ML20107F972

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Proposed Tech Specs,Revising Minimum Required Number of Operable Rv Water Level Trip Sys During Period That RCS Instrument Line Excess Flow Check Valve Surveillance Tests Being Performed
ML20107F972
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/14/1996
From:
TENNESSEE VALLEY AUTHORITY
To:
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ML20107F961 List:
References
NUDOCS 9604230057
Download: ML20107F972 (23)
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Text

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d ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY

BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE T8-375 MARKED PAGES

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. I. AFFECTED PAGE LIST l Unit 1 Unit 2 Unit 3 3.2/4.2-14 3.2/4.2-14 3.2/4.2-14 3.2/4.2-24 3.2/4.2-24 3.2/4.2-23 II. MARKED PAGES 1

See attached.

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9604230057 960414 PDR P ADOCK 05000259
PDR

TABLE 3.2.8 INSTRtpENTATION THAT INITATES OR CONTROLS THE CORE Afe CONTAlleENT COOLING SYSTEMS E ** ninimus No.

5 Operable Per Trio Sva(1)

Function . Tris Level Settine Action Remarks 2 Instrument Channel - 1 470" above vessel aero A 1 Below trip setting initiates Reacter Low Water Level HPCI.

2 Instrument Channel - 1 470" above vessel aero. A 1. Multiplier relays initiate Reacter Low Water Level RCIC.

' 2 (/q Instrument Channel - 1 398" above vessel aero. A 1. Selow trip setting initiates Reacter Low Water Level CSS. l (LIS-3-584-0, W #1) '

Multiplier relays initiate LPCI.

2. Multiplier relay from CSS initiates accident signal (15).

2(16) Instrument Channel - 1 398" above vessel aero. A 1. Below trip settings, in Reactor Low Water Level l (LIS-3-584-0, W #2) conjunction with drywell 3 ta high pressure, low water i

  • level permissive, ADS timer

" timed out and CSS or RHR pump running, initiates ADS.

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2. Below trip settings, in L

d conjunction with low reactor -

water level permissive ADS timer timed out ADS high drywell pressure bypass timer timed out CSS or RHR pump 4 running, initiates A05.

1(16) Instrument Channel - 1 544" above vessel aero. A 1. Below trip setting permissive Reacter Low Water Level for initiating signals on ADS.

Permissive (LIS-3-184 &

185. W #1) i

~. 1 Instrument Channel - 1 312 5/16" above vessel aero. A l'. Below trip setting prevents

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+ -4 Reacter Low Water Level (2/3 core height) Inadvertent operation of (LITS-3-52 and 62. W #1) containment spray during accident condition. M t

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l NOTES FOR TAaf.R 3.2.B (Cont'd) FEB 0 71991

10. Only one trip system for each cooler fan.
11. In only two of the four 4160-V~ shutdown boards. See note 13. l
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J In only one of the four 4160-V shutdown boards. See note 13.

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' 13. An emergency 4160-V shutdown board is considered a trip system.

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14. RERSW pump would be inoperable. Refer to Section 4.5.C for the

! requirements of a RERSW pump being inoperable.

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15. The accident signal is the satisfactory completion of a one-out-of-two .

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or the vessel low water level (1 378" above vessel zero) originating in J

- the core spray system trip system. l l I

16. The ADS circuitry is capable of accomplishing its protective action with l one OPERABLE trip system. Therefore, one trip system may be taken out of J

service for functional testing and calibration for a period not to exceed i eight hours.

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i 17. Two RPT systems exist, either of which will trip both recirculation If pumps. The systems will be individually functionally tested monthly.

l the test period for one RPT system exceeds two consecutive hours, the f

system will be declared inoperable. If both RPT systems are inoperable i

or if one RPT system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly l

i power reduction shall be initiated and reactor power shall be less than 30 percent within four hours.

! 18. Not required to be OPERABLE in the COLD SHUTDOWN CONDITION.

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t 3.2/4.2-24 AMENDMENT N0.18 0 BPR

{ Unit 1

Note 19 (Insert A)

Only one trip system will be required to be OPERABLE during testing of the reactor coolant system instrument line flow -check valves in accordance with TS section 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN.

Manual and automatic initiating capability of CSS and LPCI will be available but with a reduced number of instrument channels.

