Text

Proposed Tech Specs Extending STIs & Allowed out-of-svc Times for Isolation Actuation Instrumentation
	ML20059A801
Person / Time
Site:	Hope Creek
Issue date:	10/18/1993
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML20059A797	List: ML20059A793; ML20059A801;
References
	NLR-N93015, NUDOCS 9310270129
	Download: ML20059A801 (10)
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ATTACIIMENT 2 i

TECIINICAL SPECIFICATION PAGES WITII PEN AND INK CHANGES l LICENSE AMENDMENT APPLICATION 93-03, NLR-N93015 STI/AOT EXTENSIONS FOR ISOLATION ACTUATION INSTRUMENTATION FACILITY OPERATING LICENSE NPF-57 IIOPE CREEK GENERATING STATION DOCKET NO. 50-354 The following Technical Specifications have been revised to reflect the proposed changes:

Technical Specification Pace l

3.3.2 3/4 3-9 Table 3.3.2-1 3/4 3-11 3/4 3-15 3/4 3-16a 1

Table 4.3.2.1-1 3/4 3-28 3/4 3-29 3/4 3-30 3/4 3-31 3/4.3.2 Bases B 3/4 3-2 9310270129 DR 931018 I?

ADDCK 05000354 [-

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INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

1

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

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INSEfiT

t. P4w-the-numbee-of-oFERABLE- channels less th= requt+ed-by-the-Mhiaem 4 -ORERABLE Channels per Teip System requirement fnr nn. trip cyst g place the inoperable channel (n) and/or that trip cyctom in the t r i nne.d condition

within nna hnge The nenwicinne nf $peciffratinn 't na are not appliceble

e. W i th-t he-number-o f--OPERABLE-c han nels-l es s-t han-required-by-t he-Mimmum ;

-OPERABLE-Channels-per Trip System-requirement-for-both-trip-systees, place-et-least--one-tr4p-system ** in the-tr4pped-condition with4 a one-.

houe-and-take-the-AGT404-requir-ed-by--Teble 3. 3. 2-1.

An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken, 18The-tr4 p-sy s t em-need-no t--be--ple c-ed-in-the-t r4 pped-cond it4 e n-14-tMs-wou4d-k!

-cause the Trip Function to occue when a trip systee can be placed in +he t rippari enndition without causing tha Tein Functiaa ta occurr place the tria

-syctam with the most inoperable channals in the trJpped condition; if hath {

systems-have -the-same-number-of-inoperable-channels r -place-e4ther-trJp system-

-i n-the-t-eipped-condit4 on. .

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TABLE 3.3.2-1 (Continued)

A 150(ATION ACTUATION INSTRUNENTATION 3

p VALVE ACTU4-TION Ga00PS MININLM APPLICABLE gle Fur.Cil0ll OPERATE SIGNALg 0 gy OPERAttE CHAIOff g ) OPERAll0N#1

, PER TRIP SYSTEM _ CONDITION ACI!ON 7.

ENR SYSTEN SHUT 00681 COOLIIIG MODE ~ ISOLATION

n. Reactor Wessel lister Level - Law Level 3 3 2/ ValveI ') 1, 2, 3 27

b. Reactor Vessel (RHR Cut-in (b)

- Permissive) Pressure - High 3 2/ ValveI ') 1, 2, 3 27

c. Manual Initiation 3 1/ ValveI ') 1, 2, 3 25 R

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TABLE 3.3.2-1 (Continued)

NOTES l

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.

Refer to Specification 3.1.5 for applicability.

1. The hydrogen water chemistry (HWC) system shall not be placed in service until reactor power reaches 20% of RATED THERMAL POWER. After reaching 20%

f of RATED THERMAL POWER, and prior to operating the HWC system, the normal full power background radiation level and associated trip setpoints may be increased to levels previously measured during full power operation with hydrogen injection. Prior to decreasing below 20% of RATED THERMAL POWER and after the HWC system has been shutoff, the background level and associated setpoint shall be returned to the normal full power values. If a power reduction event occurs so that the reactor power is below 20% of RATED THERMAL POWER without the required setpoint change, control rod motion shall be suspended (except for scram or other emerge etions) until the necessary setpoint adjustment is made.

(a) A channel may be placed in an inoperable status for up to ours for re- :

quired surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip ,

system is monitoring that parameter.

