ML18094B328

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


Text

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.

I

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. *

(

3/4 3-53

TABlf 3.3-11 ACCJlINT MONITORING INSTRLMENTATJON c:: REQUIRE 0 MINIMLM z

H NO. OF NO. OF 1-i INSTRlJ4ENT CHANNELS CHANNELS ACT JON

1. Reactor Coolant Outlet Teq>erature - 2 1 I *' 2 e

lHOT (Wide Range)

2. Reactor Coolant Inlet Te-.>erature - 2 1 l, 2 TcoLD (Wide Range)
3. Reactor Coolant Pressure (Wide Range) 2 1 I* 2
4. Pressurizer Water ~vel 2 1 l* 2
5. Steam l1ne Pressure 2/Steam Generator l/Steam Generator 1, 2 w

I U1 6. Steam Generator Water ~vel (Narrow 2/Steam Generator l/Steam Generator l, 2

~

Range)

7. Steam Generator Water ~vel (Wide 4 (l/Steam Generator) 3 (I/Steam Generator) 1, 2 Range)
8. Refueling Water Storage Tank Water 2 1 I, 2

~vel

9. Boric Acid Tank Solution level 2 (l/tank) 1 (I/tank) 3
10. Auxiliary Feeclifater Flow Rate 4 (I/Steam Generator) 3 (I/Steam Generator) 4, 6
11. Reactor Coolant System Subcooling 2,> 1 ~

Margin Monitor l) 2

12. PORV Position lnd1 cato r 2 /vdlv e ** I, 2

TABLE 3.3-11 (Continued)

I ACCllINT MONITORING INSTRlMENTATION REQUIRED HIN 1Hlt4 c NO. OF NO. OF z

H 8

INSTRIJ4ENT CHANNELS CHANNELS ACT ION

13. PORV Block Valve Position Indicator 2/va 1ve** 1 1. 2 e
14. Pressurizer Safety Valve Position 2/valve** 1 1. 2 Indicator
15. Containment Pressure - Narrow Range 2 1 1. 2
16. Containment Pressure - Wide Range 2 1 1. 2 I. w
17. Containment Water Leve 1 -

Wide Range 2 1 7. 2 w

U1 I

18. Core Exit Thennocouples 4/core quadrant 2/core quadrant 1, 2 U1
19. Reactor Vessel Level Instrumentation 2 1 JL(]) 8 Syste* (RVLIS) I , '2.

(*)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.

(**)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

  • 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be i n HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 3 With the number of OPERABLE channels one less than the Required Numb er 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 Tab l e 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
  • TABLE 3.3-11 (continued )

TABLE NOTATION ACT ION 6 With the number of OPERABLE channels l ess than the Minimum Numb er of channe l s 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 ne xt 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACT ION 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 MOl:l: 5, COLD SHUTOOWN ).

f!. <i'4 I re.~ 0 ~

ACT ION 8 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 l ed CHANNEL CALIBRATION (which shall be performed upon the next entry in to MO Cl: 5, CO LO SHUT OOWN ) *
  • SA LEM - UNIT 1 3/ 4 3-56a
  • **
  • r ..

TAB LE 4. 3-11 SOOVE IllANCf REQUIREMENTS FOR ACCil£NT MONITORING INSTRlMENTATION c:

z H CHANNE l t-3 CHANNE l CHANNE l FUNCTIONAL INSTRl.HENT CHECKS CALIBRATION TEST I. Reactor Coolant Outlet Tentterature - M R NA THoT (Wide Range)

2. Reactor Coolant Inlet Tentterature - H R NA TcolD (Wide Range)
3. Reactor Coolant Pressure (Wide Range) H R NA
4. Pressurizer Water Level H R NA
5. Steam line Pressure H R NA w 6. Steam Generator Water level (Narrow H R NA Ul I Range)
7. .

Steam Generator Water level (W1de Range)

M R NA R , NA

8. Refue11ng Water Storage Tank Water M level
9. Bor1c Ac1d Tank Solut1on level H R NA IO. Aux11iary Feedwater Flow Rate SUI R NA
11. Reactor Coolant System Subcooling M N/A* NA Margin Monitor I/Auxiliary Feedwater System is used on each startup ctnd flow rctte indication is verified at that t illle
  • I th I' i t ctrt~ calibro!Pd on on Hl month cvrli>:

1111\Jl I\ r*

  • Jtii* instruments ust>d to dt.*velop RCS sullcoolinq mctrqin

t Ul

)JI t-<

TABlf 4.3-11 (CONTINlEO}

l:rJ SURV[ILLANC£ R£QOJR£M[NT~ FOR

~

ACCllENT RONJTORJNG INSTRl.M[NT~JTON CHANNEL c CHANNEL CHANNEL FUNCTIONAL z

H INSTRLMENT CHECK CALIBRATION TEST t-:J

...... 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 - Narr<M Range M NA NA w

