ML20155B786

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Proposed Tech Specs,Including Table 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints, Re Hydrogen Water Water Chemistry Sys
ML20155B786
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/28/1988
From:
Public Service Enterprise Group
To:
Shared Package
ML20155B778 List:
References
NUDOCS 8810070078
Download: ML20155B786 (7)
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Text

- . _ ______ .___ - _ _ - - __ - - -- . - .. _ . - __ _ -_ __ _ . - - -_ -

4 - l

  • IAELE 2.2.I-1 o,

~ REACTOR PROJECTION SYSTEM INSTRtmfMTATICM SETPOINIS -

9 (continued) 4

.mmm ^ fuhCTIONAL 1mIT AlltAsABLE 33 TRIP SEIPOINT VALUE5 g 6. Main steam Line Radiation - High Hight g i 3.0 x full power background < 3.6 a full power f oo background pg 7. Drywell Pressure - High

! 1 1.68 psig i 1.88 psig C8 8. Scran Discharge Volume idater Level - High C C; .

m86 a. Float Switch zuc Elevation 110' 10.5"

=E Elevation 111' O.5"

, b. Level Transmitter / Trip Unit Elevation 110' 10.5"* Elevation 111' 4.5'a m 9. Turbine Stop Valve - Closure 0- 1 5% closed 10.

i 7% closed Turbine Control Valve fast Closure, Trip 011 Pressure - Low .

, 3 530 psig 1 465 psig i

11. Reactor Mode Swltch Shutdown Position M -

MA

12. Manual Scram M NA

'80.5" instr above - d instrument zero EL 104' 2" for Level Transmitter / Trip Unit A45 (South Header) 83.25" above .

WITIW: rare Et lav 1125* far Level Traamitter/Tria Unit ran tuaeth Me *-d prior to the pleened start of the t,t ga. :.n, ection test, with reacter power l than 22E of ' PthER, the normal full power radiati on background level t j

N setpoints may be c.~

The background rael.t on level and ascalculated rf value of the radiation 1 -

during ed trip the test. ' M

  • setpoints  ;

based on alther caltslations or measurements of Justed during the test program as tion. The background raJiation leve ation levels resulting from hydrogen injec-i set within 24 he,ers of -

dete: mined lated trip setpoints shall ta-injection tes ing normal radiation levels af ter coup e ~ the hydrogen ,

a 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% o ANAL e these functions are required to be OPERA 8tE.

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 -

Be inthe within at next least 24HOT hours.SHUT 00WN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in CO ACTION 21 -

ACTION 22 -

within in COLD SHUTOOWN 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> within the or ne,xt 24 be hours. in et least HOT SH ACTION 23 - Be in at least STARTUP vithin 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Close the affected system isolation valves within one hour and ACTION 24 - declare the affected system inoperable.

Restore the sanual initiation function to OPERA 8LE status wit 48 and hours in COLDor SHUTDOWN be in at withinleastthe H0T following SHUTDOWN 24 hcurs. within the next 12 ACTION 25 -

Restore the manual initiation function to OPERABLE status wit 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 ACTION 26 - next hour and declare the affect.ed systee inoperable.

J Establish SECONDARY CONTAINMENT INTEG O TY w'*.h th Recirculation and Ventilation Systte (FRVS) operating within ,

one hour.

4 ACTION 27 -

i Lock the affected system isolatiott valv2s closed within one hour ACTION 28 - and declare the affected system inoperable.

Place the inoperable channel in the tripped Condition or close the affected systee affected systemir.isolationoperable. valves within one hour and declare the ACTION 29 -

place the inoperable channel in the tripped condition or establish SECONDARY CUNTAINMENT INTEGRITY with the Filtration. Rec and Ventilation System (FRYS) operating within one hour.

NOTES When handling irradiated fuel in the'se'condary containment and during C ALTERATIONS and operations with a potential for draining the reactor vesse vhen lockedany bypass turbineswitchstop is in valve the Norsis greater position. than 90% open and/or when the ke Refer to 5)ecificar, ion 3.1.5 for annlicabulinv.

M with n 24 aours pr' p or to the planned start o" the hydrogen injection tgy M

full power r ower at greater than 22% of RATED THERMAL POWER, al changed based on aon background level and associated tri nts may be the test. The backgrou lated ve.lue of the radiati expected during tion level a cisted trip setpoints may be adjusted during the test pro ments of actual radiation level either calculations or seasure-background radiation levj ros hydrogen injection. The setpoints sha)1 bg M ' thin 241 hours0.00279 days <br />0.0669 hours <br />3.984788e-4 weeks <br />9.17005e-5 months <br /> be determine of re estab the associated trip levels aft etion of the hydrogen injection test or normal radiation I of e 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ing reactor power levelt, below 22% of RATED THENHAL a thats functions are ranuired ta ha OpfeAAlL

(a) t 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 monituting that parameter,provided at least one other OPERA 8LE channe (b) l (c) Also trips and isolates the rechanical vacuus pumps.