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TABLE 3.2.B INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS g g, Minimum No, m gg Operable Per

7 Trip Sys(l) Function Trio Level Settino Action Remarks

'" 2 Instrument Channel - 1 470" above vessel zero. A 1. Below trip setting initiates

  • Reactor Low Water icvet HPCI.

(LIS-3-5BA-D)

  • 2 Instrument Channel - 1 470" above vessel zero. A 1. Multiplier relays initiate keactor Low Water Level RCIC.

(LIS-3-58A-D)

  • 2 ([lj Instrument Channel - 1 398" above vessel zero. A 1. Below trip setting initiates l Reactor Low Water Level CSS.

(LS-3-5BA-D)

Multiplier relays initiate ,

LPCI.

2. Multiplier relay from CSS

, initiates accident signal (15).

o 2(16) Instrument Channel - 1 398* above vessel zero. A 1. Below trip settings, in

] Reactor Low Water Level conjunction with drywell (LS-3-58A-D) high pressure, low water if level permissive. ADS timer 8' timed out and CSS or RH2 pump running, initiates ADS.

2. Below trip settings, in conjunction with low reactor water level permissive, ADS timer timed out, i ADS high drywell pressure bypass timer timed out, CSS or RHR pump running. -

initiates ADS. <

e.

i T: 1(16) Instrument Channel - 1 544" above vessel zero. A 1. Below trip setting permissive L

[2 Reactor Low Water Level for initiating signals on ADS.  !

C3 Permissive (LIS-3-184

@g ma 185)

-=-

_, 1 Instrument Channel - 1 312 5/16" above vessel zero. A 1. Below trip setting prevents 23 Reactor Low Water Level (2/3 core height) inadvertent operation of >""

(LIS-3-52 and LIS-3-62A) containment spray during t<3 (J accident condition. __.

H4 43

Manual and automatic initiating capability of CSS and LPCI will be available, but with a reduced number of instrument channels.

NOTES FOR TABLE 3.2.B (Cont'd)

10. Only one trip system for each cooler fan. FEB 0 71991 i

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11. In only two of the four 4160-V shutdown boards. See note 13.
12. In only one of the four 4160-V shutdown boards. See note 13.
13. An emergency 4160-V shutdown board is considered a trip system.
14. RHRSW pump would be inoperable. Refer to Section 4.5.C for the requirements of a RHRSW pump being inoperable.
15. The accident signal is the satisfactory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pressure or the vessel low water level (1 398" above vessel zero) originating in the core spray system trip system.
16. The ADS circuitry is capable of accomplishing its protective action with one OPERABLE trip system. Therefore, one trip system may be taken out of service for functional testing and calibration for a period not to exceed l eight hours.
17. Two RPT systems exist, either of which will trip both recirculation pumps. The systems will be individually functionally tested monthly. If the test period for one RPT system exceeds two consecutive hours, the

[

system will be declared inoperable. If both RPT systems are inoperable I or if one RPT system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly l power reduction shall be initiated and reactor power shall be less than j 30 percent within four hours. i l

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18. Not required to be OPERABLE in the COLD SHUTDOWN CONDITION.

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19. See TA%f A i

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AMENDMENT NO.19 0

B h.... 3.2/4.2-24 j Unit 2 I

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(Insert A) i

~ Note 19 l Only one trip system will be required to be OPERABLE during testing of the reactor coolant system instrument line flow check valves in accordance with TS section 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN.

i Manual and automatic initiating capability of CSS and LPCI will be c.vailable but with a reduced number of instrument channels.

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TABLE 3.2.8 INSTRipENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAlleeff COOLING SYSTEMS c2 to Minlanan No.

n Operable Per Trie Svs(11 Function Trle Level Settine Action Remarks 2 Instrument Channel - 1 470" above vessel aero. A 1. Below trip setting initiates Reactor Low Water Level HPCI.

(LIS-3-58A-0) l 2 Instrument Channel - 1 470" above vessel aero. A 1. Multiplier relays initiate Reactor Low Water Level RCIC. l (LIS-3-58A-0) I Instrument Channel - 1.

2 (l%/ Reactor Low Water Level 13M" above vessel aero. A Below trip setting initiates CSS.

l (LS-3-58A-D) l Multiplier relays initiate LPCI.

