ML20214K972

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Proposed Tech Specs,Revising Tables 2.2.1-1,3.3.2-1 & 3.3.2-2 for Main Steam Line Radiation hi-hi Full Power Radiation Background Levels & Associated Trip Setpoints
ML20214K972
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/22/1987
From:
Public Service Enterprise Group
To:
Shared Package
ML20214K962 List:
References
NUDOCS 8705290127
Download: ML20214K972 (7)
v • d • e


Text

_ . _ _ _ _ _ _ . _ _._ _- . _ ___ -

TABLE 2.2.1-1

_O FUNCTIONAL UNIT ALLOWABLE TRIP SETPOINT

! A VALUES ..

1. Intermediate Range Monitor, Neutron Flux-High
5 120/125 divisions 5 122/125 divisions

, 2. Average Power Range Monitor:

of full scale of full scale

a. Neutron Flux-Upscale, Setdown 5 15% of RATED THERMAL POWER <

_ 20% of RATED THERMAL POWER

b. Flow Biased Simulated Thermal Power-Upscale
1) Flow Biased $ 0.66(w-aw)+51%** with 1 0.66(w-Aw)+54%** l  !

a maximum of with a maximum of l 2) High Flow Clamped 1 113.5% of RATED 1 115.5% of RATED THERMAL POWER THERMAL-POWER

c. Fixed Neutron Flux-Upscale 7 1 118% of RATED THEIMAL POWER $ 120% of RATED
  • THERMAL POWER
d. Inoperative NA NA
e. Downscale

-> 4% of RATED

> 3% of RATED l, THERMAL POWER ~ THERMAL POWER

3. Reactor Vessel Steam Dome Pressure - High-5 1037 psig
  • 1 1057 psig 2
4. Reactor Vessel Water Level - Low, Level 3 -> 12.5 inches above instrument > 11.0 inches above -

{ zero* ' instrument zero g 5. Main Steam Line. Isolation Valve - Closure

$ 8% closed 5 12% closed 3

6. Main Steam Line Radiation - High, High 1 3.0 x full power background I

k_

?,

5 3.6 x full power background

, y *See Bases Figure B 3/4 3-1.

} m

    • The Average Power Range Nonitor Scram function varies as a function of recirculation loop drive flow (w).

l Aw is-defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow. Aw = 0 for two recirculation-U loop operation. Aw = "To be determined at a later date" for single recirculation loop operation.

~

j MOVE FUhCTIONAL UNIT

  1. 6 TO PAGE 2-5 52

{07 gq p PDR

FUNCTIONAL UNIT #6 FROM PAGE 2-4 g TABLE 2.2.1-1 A

n REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS g (continued)

E ALLOWABLE FUNCTIONAL UNIT TRIP SETPOINT VALUES

7. Drywell Pressure - High 5 1.68 psig 5 1.88 psig
8. Scram Discharge Volume Water Level - High
a. Float Switch Elevation 110' 10.5" Elevation 111' O.5"
b. Level Transmitter / Trip Unit Elevation 110' 10.5"* Elevation 111' 4.5"*
9. Turbine Stop Valve - Closure 5 5% closed 5 7% closed ,
10. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low 1 530 psig 1 465 psig
11. Reactor Mode Switch Shutdown Position NA NA
12. Manual Scram NA NA

^80.5" above instrument zero EL 104' 2" for Level Transmitter / Trip Unit A&B (South Header) 83.25" above instrument zero E! 103' 11.25" for Level Transmitter / Trip Unit C&D (North Header)

[#Within24 hours prior to the planned start of the hydrogen injection test, with reactor power

( at greater than 225 of RATED THERMAL POWER. the normal full power radiation background level

( and associated trip setpoints may be changed based on a calculated value of the radiation level j

{ expected during the test. The background radiation level and associated trip setpoants may be adjusted during the test program based on either calculations or measurements of actual q radiat1on levels resulting from hydrogen anjection. The background radiation level shall be l determaned and the 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 af ter completion of the hydrogen injection test or 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 22% of RATED THERMAL POWER. while these functaons are required to be OPERABLE.

- - - m s .m n mm a - ^ ~- - .

