ML20058C634

Proposed Tech Specs,Per Method Utilized in New STS

ML20058C634
Person / Time
Site:	Hope Creek
Issue date:	11/16/1993
From:	Public Service Enterprise Group
To:
Shared Package
ML20058C610	List: ML20058C606 ML20058C634
References
NLR-N93161, NUDOCS 9312020515
Download: ML20058C634 (13)

Text

'

ATTACllMENT 2 TECIINICAL SPECIFICATION PAGES WITil PEN AND INK CIIANGES t

REVISION

"'O LICENSE AMENDMENT APPLICATION 92-10, NLR-N93161 INSTRUMENTATION REQUIREMENTS FOR SINGLE IDOP OPERATIONS FACILITY OPERATING LICENSE-HPF-57 IIOPE CREEK GENEPATING STATION DOCKET NO. 50-354 The following Technical Specifications have been revised to reflect the proposed changes:

t Technical Specification facte 2.2.1, Table 2.2.1-1 2-4 Specification 3.0.5 3/4 0-1 l

l 3. ?.; ?

3/4 2-2 f

3/4.1.1 3/4 4-1 3/4 4-2 3/4 4-2a Specification 3.0.5 Bases B 3/4 0-3 l Bases B 3/4 4-1 B 3/4 4-1 i

f P

TABLE 2.2.1-1 x

REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS m

Q ALLOWABLE p

FUNCTIONAL UNIT TRIP SETPOINT VALUES n

1.

Intermediate Range Monitor, Neutron Flux-High 5 120/125 divisions 5 122/125 divisions of full scale of full scale 2.

Average Power Range Monitor:

a.

Neutron Flux-Upscale, Setdown 5 15% of RATED THERMAL POWER i 20% of RATED THERMAL POWER b.

Flow Biased Simulated Thermal Power-Upscale

1) Flow Biased 5 0.66(w-Aw)+51%** with 5 0.66(w-aw)+54%**

a maximum of with a maximum of

2) High Flow Clamped 5 113.5% of RATED

$ 115.5% of RATED TliERMAL POWER THERMAL POWER rp c.

Fixed Neutron Flux-Upscale 5 118% of RATED THERMAL POWER

$ 120% of RATED

=

THERMAL POWER d.

Inoperative NA NA 3.

Reactor Vessel Steam Dome Pressure - High 5 1037 psig 5 1057 psig 4.

Reactor Vessel Water Level - Low, Level 3

-> 12.5. inches above instrument

> 11.0 inches above zero*

- instrument zero 5.

Main Steam Line Isolation Valve - Closure 5 6% closed 5 12% closed

• See Bases Figure B 3/4 3-1.

E

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

=

y ow is-defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and sinale loop operation atA he same core flow.

Aw = 0 for two recirculation a

5 loop operation. Aw = :"Tc bc detemined at

!ater-dat#1 for single recirculation loop operation.

?

Cyclo W

r

~

r 1

3/4.0 APPLICA82LITY l

/

~i LINITING CONDITION FOR OPERATION 3.0.1 -Compliance with the Limiting conditions' for Operation contained in th succeeding Specifications is_ required during the OPERATIONAL CONDITIO conditions specified'therein;. except that voon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 the Limiting Condition for Operation and associated AC 1

not met within the specified time intervals.

l If the Lietting Condition'for Operation is restored prior to expiration of the specified time intervals, qompletion of the Action requirements is not required.

3. 0. 3 in the associated ACTION requirements, within one hour ated to place the unit in an OPERATIONAL CONDITION in which the Specificationa does not apply by placing it, as applicable, in:

I 1.

At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective esasures are cospleted that permit operation under the ACTION 1

~

requirements, the ACTION may be taken in accordance with the specified time-i\\

limits as measured from the time of failure to meet the Limitim Con Operation.

Exceptions to these requirements are stated in the 'ndividual Specifications.

{

This Specification is not applicable in CPERATIOML CONDITIONS 4 or 5.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Candition for Operation are not met and the associated ACTION' requires a. shutdown if they are not met

+

within a specified time interval.

Entry into'an OPERAT10E L CONDITION'or other specified condition may be made in accordance with the ACTION-requirements when conformance to then permits continued operation of the facility for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual =

Specifications.

INSERT A-i l

i l

HOPE CREEK 3/4 0 1 Amendment No.