2. Multiplier relay from CSS initiates accident signal (15).

2(16) Instrument Channel - 1 398" above vessel aero. A 1. Below trip settings, in l

F Reactor Low Water Level conjunction with drywell N (LS-3-58A-D) high pressure, low water l

2 level permissive. ADS timer timed out and CSS or RHR Y

pump running, initiates ADS.

2. Below trip settings, in conjunction with low reactor water level permissive, ADS timer timed out. ADS high drywell pressure bypass timer timed out. CSS or RHR pump running. **ltiates ADS.
  • 1(16) Instrummt Channel - 1 544" above vessel aero. A 1, 8elow trip setting permissive E Reactor Low Water Level for initiating signals on ADS.

3 C

Permissive (LIS-3-184, 185) l Instrument Channel -

1 Reactor Low Water Level 1 312 5/16' above vessel aero. A (2/3 core height)

1. Below trip setting prevents Inadvertent operation of h 5

-4 to R

NOTES FOR TABLE 3.L]l (Ccntinusd) JUL 171995

10. Only one trip system for each cooler fan.

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11. In only two of the four 4160-V shutdown boards. See note 13.
12. In only one of the four 4160-V shutdown boards. See note 13,
13. An emergency 4160-V shutdown board is considered a trip system.
14. RHRSW pump would be inoperable. Refer to Section 4.5.C for the requirements of a RHRSW pump being inoperable.
15. The accident signal is the satisfactory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pressure or the vessel low water level (1 398" above vessel zero) originating in l the core spray system trip system.
16. The ADS circuitry is capable of accomplishing its protective action with one OPERARf2 trip system. Tharefore, one trip system may be taken out of service for functional testing and calibration for a period not to exceed eight hours.
17. Two RPT systems exist, either of which will trip both recirculation pumps. The systems will be individually functionally tested monthly. If the test period for one RPT system exceeds two consecutive hours, the system will be declared incperable. If both RPT systems are inoperable or if one RPT system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly power reduction shall be initiated and reactor power shall be less than 30 percent within four hours. '
18. Not required to be OPERARIR in the COLD SHUTDOWN CONDITION.

19, See TMot/l BPN 3.2/4.2-23 EE E'1 N "

Unit

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Note 19 (Insert A)

Only one trip system will be required to be OPERABLE j during testing of the reactor coolant system instrument line flow check valves in accordance with TS section 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN.

Manual and automatic initiating capability of CSS and 1 LPCI will be available but with a reduced number of l instrument channels.

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1 ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (DFN) l UNITS 1, 2, AND 3 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-375 REVISED PAGES l

I. &ZEECTED PAGE LIST Unit 1 Unit 2 Unit 3 3.2/4.2-14 3.2/4.2-14 3.2/4.2-14 3.2/4.2-15* 3.2/4.2-15* 3.2/4.2-15*

3.2/4.2-24 3.2/4.2-24 3.2/4.2-23 II. REVISED PAGES See attached.

  • - Denotes spillover page i

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i dW TABLE 3.2.B et h INSTRUMENTATION THAT INITATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS

" Minimum No.

Operable Fuc Trin Sys(1) Function Trin Level Settincr Action Remarks 2 Instrument Channel - 2 470" above vessel zero A 1. Below trip setting initiates Reactor Low Water Level HPCI.

1 2 Instrument Channel - 2 470" above vessel zero. A 1. Multiplier relays initiate Reactor Low Water Level RCIC.

F 2(19) Instrument Channel - 2 398" above vessel zero. A 1. Below trip setting initiates l [

Reactor Low Water Level CSS.

(LIS-3-58A-D, SW #1)

Multiplier relays initiate ,

LPCI.

I w 2. Multiplier relay from CSS .

L initiates accident signal (15). [

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b b 2(16) Instrument Channel - 2 398" above vessel zero. A 1. Below trip settings, in

  • Reactor Low Water Level conjunction with drywell 4

A (LIS-3-58A-D, SW #2) high pressure, low water i level permissive, ADS timer 5 timed out and CSS or RHR pump running, initiates ADS.

1

2. Below trip settings, in conjunction with low reactor water level permissive, ADS timer timed out,-ADS high drywell pressure bypass timer timed out, CSS or RHR pump running, initiates ADS.

i 1(16) Instrument Channel - 1 544" above vessel zero. A 1. Below trip setting permissive Reactor Low Water Level for initiating signals on ADS.