TARLE 3.3.2-1 (Continued) 5 g ISOLATION ACTUATION INSTRUMENTATION k

m VALVE ACTUA-

  • TION GROUPS MINIMUM APPLICA8LE OPERA 8LE CHANNE OPERATIONAL TRIP FUNCTION OPERATEQY SIGNAL PERTRIPSYSTEM(g) CONDITION ACTION
3. MAIN STEAM LINE ISOLATION
a. ' Reactor Vessel Water Level - 1 2 1,2,3 21 tow Low, Level I
b. La Steam Line Radiation - 1, 2(b) 2 1,2,3 21 High, High
c. Main Steam Line Pressure - 1 2 1 22 Low
d. Main Steam Line Flow - High 1 2/line 1, 2, 3 20

$ e. Condenser Vacuus - Low 1 2 1, 2**, 3** 21 y f. Main Steam Line Tunnel 1 2/line 1,2,3 21 g Temperature - High

g. Manual Ir.itiation 1, 2, 17 2 1,2,3 25
4. REACTOR WATER CLEANUP SYSTEM ISOLATION

]~ a. .RWCU A Flow - High 7 1/ ValveI ') 1, 2, 3 23

b. RWCU A Flow - High, Timer 7 1/ Valvef ') 1, 2, 3 23
c. RWCU Area Temperature - High 7 6/ Valvef ') 1, 2, 3 23
d. RWCU Area Ventilation A 7 6/ Valve (') 1, 2, 3 23 j Temperature-High i
e. SLCS Initiation 7(I) 1/ Valvef ') 1, 2, 5# 23 l f. Reactor Vesse Water 7 2/ ValveI *) 1, 2, 3 23 Level - Low Low, Level 2
g. Manual Initiation 7 1/ Valvef ') 1, 2, 3 25

)

i TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION j ACTION ACTION 20 -

Be in at least HOT SHUTDOWN within-12 hours and in COLD SHUTOOWN

, within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21 -

8e in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 22 -

8e in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 23. - Close the affected system isolation valves within one hour and i

declare the affected system inoperable.

i ACTION 24 -

Restore the manual initiation function to OPERABLE status within 1

, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 25 -

Restore the manual initiation function to OPERA 8LE status within l

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable.

ACTION 26 -

Establish SECONDARY CONTAINMENT INTEGRITY with the Filtration,.

I Recirculation and Ventilation System (FRVS) operating within

! one hour.

ACTION 27 -

Lock the affected system isolation valves closed within one hour i

and declare the affected system inoperable.

ACTION 28 -

Place the inoperable channel in the tripped condition or close the i_ affected system isolation valves within one hour snd declare the affected system inoperable.

} ACTION 29 -

Place the inoperable channel in the tripped condition or establish i

SECONDARY CONTAINMENT INTEGRITY with the Filtration, Recirculation, j lI NSERTI and Ventilation System (FRVS) operating within one hour.

NOTES When handling irradiated fuel in the secondary containment and during CORE

    • ALTERATIONS and operations with a potential for draining the reactor vessel.

When any turbine stop valve is greater than 90% open and/or when the key-

locked bypass switch is in the Norm position.
J Refer to Specification 3.1.5 for applicebility.

Ta) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for re-

! quired surveillance without placing the trip system in the tripped condition provided at least one other OPERA 8LE channel in the same trip system is j monitoring that parameter, j (b) Also trips and isolates the mechanical vacuum pumps.

(c) Also starts the Filtration, Recirculation and Ventilation System (FRVS).

(d) Refer to Table 3.3.2-1 table notation for the listing of which valves in an '

actuation group are closed by a particular isolation signal. Refer to

' Tabic 3.6.3-1 and 3.6.5.2-1 for the listings of all valves within an actuation group.

(e) Sensors arranged per valve group, not per trip. system.

] (f) Closes only RWCU system isolation valve (s) HV-F001 and HV-F004.

(g) Requires system steam supply pressure-low coincident with drywell pressure-

! high to close turbine exhaust vacuum breaker valves.

! (h) Manual isolation closes HV-F008 only, and only following manual or automatic

, initiation of the RCIC system.

(i) Manual isolation closes HV-F003 and HV-F042 only, and only following manual or automatic initiation of the HPCI system.

l i

HOPE CREEK 3/4 3-16

--~v .,-n- , ,e - - - . . . -m- ,.,me--,, ------n-v-,,-em ,v,- re .~-,.re-ww wm m--- w w , e n e , m r e-w ,w-m-rs e-~r,,-s--.,-- re,,w -een e,ro'.n.,,- . " , ,w e,--v,- " - -,e----y,--w

_ . _= _ _ _ - . _ _.

