ML20098E908

Proposed Tech Specs,Permitting Changes in Settings of Certain Main Steam Line Instrumentation to Allow Testing of Hydrogen Injection as Means of Mitigating IGSCC

ML20098E908
Person / Time
Site:	Peach Bottom
Issue date:	09/28/1984
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20098E899	List: ML20098E898 ML20098E903 ML20098E908
References
NUDOCS 8410020107
Download: ML20098E908 (4)

Text

. - -.

.- ~.. -..

1 I

- Tchlo 3.1.1 (Cont'd)

REACTOR PROFECTION SYSTEM (SCRAM) INIiTRUMENTATION REQUIREMENT

/

Minimus No.

Modes in which Number of

-r of Operable Function Must be Instrument Instrument Trip Level Operable Channels Action Channels Trip Function Setting-Provided (1)

._per Trip Refuel Startup Run by Desgin.

- System (1)

(7) 2 High Water Level

<50 Gallons X (2)

X X

4 Instrument A

l in Scram Discharge Channels I

Volume 2

Turbine Condenser

>23 in. Hg.

X(3)

X(3)

X 4 Instrument A or C i

Low Vacuum Vacuum Channels O

2 Main Steam Line

<3 X Normal Full X

X X(14]

4 Instrument A

y High Radiation Fower sackground Channels 4

Main Steam Line

<10% Valve X (3) (6)

X (3) (6)

X (6) 8 Instrument A

Isolation Valve Elosure Channels Closure 2

Turbine Control 500<P<850 psig X(4) 4 Instrument A or D L

Valve Fast Closure Control Oil Pres-Channels sure Between Fast Closure Solenoid and Disc Dump Valve l

i 4

Turbine Stop

<10% Valve X(4) 8 Instrument A or D 1

Valve Closure Elosure Channels 8410020107 840929 PDR ADOCK 05000277 P

PDR

PBAPS

' NOTES FOR TABLE 3.1.1 (C:nt' d) 10.

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

11.

An APRM will be considered operable if there are at least 2 LP".M inputs per level and at least 14 LPRM inputs of the normal complement.

12.

This equation will be used in the event of operation with a maximum fraction of limiting power density (MFLPD) greater than the fraction of rated power (FRP), where FRP = fraction of rated thermal power (3293 MWt).

MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KW/ft for all 8 x 8 fuel.

The ratio of FRP to MPLPD shall be set equal to 1.0 unless the actual operating va..ue is less than the design value of 1.0, in 1

which case the actual operating value will be used.

W=

Loop Recirculation flow in percent of design.

W is 100 for core flow of 102.5 million Ib/hr or greater.

Delta W =

the difference between two loop and single loop effective recirculation drive flow rate at the same core flow.

During single loop operation, the reduction in trip setting (-0.66 delta W) is accomplished by correcting the flow input of the flow biased High Flux trip setting to preserve the original (two loop) relationship between APRM High Flux setpoint and recirculation drive flow or by adjusting the APRM Flux trip setting.

Delta W equals zero for two loop operation.

Trip level setting is in percent of rated power (3293 MWt).

13.

See Section 2.1.A.1.

14.

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 the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power background radiation level and associated trip setpints may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip setpoints may be adjusted during the test program 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 the test program, and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power. __

TABLE 3.2.A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimus No.

of Operable Number of Instrument

-Instrument Instrument Trip Level Setting Channels Provided Action Channels per By Design (2)

Trip System (1) 2 (6)

Reactor Low Water

> 0" Indicated

- 4 Inst. Channels A

Level Eevel (3) 1 Reactor High Pressure

< 75 psig 2 Inst. Channels D

(Shutdown Cooling Isolation)

E 2

Reactor Low-Low at or above -49" 4 Inst. Channels A

T' Water Level indicated level (4) 2 (6)

High Drywell Pressure

< 2 psig 4 Inst. Channels A

I2 High Radiation Main

< 3 X Normal Rated Full 4 Inst. Channels B

~

Steam Line Tunnel Power Background (8) (10) 2 Low Pressure Main

> 850 psig (7) 4 Inst. Channels B

Steam Line 2 (5)

High Flow Main

< 140% of Rated 4 Inst. Channels B

Steam Line 5 team Flow 2

Main Steam Line

< 200 deg. F (9) 4 Inst. Channels B

Tunnel Exhaust

-Duct High Temperature

. _ _ __.__.. = _ _. _

PBAPS

A *

• f' NOTES FOR TABLE 3.2.A

- 1.. Whenever Primary Containment integrity is required by Section 3.7, i

there shall be two operable or tripped trip systems for each

. function.

2.

If the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken:

A.'

Initiate an orderly shutdown and have the reactor in Cold l

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 Main Steam Lines

]

isolated within eight hours.

C.

Isolate Reactor Water Cleanup System.

j D.

Isolate Shutdown Cooling.

3.

Instrument setpoint corresponds to 177.7" above top of active fuel.

4.

Instrument setpoint corresponds to 129.7" above top of active fuel.

1 l

S.

Two required for each steam line.

6.

These signals also start SBGTS and initiate secondary containment isolation.

7.

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

8.

At a radiation level of 1.5 times the normal rated power background, an alarm will be tripped in the control room to alert the control i

room operators to an increase in the main steam line tunnel radiation level.

9.

In the event of a loss of ventilation in the main steam line tunnel area, the main steam line tunnel exhaust duct high temperature setpoint may be raised up to 250 degrees F for a period not to i

exceed 30 minutes to permit restoration of the ventilation flow.

During the 30 minute period, an operator chall observe control room indications of the duct temperature so in the event of rapid I

increases (indicative of a steam line break) the operator shall promptly close the main steam line isolation valves.

10. 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 the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip j

i setpoints may be changed based on a calculated value of the i

radiation level expected during the test.

The background radiation l

level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual 1

j radiation levels resulting from hydrogen injection.

The background i

radiation level shall be determined and' associated trip setpoints j

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 the test program, and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of i

establishing reactor power levels below 20% rated power.

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