19-SEP 2 81988

I t

POWER DicTRIBUTION LIMITS 1

t 3/4.2.2 RM SETPOINTS i

LIMITING CONDITION FOR OPERATION

^

r 3.2.2 The APRM flow biased simulated thermal power upscale scram trip setpoint (S) and flow biased neutron flux upscale control rod-block trip setpoint (5 shall be established according to tne following relationships:

93)'

TRIP SETPOINT ALLOWABLE VALUE 5 < (0.66(w-aw)** + 517%)T S < (0.66(w-aw)** + 54%)T SRB i (0.66(w-aw)** + 42%)T S ~ $ (0.66(w-aw)** + 45%)T

(

i p

where:

5 and 5 0 are in percent of RATED THERMAL POWER, 1

W = Loop recirculation flow as a percentage of the loop recirculation flow'which produces a rated core flow of 100 million lbs/hr, j

T = Lowest value of the ratio of FRACTION OF RATED THERMAL PO (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING' POWER I

DENSITY-(CMFLPD).

T is applied only if less e an or equal to 1.0.

{

APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

j ACTION:

I 4

With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased neutron flux upscale control rod block trip setpoint less conservative than the value shown in the Allowable Value column for 5 or 5 above determined, initiate corrective action within 15 minutes and adjust $0.-as-or S and/'

THERML POWER to less than 25% of RATED THERMAL PO!

SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP and the CMFLPD shall be determined,- the value of T calculatec.

and the most recent actual APRM flow biased simulated thermal power upscale scram and flow biased neutron flux upscale control rod block trip'setpoints r

verified to be within the above limits or adjusted, as required;

!i At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a.

' b.

i Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating l

c.

with CMFLPD greater than or equal to FRTP.

j d.

The provisions of Specification 4.0.4 are not applicable.

"With CMFLPD greater than the FRTP, rather than adjusting the APRM setoo mts. the I

APRM gain may be adjusted such that the APRM readings are greater than or ecual to 100% times CMFLPD provided that the adjusted APRM reading does not e=ceec-i 100% of RATED THERMAL POWER and a notice of. adjustment is posted on the -eactor t

control panel.

• • The Average Power Range Monitor Scram function varies as a function of rec ucu-

}

1ation loop drive flow (w). 'aw is defined as the difference in indicateo cr've-q flow (in percent of drive flow which produces rated core flow) between t o ' cop -

and sin' gle loop operation at the same core flow.

j

~aw = O lor two recirculation i

loop operation.

Aw =l"To be dete @ ;d :t : ':t:- d:tc"I for single recirculation -

-loop. operation.

e f

{

HOPE CREEK Y

3/4 2-2 Amendment No. 34 J

I t

3/A 1 3EAC*:R:CCLANT 5'5'Eu 6

3/4 4 1 3EC::CULAi!CN sv57Eu IEC*2CULA**CN.0005 1

f i

.:wi~:NG ::N0!~:0N c0R OPE #AT:CN t

3. 4.1. '

.o reactor coolant system recirculation loops small te 'in c: erst'On

.ith:

t Total core flow greater than or ecual to a5% of ratec core '1sw.

4.

or THERMAL POWER 1ess than er equal to the limit specified in 0.

Figure 3.4.1.1-1.

APPLICABILITY: OPERATICNAL CONDITICNS l' and 2" J

ACTION:

t, I!

with one reactor coolant system recirculation 1000 not in operation:

a.

1.

Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:

t a)

Place the recirculation flow control system in the Local Manual moce, and b)

Reduce THERMAL POWER to 170% of RATED THERMAL POWER, and t

t c)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety. -

f Limit by 0.01 to 1.08 per Specification 2.1.2, and I

d)

Reduce the Maximum Average Planar Linear Heat Generat'On t

Rate (MAPLHGR) liett to a value of 0.86 times the two del _ETED 3 rectreulation toep timit per specification 3.2.1,. ara yj

n-ef*'*::::: the e ve-e;: "r_;r "tr;; " riter (.***M) Stre eae 2 c Elect ":riter 7-ip Setred at e e-d '2"c t$1-Ve19-*

'a

• aa**

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.appi-i<ce!: for :f ;10 ---freu!etie- '^e; ace etim. a r

!;eri'! cati:n:-2.4.1,~3.2.2 :n 3.3.5 i

3k3./,

f)

Limit the speed of the operating recirculation puso to a

less th',n er esual to 905 of rated pump speed, anc IWSERT-g) 1,Qorm sur93,rillance recuirement 4.4.1.1.2 if THERMAL. *0wER-p.

,,37to 7se n t po,c,,,t

,,,,,coiet,,,

(1 3;ji-flow in the operating loop is 1 505 ** of rated looo flow.

- 5.

The provisions of specification 3.0.4 are not appitcaole.

