ML20101T570

Proposed Tech Spec Tables 3.1.1 & 3.2.A Re Main Steam Line High Radiation Instrument Setpoint to Address Expected Increase in Radiation from Injecting Hydrogen as Mitigator of IGSCC

ML20101T570
Person / Time
Site:	Pilgrim
Issue date:	02/01/1985
From:	BOSTON EDISON CO.
To:
Shared Package
ML20101T562	List: ML20101T560 ML20101T570
References
NUDOCS 8502060233
Download: ML20101T570 (4)

Text

n n.y -

u.

o3=- +

x

~ .

TABLE.3.1.1- k. -

~ REACTOR' PROTECTION SYSTEM (SCRAM) INSTRUMENTATI0li REQUIREMENT-f Minimum Number- Modes in Which function .

Operablef Inst. Trip Function Trip Level Setting ~ Must Be Operable Action

Channels.per Trip Refuel (7) Startup/Hott Run (1) System Standby 'e '

1 Mode Switch in Shutdown X X X A

<1 Manual Scram X- X X -

A IRM 3 High Flux 1120/125 of full scale X X (5) A 3 Inoperative X X (5) A APRM.

2 High Flux *

(14) (15) (17) (17) X A or B 2' Inoperative- X X(9) X A or B -

l 2 Downscale 12.5 Indicated on Scale (11) (11) X(12) A or 8 2 'High Flux (15%) 115% of Design Power X X (16) A or 8 2 High Reactor Pressure 11085 psig X(10) X X A 2 High Drywell Pressure 12.5 psig X(8) X(8) X A 2 Reactor Low Hater Level 19 In. Indicated Level X X X A 2 High Water Level in Scram Discharge Tank 139 Gallons X(2) X X A 2 Turbine Condenser Low Vacuum 223 In. Hg Vacuum X(3) X(3) X A or C 2 Main'-Steam Line High 17X Normal Full Power Radiation Background (18) X X X(18) A or C l 4 Main Steam Line Isolation Valve Closure 110% Valve Closure X(3)(6) X(3)(6) X(6) A or C 2 Turb. Cont. Valve Fast 1150 psig Control Oil Closure Pressure at Acceleration Relay X(4) X(4) X(4) A or D 4 Turbine Stop Valve Closure 1 101 Valve Closure X(4) X(4) X(4) A or D

• APRM high flux scram setpoint 1(.65H + 55) FRP Two recirc. pump operattor.

Amendment No. ,. MFLPD 27

! h p

O PM

NOTES FOR TABLE 3.1.1 (CONT'D)

10. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.

11. The APRM downscale trip function is only active when the reactor mode switch is in run.

12. The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not high.

13. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 50% of the normal complement of LPRM's to an APRM.

14. W is percent of drive flow required to produce a rated core flow of 69 M1b/hr. Trip level setting in percent of design power (1998 MWt).

15. See Section 2.1.A.I.

16. The APRM (15%) high flux scram is bypassed when in the run mode.

17.' The APRM flow biased high flux scram is bypassed when in the refuel or startup/ hot standby modes.

18. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of hydrogen injection with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the injection

.of hydrogen. The background radiation level and associated trip setpoints may be adjusted based on etther calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of hydrogen injection or prior to withdrawing control rods at reactor power levels below 20% rated power.

~

Amendment No. 29 h ..

gp  :+-~ -

7

, , , q 1 PNPS' TABLE 3.2.A: .

INSTRUMENTATION THAT~ INITIATES PRIMARY CONTAINMENT ISOLATION .

~ Minimum'# ofL Operable Instrument Channels Per Trip System-(l) Instrument ~ Trip Level Settina Act) o (21_

2(7) ' Reactor Low Water Level 19" indicated level (3) A and 0 1 Reactor High Pressure- 1110 psig . D

2= Reactor Low-Low Water Level at or above -49 in. A indicated level (4) 2- Reactor-High Water Level 148" indicated level (5) B 2(7). High Drywell Pressure 12.5 psig A

.2 High' Radiation Main Steam 57 times normal rated B Line Tunnel (9) full power background 2 Low Pressure Main Steam Line 1880 psig (8) B 2(6): High. Flow Main Steam Line 1140% of rated steam flow B 2 Main Steam Line Tunnel Exhaust Duct High Temperature 1170*F B 2 Turbine. Basement Exhaust Duct.High Temperature 1150*F B

1. Reactor Cleanup System High Flow 13001 of rated flow C

.2 Reactor Cleanup System High Temperature $150*F C

! ' Amendment No. 45

FT

, NOTESE/OR TABLEE3.2.A

1. Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.

2 ' Action If the first coldmn cannot be met for one of the trip systems, that trip system shall be tripped. If the first column cannot be met for both trip systems, the appropriate action listed below chall be taken.

A. Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. >

B. Initiate'an orderly load reduction and have Ma'sn Steam Lines isolated within eight hours.

C. Isolate Reactor Water Cleanup System.

D. Isolate Shutdown Cooling.

3. Instrument set point corresponds to 129.5" above top of active fuel.

4. Instrument set point corresponds to 78.5" above top of active fuel.

' 5. Not required in Run Mode (bypassed by Mode Switch).

6. -Two required for each steam line.

7. These signals also start SBGTS and initiate secondary containment isolation.

8. Only required in Run Mode (interlocked with Mode Switch).

9. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of hydrogen injection with the_ reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the. injection of hydrogen. The background radiation level and associated trip setpoints

-may be adjusted based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation

' level-shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of hydrogen-injection or prior _to withdrawing control rods at reactor power levels below 20%' rated power.

/

q

)

U Amendment No. 46

!