Permissive (LIS-3-184 &

185, SW #1) i

_ . . -__ .____.m. _ . _ - - _ - - _ - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - ---- - - - - - - - - - - -

g tD TABLE 3.2.B (Continued) 7k Minimum No. .

" Operable Per Trio Sys (1) Function Trio Level Settina Action Remarks 1

1 Instrument Channel - 2 312 S/16* above vessel A 1. Below trip setting prevents Reactor Low Water Level zero. (2/3 core height) inadvertent operation of (LITS-3-52 and 62, SW #1) containment spray during accident condition.

2(1R) Instrument Channel - is ps2.5 psig A 1. Below trip setting prevents Drywell High Pressure inadvertent operation of (PS-64-58 E-H) containment spray during accident conditions.

2(18) Instrument Channel - s 2.5 psig A 1. Above trip setting in con-Drywell High, Pressure junction with low reactor (PS-64-58 A-D, SW #2) pressure initiates CSS.

w Multiplier relays initiate

'u HPCI.

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2. Multiplier relay from CSS

'u initiates accident signal. (15) 4 un 2(18) Instrument Channel - s 2.5 psig A 1. Above trip setting in Drywell High Pressure conjunction with low (PS-64-58A-D, SW #1) reactor pressure initiates LPCI.

2(16)(18) Instrument Channel - s 2.5 psig A 1. Above trip setting, in Drywell High Pressure conjunction with low reactor (PS-64-57A-D) water level, low reactor water level pemissive, ADS timer timed out, and CSS or RHR pump running, initiates ADS.

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NOTES FOR TABLF 3.2.B I

1. Whenever any CSCS System is required by Section 3.5 to be OPERABLE, there shall be two OPERABLE trip systems except as noted. If a requirement of the first column is reduced by one, the indicated action shall be taken.

If the same function is inoperable in more than one trip system or the first column reduced by more than one, action B shall be taken.

Action:

A. Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the function is not OPERABLE in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.

B. Dsclare the system or component inoperable.

C. Immediately take action B until power is verified on the trip system. I D. No action required; indicators are considered redundant.

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E. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel (s) to OPERABLE status or place the inoperable channel (s) in the tripped condition.

2. In only one trip system.
3. Not considered in a trip system.
4. Deleted
5. With diesel power, each RERS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 sec. later.
6. With normal power, one CSS and one RHRS pump is scheduled to start instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 sec. with similar pumps starting after about 14 sec. and 21 sec.,

at which time the full complement of CSS and RHRS pumps would be operating.

7. The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percent above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isclation following a postulated steam line break.

Similarly, the HPCIS setting of 90 psi corresponds to at least 150 percent above maximum steady state flow while also ensuring the initiation of isolation following a postulated break.

8. -Note 1 does not apply to this item.
9. The head tank is designed to assure that the discharge piping from the CS and RHR pumps are full. The pressure shall be maintained at or above the l values listed in 3 5.H, which ensures water in the discharge piping and up to the head tank.

BFN 3.2/4.2-23 MDMENT NO. 2 2 0 Unit 1

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NOTES FOR TABLE 3.2.B (Cont'd)

10. Only one trip system for each cooler fan.
11. In only two of the four 4160-V shutdown boards. See note 13.
12. In only one of the four 4160-V shutdown boards. See note 13.
13. An emergency 4160-V shutdown board is. considered a trip system.
14. RHRSW pump would be inoperable. Refer to Section 4.5.C for the requirements of a RHRSW pump being inoperable.
15. The accident signal is the satisfactory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pressure or the vessel low water level (2 398" above vessel zero) originating in the core spray system trip system.
16. The ADS circuitry is capable of accomplishing its protective action with one OPERABLE trip system. Therefore, one trip system may be taken out of service for functional testing and calibration for a period not to exceed eight hours.
17. Two RPT systems exist, either of which will trip both recirculation pumps. ,

The systems will be individually functionally tested monthly. If the test period for one RPT system exceeds two consecutive hours, the system will be declared inoperable. If both RPT systems are inoperable or if one RPT system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly power reduction shall be initiated and reactor power shall be less than 30 percent within febr hours.

