ION FOR OPERATION 3.3.3.7 The acc.ident monitoring instrumentation channels shown in Table 3.3-11 shall be operable.

APPLICABILITY:

MOCES 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 CALIBRATION operations at the frequencies shown in Table 4.3-11.

(

SA LEM -

UN IT 1 3/4 3-53 I

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TABlf 3.3-11 ACCJlINT MONITORING INSTRLMENTATJON INSTRlJ4ENT

1. Reactor Coolant Outlet Teq>erature -

lHOT (Wide Range)

2. Reactor Coolant Inlet Te-.>erature -

TcoLD (Wide Range)

3. Reactor Coolant Pressure (Wide Range)

4.

Pressurizer Water ~vel

5. Steam l1ne Pressure

6. Steam Generator Water ~vel (Narrow Range)

7. Steam Generator Water ~vel (Wide Range)

8. Refueling Water Storage Tank Water

~vel

9. Boric Acid Tank Solution level

10. Auxiliary Feeclifater Flow Rate

11. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position lnd1 cator REQUIRE 0 NO. OF CHANNELS 2

2 2

2 2/Steam Generator 2/Steam Generator 4 (l/Steam Generator) 2 2 (l/tank) 4 (I/Steam Generator) 2,>

2/vdlve **

MINIMLM NO. OF CHANNELS 1

1 1

1 l/Steam Generator l/Steam Generator ACT JON I '

2 l, 2 I

2 l

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

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

~

l) 2 I, 2 e

I.

c z H

8 w

w I

U1 U1 TABLE 3.3-11 (Continued)

ACCllINT MONITORING INSTRlMENTATION INSTRIJ4ENT

13. PORV Block Valve Position Indicator

14. Pressurizer Safety Valve Position Indicator

15. Containment Pressure - Narrow Range

16. Containment Pressure - Wide Range

17. Containment Water Leve 1 -

Wide Range

18. Core Exit Thennocouples REQUIRED NO. OF CHANNELS 2/va 1 ve**

2/valve**

2 2

2 4/core quadrant I

HIN 1Hlt4 NO. OF CHANNELS ACT ION 1

1. 2 1

7. 2 2/core quadrant 1, 2

19. Reactor Vessel Level Instrumentation 2

1 JL(]) 8.. *.

Syste* (RVLIS)

(*)Total number of ehannels is considered to he twa (2) wtth ane (1) at the ehaAAels be1ng manual Ea1tw1at1en ~ 11eensed eentrel reem personnel ws1ng data fr9111 OPERABli w1de range ReaGtor Cool*nt Pressure and Te~erat~re along wtth Steam Tables as desGr1hed 1n ACTION 5.

I, '2.

(**)Total number of channels to be two (2) w1th one (1) of the channels be1ng any one (1) of the following alternate ineans for determining PORV. PORV Block. or Safety Valve pos1tion: Tailpipe Te~eratures for the valves. Pressurizer Relief Tank Teq>erature Pressur1zer Reltef Tank Level OPERABlI

e

INSERT A

(***)

Action 8 remains in effect until startup from the 10th refueling outage at which time, PSE&G will install the upgraded RVLIS.

Upon expiration, Actions 1 and 2 will apply.

TABlE 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 CPERABLE accident monitoring channels less than th e 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 i n 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 th at 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 no OPERABLE Auxiliary Feectwater Flow Rate channel

ACTION 5 With the number of OPERABLE channels less than the Required Number Jf Channels show in Table 3.3-11, operation may proceed provided tha t 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

ACT ION 6 ACT ION 7 ACT ION 8 TABLE 3.3-11 (continued )

TABLE NOTATION With the number of OPERABLE channels l ess than the Minimum Number of channe ls shown in Table 3.3-11, restore the inoperable channel (s ) to OPERABLE status within 7 days, or be in HOT SH UTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 MOl:l: 5, COLD SHUTOOWN ).

f!.

<i'4 I re.~ 0 ~

With the number of OPERABLE Channels one less than the "M inimum number of channels shCMn 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 th e Core Exit Thermocouples shown in Table 3.3-11 less than the Requi red Number of Channels, follow the associated Action Statement, and

2.

