ML20203N209

Proposed Tech Specs,Consisting of Proposed Change 86-09, Making Permanent short-term Change Granted in Amend 86 Re Operation of Main Steam Line W/Hydrogen Injection Into Reactor Coolant

ML20203N209
Person / Time
Site:	Pilgrim
Issue date:	09/09/1986
From:	BOSTON EDISON CO.
To:
Shared Package
ML20203N202	List: BECO-86-136, Application for Amend to License DPR-35,consisting of Proposed Change 86-09,making Permanent short-term Change Noted in Amend 86 Re Operation of Main Steam Line W/Hydrogen Injection Into Reactor Coolant.Fee Paid ML20203N209
References
NUDOCS 8609230212
Download: ML20203N209 (4)

Text

. _ .

TABLE 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum Number Modes in Which function Op2rable Inst. Trip Function Trip Level Setting Must Be Operable Action

Channels per Refuel (7) Startup/ Hot Ren Trip (l) System Standbv 1 Mode Switch in Shutdown X X X A , . ,

( J 1 Hanual Scram -X eX Xe A j

, ~ ,. 't

? -

IRM 3 High Flux -<120/125 of full scale X X (5) A av '

~

3 Inoperative - -

X X (5) A . ,,,,

m '

m. ,..

APRM ,, , d ,

2 High Flux *

( 14) (17) (17) X_ i.Or_ B r' A or 8 Q

"" ~'t 1 2 Inoperative (13) . (15) L. X(9) X l 2 Downscale >2.5 Indicated on Scale C.11 ) (11) X(12) A or B  %^

2 High Flux (151) jl5%ofDesignPower X .X (16) A or L -

, # ~

n' ' .a ."

(,

2 High Reactor Pressure 11085 psig ,, X(10) X ,

Xs A s r

~

2 High Drywell Pressure $2.5 psig X(8) 7 88) ~X b~ A ^w V

_ 2 Peactor Low Water Level 19 In. Inaicated L2'Je) , X X

" 'X , l _ : .:A/

. . .-  :.  ; i . , ~ .

~

2 High Wate7 Level in Scram '<-

se es /

- A6 X, '

Discharge Tank 139 Gallons .X(2) 'X

.?  : ~. '

. 2* Turbine Condenser' Low ,

T_ y '

) Vacuum 123 -Inc Hg Vacuum, a X'3) X(3) ,. X A or C

~

.~ w. a " . ~

~

(. _2, Main Steam Line H1gh 17X Normal. Full Power  ;[^

• 3

-- - Radiation' 18ackground (18) X 's. X X(18) A or C -

f-

- , - 4 Main Steam Line Isolat19n ,

,- - / .

', Valve Closure " ~

-<10% Valve Glosure X(3)(6) X(3)(6) A or P

[XW*q  %;

2150 psig Control Oil .c e ' ' m -

i ~2 .f- ' lurb7 C9nt. Valve ~ Fast- ' '

'r

[* ~' J f L

e Closure' ~, Pressure it s '

- '* Kcceleration_ Relay X(4) X(4) iX(4) ..y A or D l

s v

4 T0rbine Stop Valve Closure 11CL Valve Clow r y X(4) 'U 4) lX(4) A or D

..v - .- ;

. '/~'

-*APRM high flux scram setpoint <(.6AW e 621)

~

FRP _ lInc,recirc. pur.%.0peration ' "

7

. . 5. 8609230212 860909 MFLPD y,/ '

y 2,1 ADOCK 05000293

' Amendment No. 92 PDR e'~ 1 f*'

p PDR - +

, ,-L ,

'4 .

Ib .i k ,

.}4

)

et .

NOTES FOR TABLE 3.1.1 (CONT'D)

O. ,

T4# 10. Not required to be operable when the reactor pressure vessel head is not l's bolted to the vessel.

5 11. The APRM downscale trip function is only active when the reactor mode d

switch is in run.

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

Y '

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.

O 14. H 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.

< y !.

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

N 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 4/ 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 g 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 and prior to withdrawing control rods at reactor power levels below 20% rated power.

I D6 I

L Amendment No. g 29

PNPS TABLE 3.2.A e' INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum # of ,

Operable Instrument Channels Per Trip System (1) Instrument Trip Level Setting Action (2) 2(7) Reactor Low Water Level 29" indicated level (3) A and D 1 Reactor High Pressure 1110 psig D 2 Reactor Lou-Low Water Level at or above -49 in. A indicated level (4) 2 Reactor High Hater Level 148" indicated level (5) B l

2(7) High Drywell Pressure 12 5 psig A 2 High Radiation Main Steam 17 times normal rated B g

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 1 170*F B 2 Turbine Basement Exhaust Duct High Temperature 1150*F B 1 Reactor Cleanup System High Flow 1300% of rated flow C 2 Reactor Cleanup System High Temperature 1150*F C Amendment No. 86 45

F o

NOTES FOR TABLE 3.2.A

1. Htenever 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 column 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 shall be taken.

Initiate an orderly shutdown and have the reactor in Cold Shutdown A.

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.

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 and prior to withdrawing control rods at reactor power levels below 20% rated power.

Amendment No.,96' 46

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