18. Not required to be OPERABLE in the COLD SHUTDOWN CONDITION.
19. Only one trip system will be required to be OPERABLE during testing of the reactor coolant system instrument line flow check valves in accordance with TS Section 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN. Manual and automatic initiating capability of CSS and LPCI will be available but with a reduced number of instrument channels.

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BFN 3.2/4.2-24 Unit 1 l . - _. .. - _. - . .- . --

c tD TABLE 3.2.B h$

tv INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS

" Minimum No. '

Operable Per Trio Sys (1) Punction Trin Level Settina Action Ramarks 2 Instrument Channel - 2 470* above vessel zero. A 1. Below trip setting initiates Reactor Low Water Level HPCI.

(LIS-3-58A-D) 2 Instrument Channel - 2 470" above vessel zero. A 1. Multiplier relays initiate Reactor Low Water Level RCIC.

(LIS-3-58A-D)

  • 2 (19 ) Instrument Channel - 2 398* above vessel zero. A 1. Below trip setting initiates l Reactor Low Water Level CSS.

(LS-3-5BA-D)

Multiplier relays '..itiate g

LPCI.

2. Multiplier relay from CSS f initiates accident signal (15).

u 2(16) Instrument Channel - 2 398* above vessel zero. A 1. Below trip settings, in Reactor Low Water Level conjunction with drywell (LS-3-58A-D) high pressure, low water level permissive, ADS timer '

timed out and CSS or RHR pump running, initiates ADS.

2. Below trip settings, in conjunction with low reactor water level permissive, ADS timer timed out, ADS high drywell pressure bypass timer timed out, CSS or RHR pump running, initiates ADS.
  • Only one trip system will be required to be OPERABLE during the period that the Reactor Vessel water level instrumentation modification requested by NRC Bulletin 93-03 is being performed, provided that the reactor is in the COLD SHUTDOWN CONDITION. Manual and automatic initiating capability of CSS and LPCI will be available, but with a reduced number of instrument channels.

. _ . . ~ . . - - , - . _ . _ - . - - - - - --- . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

4 CW TABLE 3.2.B (Continued) 55 a

Minimum No. -

" Operable Per Trin Svs (1) - Function Trin Level Settina Action Remarks 1(16) Instrument Channel - 2 544" above vessel zero. A 1. Below trip settir.g permissive Reactor Low Water Level -for initiating signale on ADS.

Permissive (LIS-3-184, 185) 1 Instru.mnt Channel - 2 312 5/16" above vessel A 1. Below trip setting prevents Reactor Low Water Level zero. .(2/3 core height) inadvertent operation of (LIS-3-52 and LIS-3-62A) containment spray during accident condition.

II 2(18) Instrument Channel - 1s ps2.5 psig A 1. Below trip setting prevents Drywell High Pressure inadvertent operation of 4.3 (PIS-64-58 E-H) containment spray during

.i h accident conditions.

A 2(18) Instrument Channel - s 2.5 psig A 1. Above trip setting in con-L junction with low reactor Drywell High Pressure 4 '

pressure initiates CSS.

l Ln (PIS-64-58 A-D)

- Multiplier relays initiate HPCI.

2. Multiplier relay from CSS initiates accident signal. (15)

! 2(18) Instrument Channel - s 2.5 psig A 1. Above trip setting in I Drywell High Pressure conjunction with low (PIS-64-58A-D) reactor pressure initiates

' LPCI.

2(16) (18) Instrument Channel - s 2.5 psig A 1. Above trip setting, in j Drywell High Pressure conjunction with' low reactor  !

(PIS-64-57A-D) water level, low reactor  !

water level permissive, ADS I timer timed out, and CSS or j RHR pump running, initiates j ADS. {

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NOTES FOR TABLE 3.2.B

1. Whenever any CSCS System is required by Section 3.5 to be OPERABLE, there shall be two OPERABLE trip systems except as noted. If a requirement of the first column is reduced by one, the indicated action shall be taken.

If th3 same function is inoperable in more than one trip system or the first column reduced by more than one, action B shall be taken.

Action:

A. Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the function is not OPERABLE in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.

B. Declare the system or component inoperable.

C. Immediately take action B until power is verified on the trip system.

D. No action required; indicators are considered redundant.

E. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel (s) to OPERABLE status or place the inoperable channel (s) in the tripped condition.