Restore the system to OPERAS LE status at the next schedu led CHANNEL CALIBRATION (which shall be performed upon the next entry into MO Cl: 5, CO LO SHUT OOWN )

SA LEM - UN IT 1 3/ 4 3-56a

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I Ul TAB LE 4. 3-11 SOOVE IllANCf REQUIREMENTS FOR ACCil£NT MONITORING INSTRlMENTATION INSTRl.HENT I. Reactor Coolant Outlet Tentterature -

THoT (Wide Range)

2. Reactor Coolant Inlet Tentterature -

TcolD (Wide Range)

3. Reactor Coolant Pressure (Wide Range)

4. Pressurizer Water Level

5. Steam line Pressure

6. Steam Generator Water level (Narrow Range)

7.

Steam Generator Water level (W1de Range)

8. Refue11ng Water Storage Tank Water level

9. Bor1c Ac1d Tank Solut1on level IO. Aux11iary Feedwater Flow Rate

11. Reactor Coolant System Subcooling Margin Monitor CHANNE l CHECKS M

H H

H M

M H

SUI M

CHANNE l CALIBRATION R

R R

R,

R R

N/A*

CHANNE l FUNCTIONAL TEST NA NA NA NA NA NA NA NA NA NA NA I/Auxiliary Feedwater System is used on each startup ctnd flow rctte indication is verified at that t illle

I

Jtii* instruments ust>d to dt.*velop RCS sullcoolinq mctrqin ctrt~ calibro!Pd on on Hl month cvrli>: th I' 1111\\Jl i t I\\ r*

r

Ul

)JI TABlf 4.3-11 (CONTINlEO}

t-<

l:rJ SURV[ILLANC£ R£QOJR£M[NT~ FOR

~

ACCllENT RONJTORJNG INSTRl.M[NT~JTON c

CHANNEL z

INSTRLMENT CHECK H

t-:J

12.

PORV Position Indicator M

13.

PORV Block Valve Position Indicator M

14. Pressurizer Safety Valve Position M

Indicator

15. Containment Pressure - Narr<M Range M

w

16. Containment Pires sure - W1 de Range M

~

w I

17. Containment Water Level -

H Ul

-.J Wide* Range Ill

18. Core Exit Thermocouples M

19. Reactor Vessel Leve 1 lnstrumentat ion 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 t

REVISED PAGES -

UNIT NOo 2

INSTRLMENTAT ION ACCHENT MONITORING INSTRlli1ENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be operable.

APPLICABILITY:

MOCES 1, 2, and 3.

ACT ION:

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 CHECIC and CHANNEL CA LIB~AT ION operations at the frequencies shown in Table 4.3-11

SA t.£M -

UN IT 2 3/4 3-50

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I Ul TAU lf 3.3-11 ACC I CENT MON HOR ING INSTRU4£NTATION INSTRU4ENT I. Reactor Coolant Outlet Teq>erature -

lHOT (Wide Range)

2. Reactor Coolant Inlet Tellf)erature -

TCOlD (W1de Range)

3. Reactor Coolant Pressure (Wide Range)

4. Pressurizer Water level

5.

Steam line Pressure

6.

Steam Generator Water level (Narrow Range)

7.

Stea* Generator Water level (Wide Range)

8. Refueling Water Storage Tank Water level

9. Boric Acid Tank Solution level

10. Auxiliary Feed.later Flow Rate

11. Reactor Coolant System Subcoo11ng Margin Mon Hor

12. PORV Position Indi cator REQUIRED NO. OF CHANNELS 2

2 2

2 2/Steam Generator 2/Steam Generator 4 (I/Steam Generator) 2 (I/tank) 4 (I/Steam Generator) 2;/1-MIN 1Mlt4 NO. OF CHANNf LS 1

1 I

1 I/Steam Generator I/Steam Generator 3 (I/Steam Generator) 1 1 (I/tank) 3 (I/Steam Generator)

I.

ACT ION I. 2

1. 2 I. 2 I. 2

1. 2 I. 2 I. 2 I. 2 3

4. 6

~

J) 2.

1. 2

c z H

1-:3 N

w

~

w I

lJl llJ

13.

14.

15.

16.

17.

18.