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

j HOPE CREEK 3/4 3 16 Amendment % e

TA8tf 3.3.2-2 (Continued) ~

5 y 1501A110N ACTUATION INSTRt4ENTAIION SEIPOINIS O

- 2 TRIP TUNCTION Alt 0WA8tE 7 TRIP SE! POINT VALUE 7.

RHR SYSTIM SHUIDOW COOL 1NG MODE 150( ATION

a. Reactor Vessel Water Level -

Low, level 3 3 12.5 inches

  • 3 11.0 inches
b. Reactor Vessel (AHR Cut-in Permissive) Pressure - High $ 82.0 psig
c. i 102.0 psig Manual Initiation MA NA w "See Bases figure 8 3/4 3-1.
1 ** Initial setpoint. Final setpoint to be determined during startup test program.

, ***These setpoints are as follows:

4'"

160*F - RWCU pipe chase room 4402 -

140*F - RWCU pump room and heat exchanger rooms 135'F - RWCU pipe chase room 4505

  1. 30 minute time delay. .

8815 minute time delav.

O.Tt:..- ** ':: s prior to the planned start of the hydrogen injection test, uith reactor V '

greater than IED THERMAL POE R, the normal full power radiation back iated trip setpoints me - e and assoc-during the test.* The background " ---- rbased on a calculated value of on level e 9ected evel and a rip setpoints may be adjusted during the test program based se either cale resulting from t,2;;;;;. Injection ground ras a measurements of actual radiation levels associated trip setpoi shall be determined and the i I after c 1 set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re estab ~

1 radiation levels 1

i,2; g. 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 estables ter power e ow 22% of RATED TENGAL POWER, while these functions are receired to be OPE *>etN 1 ,

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! INSERT l FOR TECHNICAL SPECIFICATION TABLES i l -

u 1 2.2.1-1, Reactor Protection System Instrumentation Setpoints 4 3.3.2-1, Isolation Actuation Instrumentation l 3.2.2-2, Isolation Actuation Instrumentation Setpoints

! i The hydrogen water chemistry (HWC) system shall not be  !

g placed in service until reactor power reaches 20% of RATED '

3 THERMAL POWER. After reaching 20% of RATED THERMAL POWER,  ;

j and prior to operating the NWC system, the normal full power 1 background radiation level and associated trip setpoints may l i be increased to levels previously measured during full power  ;

i

operation with hydrogen injection. Prior to decreasing l
below 20% of RATED THERMAL POWER and after the NWC system  !

, has been shutoff, the background level and associated l j setpoint shall be returned to the normal full power values. j J

If a power reduction event occurs so that the reactor power  ;

i is below 20% of RATED THERMAL POWER without the required  ;

3 setpoint change, control rod motion shall be suspended l (except for scram or other emergency actions) until the  !

i necessary setpoint adjustment is made.  ;

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iY ROSEN MINI TES" MAIN STEAM _INE MONITO' RES30NSE mse m as a vun .~

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0 0 3 10 10 14 16 17 18 22 26 30 TA 32 42 6 4 59 54 58 liYDR06EN INJECTION RATE .SCFM)

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NSL A  : NISL 6 -* - itSL C ItSL0 l

General ~ Electric HWC Steam Activity: HWC/NWC 6.0 D2 M '

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' I X Duane Arnold (DA) o N V Hotch-1 (H2) 0 Nucionor (Nuc) m- g'- + Nine Mie Po!nt-1 (NMP1) 1.0 -

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"" Wil ' A Miilotone (Wii)

Y Hope Creek (HC) oA soc d OPemting Point <-0.23 V SIE 0.0 -

i i i i i O.0 0.4 0.8 1.2 1.6 2.0 2.4 Feedwater Hydrogen Concentration (PPM)

Iigure I-3 NirmalIIed P',1 RM Act ivity v'. feedwater ifydrogen foncenI rat ion in Ion llWC Mini Test <.

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UNITED STATES OF A\tFRICA MJCLEAR REGULATORY C0bt4ISSION In the Matter of  : Docket No. 50-352 l PillLADELPillA ELECTRIC COMPANY  :

(Limerick Generating Station,  : ,

Unit No. L)  ;

CERTIFICATn OF SFRVICE t

I hereby certify that copies of the foregoing Application for Amendment of Facility Operating License NPF-39 in the above captioned matter were served on the following by deposit in the United States Mail, first class postage prepaid, on the 29th day of September,1988.

William T. Russell, Regional Adminir,trator U.S. Nuclear Regulatory Commission ,

Region I '

475 A11entale Road King of Prussia, PA 19406 ,

i T. J. Kenny t U.S. Nuclear Regulatory Commission  !

Senior Resident Inspector {

P.O. Box 47 Sanatoga, PA 19468 l l

Thomas Gerusky, Director Bureau of Radiological Protection '

Department of Environmental Resources P.O. Dox 2063 lbrrisburg, PA 17120 l

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& No -,

uger7i J/Bradley [ l l

Attorney for 1 Philadelphia Electric Company l

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