Insert for Page 3/4 3-16

    1. 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 reactor power at greater than 22% of RATED THERMAL 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 test. The background radiation level and associated trip i

setpoints may be adjusted during the test program based i on eithar calculations or measurements of actual radiation levels resulting from hydrogen injection.

The background radiation level shall be determined and the 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 hydrogen injection test or 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 225 -

of RATED THERMAL POWER, while these functions are

{ required to be OPERABLE.

4 i

t 1

2 i

t d

, - - - - , - , - , . , ,- e - ,n.- -

-e-e--- , - e , e---,-w., ,,---.r~.- ~ - - e. ,e ,,,~r--.*r--- v--- r ,w--r---<-v~ . - ~

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TABLE 3.3.2-2, ' ' -

E ISOLATION ACTUATION INSTRUNENTATION SETFDINTS

! A j n ALLOWA8LE R TRIP FUllCTION TRIP SETPOINT VALUE <

E 1. PRIMARY CONTAllelENT ISOLATION

! a. Red _ tor Vessel Water Level i

1) Low Low, Level 2 > -38.0 inches * > -45.0 inches '
2) Low Low Low, Level 1 5 -129.0 inches
  • I -136.0 inches

! b. Drywell Pressure - High 31.68psig 31.88psig

, c. Reactor Building Exhaust Radiation - High 5 1x10 8p ci/cc** $ 1.2x10 8p Ci/cc**

d. Manual Initiation NA NA
2. SEC006ARY CONTAllelENT ISOLATION
a. Reactor Vessel Water Level -

Low Low, Level 2 1 -38.0 inches

  • 1 -45.0 inches

$ b. Drywell Pressure - High 5 1.68 psig 5 1.88 psig y c. Refueling Floor Exhaust g Radiation - High $ 2x10 8p Ci/cc** $ 2.4x10 8p ci/cc**

]

d. Reactor Building Exhaust Radiation - High 5 1x10 8p ci/cc** $ 1.2x10 8p ci/cc**

Manual Initiation

e. .NA NA i
3. MAIN STEAM LINE ISOLATION

! a. Reactor Vessel Water Level -

, Low Low Low,. Level 1 1 -129.0 inches" 1 -136.0 inches  ;

b. Main Steam Line < 3.0 X full power $ 3.6 X full power  ;
Radiation - High, High 4gr4 Eackground background i c. Main Steam Line Pressure - Low 1 756.0 psig 1 736.0 psig f
d. Main Steam Line t Flow - High $ 108.7 psid 5 111.7 psid 1

I 4 J l

m l

i i TABLE 3.3.2-2 (Continued)

g. ISOLATION ACTUATION INSTRUMENTATION SETPOINTS l

1 3

l 9 TRIP FUNCTION TRIP SETPOINT ALLOWA8LE g VALUE

7. RHR SYSTEM SHtfTDOWN COOLING MODE ISOLATION '
a. Reactor Vessel Water Level - .

Low, Level 3 > 12.5 inches

  • _ > 11.0 inches  !

, b. Reactor Vessel (RHR Cut-in

Permissive) Pressure - High 5 82.0 psig $ 102.0 psig.
c. Manual Initiation MA NA 4

L 1 "See Bases Figure B 3/4 3-1.

    • Initial setpoint.  !

l R

  • Final setpoint to be determined during startup test program.

' ***These'setpoints are as follows:

Y 160*F RWCU pipe chase room 4402 U. 140*F.- RWCU pump room and heat exchanger rooms  ;

i .135'F - RWCU pipe chase room 4505 2

  1. 30 minute time delay.

1 ##15 minute time delay. .

l

-p -_

i- ### Within 24 ' hours prior to the planned start of the ' hydrogen injection test. with reactor power j

l at greater than 225 of RATED THERNAL pogst,- the moraal full power radiation background level f

i

' and associated trip setpointe may be changed based on a calculated value of the radiation level espected during the test. The background radiation ' level and asseetated trip setpoints may be j' adjusted during the test program based on either calculations or measurements of actual '

radiation levels resulting from hydrogen injection. The beekground radiation level shall be determined and the associated trip.setpointe 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 af ter completion of the hydrogen injection test or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing resetor power levels below 225 of RATED THERNAL POWER, while these functions are

, required to be OPERABLE.

e

.., - ---m. ,

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