(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 Tables 3.6.3-1 and 3.6.S.2-1 for the listings of all valves within an !

actuation group. i (e) Sensors arranged per valve group, not per trip system. i (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. 3 (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.

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Amendment No. 57 HOPE CREEK 3/4 3-164 !

_ _ . _ _ _ _ _ _ _ _ _ _ ____9

TABLE 4.3.2.1-1 5

g- ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS h CHANNEL OPERATIONAL 7 '

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

1. PRIMARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level -

1) Low Low, Level 2 S Q &

_/ R . 1, 2, 3

2) Low Low Low, Level 1 5 Q M R 1, 2, . 3

b. Drywell Pressure - High 5 O # R 1, 2, 3

c. Reactor Building Exhaust Radiation - High 5 Q # R 1, 2, 3

d. Manual Initiation NA Q #g NA 1,2,3

2. SECONDARY CONTAINMENT ISOLATION

$ a. Reactor Vessel Water Level -

Low Low, Level 2 Q _*

p'

. 5 R 1, 2, 3 and

4, b. Drywell Pressure - High S G M R' 1, 2, 3

c. Refueling Floor Exhaust Radiation - High S Q

R 1, 2, 3 and *

d. Reactor Building Exhaust.

Radiation - High S R 1, 2, 3 and

q a)

e. Manual' Initiation NA O[+4 NA 1, 2,.3 and *

3. MAIN STEAM LINE ISOLATION

a. Reactor Vessel Water Level - F Low Low Low, Level 1 S G 4 R 1, 2, 3

b. Main Steam Line Radiation'- High,'High S Q -M- R 1,2,3

c. Main Steam Line Pressure - Low S Q -M- R 1

.d. Main Steam Line Flow - High S Q 4 R 1, 2, . 3

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS n CHANNEL OPERATIONAL g CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH p TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED MAIN STEAM LINE ISOLATION (Continued)

Y

e. Condenser Vacuum - Low S QI R 1, 2**, 3**

f. ' Main Steam Line Tunnel Temperature - High NA Q M R 1, 2, 3

g. Manual Initiation NA Q M-(a) NA 1,2,3

4. REACTOR WATER CLEANUP SYSTEM ISOLATION p/

a. RWCU a Flow - High S G -M- R 1,2,3

b. RWCU A flow - High, Timer NA Q -M- R 1,2,3

$ c. 'RWCU Area-Temperature - High NA Q # R 1,2,3

<;* d. RWCU Area Ventilation a y Temperature - High NA Q -M- R 1, 2, 3

e. SLCS Initiation Q #

, NA -M(b) NA 1, 2, 5

f. Reactor Vessel Water level - Low Low, Level 2 5 Q -M- R 1,2,3

g. Manual Initiation I ")

NA Q M NA 1, 2, 3

5. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

a. RCIC Steam Line a 8 Pressure (Flow) - High NA G M- R 1, 2, 3

b. RCIC Steam Line a Pressure (Flow) - High, Timer NA Q #- R 1, 2, 3

c. RCIC Steam Supply Pressure -

Low NA Q -M- R 1, 2, 3

d. RCIC Turbine Exhaust Diaphragm Pressure - High NA Q _

-M- R 1, 2, 3

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TABLE 4.3.2.1-1 (Continued)

.k ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

[

=-

CHANNEL OPERATIONAL CHANNEL . FUNCTIONAL CHANNEL CONDITIONS FOR WHICH

.g TRIP FUDCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued)

e. RCIC Pump Room F

, Temperature-- High NA Q 44- R 1, 2, 3

f. RCIC Pump Room Ventilation i

. Ducts a Temperature - High NA O M R 1, 2, 3

g. RCIC Pipe Routing Area Temperature - High ~ NA Q -M R 1,2,3

h. RCIC Torus Compartment Temperature -High NA Q -M- R 1, 2, 3 g i. Drywell Pressure - High S Q -M .

