ML18100A492

Proposed Tech Spec Change Deleting Line Item 9 of TS 3.3.3.7,Post Accident Monitoring Sys,Table 3.3-11 & 4.3-11

ML18100A492
Person / Time
Site:	Salem
Issue date:	07/19/1993
From:	Public Service Enterprise Group
To:
Shared Package
ML18100A491	List: ML18100A490 ML18100A492
References
NUDOCS 9307280060
Download: ML18100A492 (6)

Text

TABLE 3. 3-11 ACCIDENT MONITORING INSTRUMENTATION I

REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT CHANNELS CHANNELS ACTION I. Reactor Coolant Outlet Temperature - 2 I I, 2 T HOT (Wide Range)

2. Reactor Coolant Inlet Temperature - 2 I I, 2 T COLD (Wide Range)

3. Reactor Coolant Pressure (Wide Range) 2 I l, 2 I 4. Pressurizer Water Level 2 1 1, 2 1-li

=J 5. Steam Line Pressure 2/Steam Generator 1/Steam Generator 1, 2 i

ll

.po w

I V1

~

6.

1.

Steam Generator Water Level (Narrow Range)

Steam Generator Water Level (Wide 2/Steam Generator 4/(1/Steam Generator) 1/Steam Generator 3 (I/St~am Generator) l, 2 l, 2

~

N Range)

8. Refueling Water Storage Tank Water 2 I Level

9. Boric Acid Tank Solution Level 2 (I/tank) I (l/tank) 3

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

11. Reactor Coolant System Subcooling 2 I 1, 2 Margin Monitor z 12. PORV Position Indicator 2/valve** I 1, 2 0

TABLE 3.3-11 (contipµel TABLE NOTATION ACTION 1 With the number of OPERA.8LE accident monitoring channels less tha:i the Requir"'d Number of Ch~mnels shovm in Table 3. 3-11, -.:cs tore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN 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 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be/')

in HOT SHUTDOWN 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 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, 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 OPERABLE Auxiliary Feedwater Flow Rate Channel.

ACTION 5 With the number of OPERABLE channels less than the Required Number of Channels show in Table 3.3-11, 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 - THOT (Wide Range)

b. Reactor Coolant Pressure (Wide Range)

SALEM - UNIT 2 3/4 3-Slb Amendment No. 95

°TABLE J. 3-ll ACCIDENT MONITORING INSTRUMENTATION

.I REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT CHANNELS CHANNELS ACTION

1. Reactor Coolant Outlet Temperature - 2 1 1, 2 THOT (Wide Range)

2. Reactor Coolant Inlet Temperature - 2 I I, 2 TCOLD (Wide Range)

J. Reactor Coolant Pressure (Wide Range) 2 I 1, 2

4. Pressurizer Water Level 2 I 1, 2

5. Steam Line Pressure 2/Steam Generator I/Steam Generator 1, 2 w

po w

I V1 po 6.

7.

Steam Generator Water Level (Narrow Range)

Steam Generator Water Level (Wide 2/Steam Generator 4 (I/Steam Generator)

I/Steam Generator J (l/Steam Generator) 1, 2 I, 2 Range)

8. Refueling Water Storage Tank Water 2 1 Level

9. Boric Acid Tank Solution Level 2 (I/tank) 1 (l/Tank) J

10. Auxiliary Feedwater Flow Rate 4 (l/Steam Generator) J (1/Steam Generator) 4, 6

11. Reactor Coolant System Subcooling 2 I 1, 2 Margin Monitor

12. PORV Position Indicator 2/valve** I I, 2

TABLE 3,3-11 (continue~

TABLE NOWION 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 SHUTDOWN 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 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT SHUTDOWN 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 shown in Table 3.3-11, operation may proceed provided that the Boric Acid Tanlc 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 l 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 3.3-11, 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 - THOT (Wide Range)

b. Reactor Coolant Pressure (Wide Range)

SALEM - UNIT 1 3/4 3-56 Amendment No. 117

TAAl.E 4.l-11 SURVEILLANCE REQUIRCHCNTS FOR ACCIDENT MONITORING INSTRUMENTATION CttANtlH CHANNEL CHAN NH FllNCT IONA INSTRUMENT CHECKS CALIBRATION YEST

1. Reactor Coolant Outlet Temperature -

T HOT (Wtde Range) " R NA

2. Reactor Coolant Inlet Temperature - M R T COLO (Wide Range)

J. Reactor Coolant Pressure (Wide Range) M R

4. Pressurizer Water level M R NA

5. Steam line Pressure H R NA 6~ Steam Generator Water level (Narrow R NA w

'- Range)

A w 1. Steam Generator Water level (Wide I

UI M R NA

..... Range)

8. Refuel Ing Water Stora~ T_ar* Water M R level

. 9. Bortc Actd Tank Solution level H R

10. Auxtltary Feedwater Flow Rate SUI R NA

11. Reactor Coolant System Subcoollng Hargtn Monttor " N/A*

IAuxtltary Feedwater System Is used on each startup and flow rate indication is vertfied at that time.

z 0

• The instruments used to develop RCS suhcooling mcirgin are calibrated on an 18 month cycl1~; llw monttor wi 11 be compared c:iuarterly with calculated suhcooH ng margin fur known input va I 111*~.

TABU 4. 3-11 SURVEILLANCE REQUIREMENTS FOR ACCIOENT MONITORING INSTRllMENTATilON r ,

CHANNl CHANNEL CHANNEL FUNCTli INSTRUMENT - CHECKS CALIBRATION HST

1. Reactor Coolant Outlet Temperature - M R NA Y HOT (Wtde Range)

2. Reactor Coolant Inlet Temperature - H R T COLD (Wide Range)

3. Reactor Coolant Pressure (Wtde Range) H R NA 4o Pressurizer Water level H R NA

5. Steam Ltne Pressure H R NA

6. Steam Generator Water Level (Narrow M R NJ\

w

......__ Range)

""w 1. Steam Generator Water level (Wide H R NA I

U1 tJ Range)

8. Refueling Water Storage Tank Water H R Level

9. Boric Acid Tank Solution level H R NA

10. Auxiliary Feedwater Flow Rate SUI R NA

11. Reactor Coolant System Subcooling M NA

§" Margin Monitor CD

I a.

3 CD

I

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

0 Ul *The instruments used to develop RCS suhcooling margin are calibrated on an lB month cyclP.; the w monHor will be compared quarterly with ca1rn1ated subcooling margin for known input values.