2. In only one trip system.
3. Not considered in a trip system.
4. Deleted. l
5. With diesel power, each RHRS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 seconds later, j
6. With normal power, one CSS and one RHRS pump is scheduled to start j instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 sec. with similar pumps starting after about 14 sec. and 21 sec.,

at which time the full complement of CSS and RHRS pumps would be operating.

7. The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percent above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break.

Similarly, the HPCIS setting of 90 psi corresponds to at least 150 percent above maximum steady state flow while also ensuring the initiation of isolation following a postulated break.

8. Note 1 does not apply to this item.
9. The head tank is designed to assure that the discharge piping from the CS and RER pumps are full. The pressure shall be maintained at or above the values listed in 3.5.H, which ensures water in the discharge piping and up l to the head tank.

BFN 3.2/4.2-23 AMENDMENT INL 18 7 Unit 2

NOTES FOR TABLE 3.2.B (Cont'd)

10. Only one trip system for each cooler fan.
11. In only two of the four 4160-V shutdown boards. See note 13.
12. In only one of the four 4160-V shutdown boards. See note 13.
13. An emergency 4160-V shutdown board is considered a trip system.
14. RHRSW pump would be inoperable. Refer to Section 4.5.C for the requirements of a RHRSW pump being inoperable.
15. The accident signal is the satisfactory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pressure or the vessel low water level (2 398" above vessel zero) originating in the core spray system trip system.
16. The ADS circuitry is capable of accomplishing its protective action with one OPERABLE trip system. Therefore, one trip system may be taken out of service for functional testing and calibration for a period not to exceed eight hours.
17. Two RPT systems exist, either of which will trip both recirculation pumps.

The systems will be individually functionally tested monthly. If the test period for one RPT system exceeds two consecutive hours, the system will be declared inoperable. If both RPT systems are inoperable or if one RPT system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly power reduction shall be initiated and reactor power shall be less than 30 percent within four hours.

18. Not required to be OPERABLE in the COLD SHUTDOWN CONDITION.
19. Only one trip system will be required to be OPERABLE during testing of the reactor coolant system instrument line flow check valves in accordance with TS Section 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN. Manual and l automatic initiating capability of CSS and LPCI will be available but with I a reduced number of instrument channels.

4 a

BFN 3.2/4.2-24 Unit 2 j

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I C tD TABLE 3.2.B dE rr INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND COffrAINMENT COOLING SYSTEMS Minimum No. '

Operable Per Trio Svs (1) Function Trin Level Settina Action Remarks

'2 Instrument Channel - 2 470" above vessel zero. A 1. Below trip setting initiates Reactor Low Water Level HPCI.

(LIS-3-58A-D) 2 Instrument Channel - 2 470" above vessel zero. A 1. Multiplier relays initiate Reactor Low Water Level RCIC.

(LIS-3-58A-D) 2(19) Instrument Channel - 2 398" above vessel zero. A 1. Below trip setting initiates l Reactor Low Water Level CSS.

(LS-3-58A-D)

Multiplier relays initiate w

u N

. 2. Multiplier relay from CSS Y initiates accident signal (15).

w b

2(16) Instrument Channel - 2 398" above vessel zero. A 1. Below trip settings, in Reactor Low Water Level conjunction with drywell  ;

(LS-3-58A-D) high pressure, low water level permissive, ADS timer timed out and CSS or RHR ,

pump running, initiates ADS.

2. Below trip settings, in  ;

conjunction with low reactor water level permissive, ADS ,

timer timed out, ADS high drywell pressure bypass i timer timed out, CSS or RHR pump running, initiates ADS.

1(16) Instrument Channel - 2 544" above vessel zero. A 1. Below trip setting permissive Reactor Low Water Level for initiating signals on ADS.

Permissive i (LIS-3-184, 185) s

C 12 TABLE 3.2.B (Continued)

Minimum No.

Operable Per Trin Sys(1) Function Trin Level Settina Action Remarks 1 Instrument Channel - 2 312 5/16" above vessel A 1. Below trip setting prevents Reactor Low Water Level zero. (2/3 core height) inadvertent operation of (LIS-3-52 and LIS-3-62A) containment spray during accident condition.

2(18) . Instrument Channel - is ps2.5 psig A 1. Below trip setting prevents Drywell High Pressure inadvertent operation of (PIS-64-58 E-H) containment spray during accident conditions.