R 1,2,3

j. ~ Manual' Initiation NA R NA 1, 2, 3 5 6. HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION

a. HPCI Steam Line a F Pressure (Flow) - High NA .Q -M- R 1,2,3

b. HPCI Steam Line a Pressure (Flow) High, Timer NA G + R 1, 2, 3

c. HPCI Steam Supply Pressure'-' Low NA Q -M- R 1,2,3

d. .- HPCI Turbine Exhaust-

. Diaphragm Pressure - High NA O -M- R 1, 2, 3

e. HPCI Pump Room

- Temperature'- High' NA' Q -M- R - 1, 2, 3

f. HPCI Pump Room Ventilation Ducts a Temperature.- High NA' O -M- R 1, 2, 3

g. HPCI Pipe Routing Area . .

Temperature - High NA Q -M- R 1, 2, 3 wm..-h aa- --__-----a _ A m sa ae e <wiprg a weA--u w.moaw&w ,,- enw wsyv- w -ww-e e+wrig,i -ewww. - es egg yw w use-wa*wy-!! r y wigv- g- pey,- .y y,y ig.-er 1-wr = y-g g w->w-gg'y g w -ye + +ye-,-g-- w.. -qy v y-gr-w+-p , m

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TABLE 4.3.2.1-1 (Continued) 5 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS m

CHANNEL OPERATIONAL Q

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION (Continued)

h. HPCI Torus Compartment F Temperature - High NA Q #- R 1,2,3

i. Drywell Pressure - High NA Q& R 1, 2, 3

j. Manual Initiation NA R NA 1, 2, 3

7. RHR SYSTEM SHUT 00WH COOLING MODE ISOLATION

a. Reactor Vessel Water Level - 8 Low, Level 3 5 Q -M- R 1,2,3 R

b. Reactor Vessel (RHR Cut-in Permissive) Pressure - High NA O 4 R 1,2,3 J,

s

c. Manual Initiation NA Q ga)

NA 1,2,3

" 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.

Refer to Specification 3.1.5 for applicability.

(a) Manual initiation switches shall be tested at least once per 18 months during shutdown. All ot r circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per M sdays as part of circuitry required to be tested for automatic system isolation. \

(b) Each train or logic chanrel shall be tested at least every other 31 days. 92.

b

4 INSTRUMENTATION i BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION lN$6Rf 6 This specification ensures the effectiveness of the instrument ion used f to eitigate the consequences of accidents by prescribing the OPERA 8 LITY trip t setpoints and response times for isolation of the reactor systems. When necessary, i one channel may be inoperable for brief intervals to conduct required surveillance. '

Some of the trip settings may have tolerances explicitly stated where both the high !

and low values are critical and may have a substantial effect on safety. The set-points of other instrumentation, where only the high or low and of the setting i have a direct bearing on safety, are established at a level away from the normal !

operating range to prevent inadvertent actuation of the systems involved. #

f Except for the MSI9s, the safety analysis does not address individual sensor i response times or the response times of the logic systems to which the sensors !

are connected. For D.C. operated valves, a 3 second delay is assumed before the valve starts to move. For A.C. operated valves, it is assumed that the A.C. power supply is lost and is restored by startup of the emergency diesel In this event, a time of 13 seconds.is assumed before the valve generators.

starts to move. In addition to the pipe break, the failure of the D.C. operated !

i valve is assumed; thus the signal delay (sensor response) is concurrent with -

the 10 second diesel startup. The safety analysis. considers an allowable 1 inventory loss in each case which in turn determines the valve speed in conjunc- !

tion with the 13 second delay. It follows that checking the valve speeds

' and the 13 second time for emergency power estabitshment will establish the -l response time for the isolation functions.

Operation with a trip set less conservative than its Trip 5etpoint but {

within its specified Allowable Value is acceptable on the basis that the j difference between each Trip Setpoint and the Alloweble Value is an allowance i for instrument drif t specifically allocated for each trip in the safety analyses. :

i 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRLMENTATION .

The emergency care cooling system actuation instrumentation is provided l to initiate actions to mitigate the consequences of accidents that are beyond l the ability of the operater to control. This specification provides the !

OPERASILITY requirements, trip setpoints and response times that will ensure )

effectiveness of the systems to provide the design protection. Although the !

instruments are listed by system, in some cases the same instrument may be used- j to send the actuation signal to more than one system at the same-time. ;

Operation with a trip set less conservative than its Trip setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is an allowance for instrument drift sp'ecifically allocated for each trip in the safety analyses.

HOPE CREEK B 3/4 3-2 1

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ML20059A801

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