Text

Proposed Tech Specs,Including Table 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints, Re Hydrogen Water Water Chemistry Sys
	ML20155B786
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Site:	Hope Creek
Issue date:	09/28/1988
From:	; Public Service Enterprise Group
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ML20155B778	List: ML20155B774; ML20155B786;
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- l IAELE 2.2.I-1 I

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~ REACTOR PROJECTION SYSTEM INSTRtmfMTATICM SETPOINIS 9

(continued) 4

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^ fuhCTIONAL 1mIT AlltAsABLE 33 TRIP SEIPOINT VALUE5 g

6.

Main steam Line Radiation - High Hight i

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 9.

Turbine Stop Valve - Closure m

0-1 5% closed i 7% closed 10.

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" above instrument zero EL 104' 2" for Level Transmitter / Trip Unit A45 (South Header) 83.25" above instr - d rare Et lav 1125* far Level Traamitter/Tria Unit ran tuaeth Me *-d WITIW:

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 setpoints may be c.~

ed trip M

calculated value of the radiation 1 during the test.

N The background rael.t on level and as rf setpoints Justed during the test program based on alther caltslations or measurements of ation levels resulting from hydrogen injec-as tion. The background raJiation leve dete: mined lated trip setpoints shall ta-i set within 24 he,ers of ing normal radiation levels af ter coup e ~

the hydrogen injection tes a 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of establishing reactor power levels below 22% o ANAL e these functions are required to be OPERA 8tE.

i

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 Be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in CO within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 21 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in et least HOT SH in COLD SHUTOOWN within the ne,xt 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 22 Be in at least STARTUP vithin 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

ACTION 23 Close the affected system isolation valves within one hour and declare the affected system inoperable.

ACTION 24 Restore the sanual initiation function to OPERA 8LE status wit 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least H0T SHUTDOWN within the next 12 and in COLD SHUTDOWN within the following 24 hcurs.

ACTION 25 Restore the manual initiation function to OPERABLE status wit 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within the next hour and declare the affect.ed systee inoperable.

ACTION 26 Establish SECONDARY CONTAINMENT INTEG O TY w'*.h th Recirculation and Ventilation Systte (FRVS) operating within,

J one hour.

ACTION 27 Lock the affected system isolatiott valv2s closed within one hour 4

i and declare the affected system inoperable.

ACTION 28 Place the inoperable channel in the tripped Condition or close the affected system isolation valves within one hour and declare the affected systee ir. operable.

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 any turbine stop valve is greater than 90% open and/or when the ke locked bypass switch is in the Nors position.

Refer to 5)ecificar, ion 3.1.5 for annlicabulinv.

M M

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

full power r ower at greater than 22% of RATED THERMAL POWER, al changed based on aon background level and associated tri lated ve.lue of the radiati nts may be the test.

The backgrou tion level a expected during be adjusted during the test pro cisted trip setpoints may ments of actual radiation level either calculations or seasure-ros hydrogen injection.

The background radiation levj 1 be determine setpoints sha)1 bg M ' thin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re estab the associated trip levels aft normal radiation etion of the hydrogen injection test or of e 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ing reactor power levelt, below 22% of RATED THENHAL I

a thats functions are ranuired ta ha OpfeAAlL (a)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for re-t quired surveillance without placing the trip system in the tripped condition monituting that parameter,provided at least one other OPERA 8LE channe (b)

Also trips and isolates the rechanical vacuus pumps.

l (c)

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

j HOPE CREEK 3/4 3 16 Amendment % e

TA8tf 3.3.2-2 (Continued)

~

5y 1501A110N ACTUATION INSTRt4ENTAIION SEIPOINIS O

2 TRIP TUNCTION Alt 0WA8tE TRIP SE! POINT 7

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 i 102.0 psig c.

Manual Initiation MA NA "See Bases figure 8 3/4 3-1.

w 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

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

" ---- based on a calculated value of e and assoc-on level e 9ected during the test.* The background r evel and a during the test program based se either cale rip setpoints may be adjusted measurements of actual radiation levels resulting from t,2;;;;;. Injection ground ras a shall be determined and the associated trip setpoi set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re estab

~

1 radiation levels i

I after c 1

i,2; g. Injection test or within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of estables 1

ter power ow 22% of RATED TENGAL POWER, while these functions are receired to be OPE *>etN 1 e

l I

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 l

1 background radiation level and associated trip setpoints may 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 If a power reduction event occurs so that the reactor power J

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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e 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

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No uger7i J/Bradley

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Attorney for Philadelphia Electric Company 1

ML20155B786

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