TABLE 3.3-11 (Continued)

ACCICENT MONITORING INSTRlMENTATION INSTRLMENT PORV Block Valve Position Indicator Pressurizer Safety Valve Position Indicator Containment Pressure - Narr<M Range Containment Pressure - W1 de Range Containment Water level -

Wi de Range Core Exit Thermocouples REQUIRE 0 NO. OF CHANNE l5 2/va lve**

2/valve**

2 2

2 4/core quadrant MINIMlM NO. OF CHANNE l5 ACT ION 1

1, 2 1

1

2 1

7, 2 2/ core quadrant 1, 2

19. Reactor Vessel Level Instrumentation 2

1

--14)) 6 ~**

Syste1t (RVLIS)

J :> 2.

(*)Tatal nwlllher af d 1annels is cans1deref:J t a be t we (2) with ene (I) af the channels being 1Ranua*l cal cwl at ten b,y li censed cent ral raelft persanne1 using f:Jata f r011 OPERABIE w1de range Reactor Coolant Pressure and Temperature along with Stea* Tabl es as ~es cr1bed in ACT ION 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 detennining PORV, PORV Block, or Safety Valve position: Tailpipe Teq>eratures for the valves, Pressurizer Relief Tank Teq>erature Pressurizer Relief Tank Level OPERABLE.

I

INSERT A

(***)

Action 8 remains in effect until startup from the 6th refueling outage at which time, PSE&G will install the upgraded RVLIS.

Upon expiration, Actions 1 and 2 will apply.

TABli 3.3-11 (continued)

TAB ti 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 SHUT OOWN 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 accirlent monitoring channels less than th e 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 sh()ltn in Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channe l 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 OPERATABLE Auxiliary Feea.tater Flow Rate Channel.

ACTION 5 With the number of OPERABLE channels less than the Required Numbe r of Channels shown in Table 3.3-11, operation may proceed provided t hat 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}

SA LEM - UNIT 2 3/4 3-Slb

ACT ION 6 ACT ION 7 ACT ION 8 TAB LE 3.3-11 (continued)

TABLE NOTATION With the number of OPERABLE channels less than the Minimum Number of channels shown i n 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 .

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 MO~ 5, COLD SHUTOOWN).

Re.'1_111re.~ 1>r With the number of OPERABLE Channels one less than th et' 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 i n Table 3.3-11 less than the Required Number of Channels, follow th e 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~ 5, COLD SHUTOOWN).

SA LEM - UN IT 2 3/4 3-5 lc

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TAB lf 4.3-11 SOOVE I UANCE REQUIREMENTS FOR ACCilfNT ~ORITORING INSTRU4ENTATIO~

CHANNEL CHANNEL CHANNEL FUNCT JONAL INSTRU4ENT CHECKS CALIBRATION

1. Reactor Coolant Outlet Teq>erature -

M R

THoT (Wide Range)

2. Reactor Coolant Inlet Teq>erature -

M R

T CO LO (Wide Range)

3. Reactor Coolant Pressure (Wide Range)

M R

4. Pressurizer Water Level M

R

5. Steam Line Pressure M

R

6. Steam Generator Water Level (Narrow M

R Range)

7. Steam Generator Water Leve 1 (Wide M

R Range)

8. Refueling Water Storage Tank Water M

R Level

9. Boric Acid Tank Solution Level M

R

10. Auxi 11ary Feed.later Flow Rate SUI R

11. Reactor Coolant System Subcooling H

N/A*

Margin Monitor

Auxiliary FeecMater System is used on each startup dnd fl<M rate indication is verified at that time.

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

lhe instruments used to develop HCS subcoolin9 mdrlJin dre calibrated on an 18 month cycle; the monitor I

,., I I

.* *.. l

~.. '

1

',i

ftf'

~ **

("C' '

1-

1,,.

~,

Ul

~

. t"i TABlf 4.3-11 ~CONTINLED) 1:11 s:

SURVEl[LANCE AE-DIREM[NTS FOR Act: I IENT MON JTOR ING INSTR U'l[Nll ITON c::

CHANNEL z

CHANNEL CHANNE n_

FUNCTIONAL I

H INSTRlJ4ENT CHECK CALIBRATION TEST j

t-:l N

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 - Narrow Range M

NA NA

16. Containment Pressure - Wide Range M

R NA w

~

17. Containment Water Level -

M R

NA w

W1de Range I

U1 tJ

18. Core Exit Thermocoup 1 es M

R NA iii

19. Reactor Vessel Level Instrumentation M

R NA System (RVLIS)

ML18094B328

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