2(18) Instrument Channel - s 2.5 psig A 1. Above trip setting in con-Drywell High Pressure junction with low reactor (PIS-64-58 A-D) pressure initiates CSS.

w

  • Multiplier relays initiate u HPCI.

N s

h 2. Multiplier relay from CSS initiates accident signal. (15) g 2(18) Instrument Channel - s 2.5 psig A 1. Above trip setting in Drywell High Pressure conjunction with low (PIS-64-58A-D) reactor pressur initiates LPCI. .

2(16)(18) Instrument Channel - s 2.5 psig A 1. Above trip setting, in Drywell High Pressure conjunction with low reactor (PIS-64-57A-D) water level, low reactor water level permissive, ADS timer timed out, and CSS or RHR pump running, initiates ADS.

l NOTES FOR TABLE 3.2.B

1. Whenever any CSCS System is required by Section 3.5 to be OPERABLE, there shall be two OPERABLE trip systems except as noted. If a requirement of the first column is reduced by one, the indicated action shall be taken.

If the same function is inoperable in more than one trip system or the i

first column reduced by more than one, action B shall be taker.,

l

! l Action: l A. Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the function is not OPERABLE in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take l l action B. I

! B. Declare the system or component inoperable.

j C. Immediately take action B until power is verified on the trip system.  !

I i

l D. No action required; indicators are considered redundant.

l E. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> restore the inoperable channel (s) to OPERABLE status or i I

l place the inoperable channel (s) in the tripped condition.

l 2. In only one trip system.

I I

3. Not considered in a trip system.
4. Deleted. ]
5. With diesel power, each RHRS pump is scheduled to start immediately and ea'ch CSS pump is sequenced to start about 7 seconds later. l l

l

6. With normal power, one CSS and one RHRS pump is scheduled to start j instantaneously, one CSS and one RHRS pump is sequenced to start after j about 7 seconds with similar pumps starting after about 14 seconds and  !

! 21 seconds, at which time the full complement of CSS and RHRS pumps would  !

be operating. i l

7. The RCIC and HPCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of water corresponds to at least 150 percent above maximum steady state steam flow to assure that spurious isolation does not occur while ensuring the initiation of isolation following a postulated steam line break.

Similarly, the HPCIS setting of 90 psi corresponds to at least 150 percent l l above maximum steady state flow while also ensuring the initiation of l isolation following a postulated break, i

8. Note 1 does not apply to this item.
9. The head tank is designed to assure that the discharge piping from the CS l and RER pumps are full. The pressure shall be maintained at or above the values listed in 3.5.H, which ensures water in the discharge piping and up to the head tank.

BFN 3.2/4.2-22 ANDfDMENT NO.19 4 Unit 3 4

i 5

NOTES FOR TABLE 3.2.B (Continued)

10. Only one trip system for each cooler fan.
11. In only two of the four 4160-V shutdown boards. See note 13.
12. In only one of the four 4160-7 shutdown boards. See note 13.

I

13. An emergency 4160-V shutdown board is considered a trip system. I
14. RHRSW pump would be inoperable. Refer to Section 4.5.C for the requirements of a RHRSW pump being inoperablo.
15. The accident signal is the satisfactory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pressure or the vessel low water level (2 398" above vessel zero) originating in the i core spray system trip system.

)

16. The ADS circuitry is capable of accomplishing its protective action with one OPERABLE trip system. Therefore, one trip system may be taken out of service for functional testing and calibration for a period not to exceed eight hours.
17. Two RPT systems exist, eitheu of which will trip both recirculation pumps.

The systems will be indis". dually functionally tested monthly. If the test period for one RPT sye.em exceeds two consecutive hours, the system will be l declared inoperable. If both RPT systems are inoperable or if one RPT l system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly power reduction shall be initiated and reactor power shall be less than 30 percent within I fo'ur hours. l

18. Not required to be OPERABLE in the COLD SHUTDOWN CONDITION,
19. Only one trip system will be required to be OPERABLE during testing of the reactor coolant system instrument line flow check valves in accordance with TS Section 4.7.D.1.d, provided the reactor is in COLD SHUTDOWN. Manual and automatic initiating capability of CSS and LPCI will be available but with a reduced number of instrument channels.

BFW 3.2/4.2-23 Unit 3

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