~ 16. Containment Pires sure - W1 de Range M R NA w

Ul I

17. Containment Water Level - H R NA

-.J Ill Wide* Range

18. Core Exit Thermocouples M R NA
19. Reactor Vessel Leve 1 lnstrumentat ion M R NA System (RV LIS)

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

TAU lf 3.3-11 ACC I CENT MON HOR ING INSTRU4£NTATION c

z H

t-3 REQUIRED MIN 1Mlt4 NO. OF NO. OF INSTRU4ENT CHANNELS CHANNf LS ACT ION I. Reactor Coolant Outlet Teq>erature - 2 lHOT (Wide Range) 1 I. 2

2. Reactor Coolant Inlet Tellf)erature - 2 TCOlD (W1de Range) 1 1. 2
3. Reactor Coolant Pressure (Wide Range) 2 I I. 2
4. Pressurizer Water level 2 w 1 I. 2 I

Ul 5. Steam line Pressure 2/Steam Generator

...... I/Steam Generator 1. 2

6. Steam Generator Water level (Narrow 2/Steam Generator Range) I/Steam Generator I. 2
7. Stea* Generator Water level (Wide 4 (I/Steam Generator)

Range) 3 (I/Steam Generator) I. 2

8. Refueling Water Storage Tank Water level 1 I. 2
9. Boric Acid Tank Solution level 2 (I/tank) 1 (I/tank) 3
10. Auxiliary Feed.later Flow Rate 4 (I/Steam Generator) 3 (I/Steam Generator) 4. 6
11. Reactor Coolant System Subcoo11ng 2;/1- I.

Margin Mon Hor ~

J) 2.

12. PO RV Position Indi cator
1. 2

TABLE 3.3-11 (Continued)

ACCICENT MONITORING INSTRlMENTATION REQUIRE 0 MINIMlM c NO. OF NO. OF z INSTRLMENT H CHANNE l5 CHANNE l5 ACT ION 1-:3 N

13. PORV Block Valve Position Indicator 2/va lve** 1 1, 2
14. Pressurizer Safety Valve Position 2/valve** 1 1, 2 Indicator
15. Containment Pressure - Narr<M Range 2 1 1, 2 w 16. Containment Pressure - W1 de Range 2 1 1* 2

~

17. Containment Water level - 2 1 7, 2 w

I Wide Range lJl llJ 18. Core Exit Thermocouples 4/core quadrant 2/ core quadrant 1, 2

19. Reactor Vessel Level Instrumentation 2 1 --14)) 6 ~**

Syste1t (RVLIS) J :> 2.

(*)Tat al nwlllher af d 1annels is cans1de ref:J t a be t we (2) with ene (I) af the channel s be ing 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 Temperatu re 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 th e 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 2 With the number of OPERABLE accirlent monitoring channels less t han 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 Num ber 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
  • TAB LE 3.3-11 (continued)

TABLE NOTATION ACT ION 6 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACT ION 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 MO~ 5, COLD SHUTOOWN). Re.'1_111re.~ 1>r ACT ION 8 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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

,i*

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

c::

z CHANNEL H

t-3 CHANNEL CHANNEL FUNCT JONAL N

INSTRU4ENT CHECKS CALIBRATION TEST

1. Reactor Coolant Outlet Teq>erature - M R NA THoT (Wide Range)
2. Reactor Coolant Inlet Teq>erature - M R NA TCO LO (Wide Range)
3. Reactor Coolant Pressure (Wide Range) M R NA
4. Pressurizer Water Level M R NA w

I

5. Steam Line Pressure M R NA Vl N 6. Steam Generator Water Level (Narrow M R NA Range)
7. Steam Generator Water Leve 1 (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. Auxi 11ary Feed.later Flow Rate SUI R NA
11. Reactor Coolant System Subcooling H N/A* NA Margin Monitor
  1. Auxiliary FeecMater System is used on each startup dnd fl<M rate indication is verified at that time.

, . , I I '. . ........ -* .

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

.* * . . l . ~ .. ' 1 * '

'; ' I , ,,,,,,.

___J

("C'

  • 1,,.

~,

  • ~

1-Ul

~

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

t-:l INSTRlJ4ENT CHECK CALIBRATION TEST N

12.

13.

14.

PORV Position Indicator PORV Block Valve Position Indicator Pressurizer Safety Valve Position Indicator M

M M

NA NA NA Q

Q R

  • j
15. Containment Pressure - Narrow Range M NA NA w
16. Containment Pressure - Wide Range M R NA

~

17. Containment Water Level - M R NA w

I W1de Range U1 tJ iii

18. Core Exit Thermocoup 1es M R NA
19. Reactor Vessel Level Instrumentation M R NA System (RVLIS)
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