1 '

• - 1 Otherwise be in at Seast HOT SHUTDOWN within the next 12 m f

ours "See Special Test Exception 3.10.4 JL_

}

"* Initial'==1iien riael vetere te de deter:fr; euring sterte; Te ti ; estos

' ::n in: 'J.r ;n:14 "i r l W A-end-coe4cewle64:n 1:;; "1:

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.1 ween the en1d watae f enen tha waamm1 ha t t aan u =d_ n, e. m_ un_ a+ 4 aa. a t en t i f 4 c a_ t t a_ a i

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t HOPE CREEK' 3/4 4-1 Amendment 40.

15 t

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e ar :-

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-E..wA. 27 5E :s 'ess : a :-

e:.a' :: : e v: s:ect " ec n **gare 3.4 ; ;-l.1:n

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'- : ate essores to s' ace :ne an't 4 9 at ' east STAE*.

--- i :urs aac

-C Seu :0WN.itnin tre next 6 nours

( _40*/6l _

.itn.cne or

• o mact:r ::clant system *ecir:ulation ':::s - :e t tion anc total ::re f1:w less than 45% out greater tran 24.4 Figure 3.4.1.1-1:ratec :cre flow anc raERMAL PChER greater inan tne limt:

s:e: < e:

1.

Determine the APRM anc LPRM" noise levels (Surveillance A.4.1.1.a):

a)

At least once :er 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and c) within 30 minutes after tne c moletion of a 'aE:ua. :C.i:

increase of at : east 5% of RATED THERMAL PChER.

2.

with the APRM or LPRM" eeutron flux noise levels greate*

a-nree times thelr.estaclisnec baseline noise levels.. :-

.i mini,tes initiate c:rrective action to restore the noise eve's to within the.requirac limits wrtnin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ey incre MAL POWER to less than or equal;to in ure'3.4.1.1-1, limit specifisc i, Fi;-

d'

' 0' 4

c.

With one or two reactor coolant system reci. u1 tion laces ia 4

e t-ana _ total core flow ~1ess-than or equal: to 995#1 and THERMAL 8C.54 ; e ne -

than the_ limit specified in Figure 3.4.1.;.-l.'within 15 miettes '-

• ne corrective action to ~ reduce THERMAL POWER to less tnan oc ecua:

the limit Apocifiec in Figure 3.4.1.1-1 or _ increase care f1:w : ; este*

taant-39Rd itnin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

A 4.1.1.1 Wit.

reactrt at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that: coolant system recirculation loop not in ocera :-

ReactorTHERMALPOWERisj70%ofRATEDTHERMALPOWER,anc a.

The recirculation flow control system is in the Local Manual mece.

c.

and The speec of the operating recirculation pump is less than or es.a c.

to 90E of rated p = ana_[ad, anc 40*h c-Core flow is greater thaRl49Ea" nen THERMAL power is greater than c.

the limit specified in Figure h.a.1.1-1.

• tatector levels A and C of one LPRM string per core octant plus detectors a ano C of one LPRM string in the center of the core should se monitorea.

4 M M 41 V lu :.

Sel. le;; 1 07 C o-

'E:0 tr'Eg Star *"" *:::

Jtz itn A; n r::f r:;1 ti:n ;- :: _

e yi t : n ::::c).

1

• 0PE CREEK 3/4 a-2 Amendment No-3

=

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1 UEAC"CR ::CLANT 5<5754 SURVEILLANCE RECUIREWENTS i

A4 1.1.2

• itn one eactor : ol.snt system eci :214:1:n ':co ot

-tt**,

4a o more inan 15 minutes or'ar ::

cers:

4 estrer *-ERMAL 3CbER i c esse :- ec:--

!at*:n ' 0c fl0* 'ncrease. <ertfy snat tne 's!i:wiag c.**erent ai e:utre+ eats are met if tetce st, e 7WERMAL #ChER is <lk;L*lef RATED ~~ERMAL :CwEa r te ec'e:a'at* n t:co flow loop f'ow:

in tne operating Pbcirc0lation toco is < 50

[ gg sl

~

of stea y

145*F totween reactor vessel steam space coolant and cottom m a.

drain line coolant, and ead

< 50*F between the re6ctor coolant within the loop not in operetton o.

and the coolant in the reactor pressure vessel, and

< 50*F between the reactor coolant within the loop not in operation c.

and the operating 1000 The differential temperature recuirements or Scecifications 4 4 1 1 2b and i

4.4.1.1.2c co net acoly wnen the loco not in operation is isolated f r s the i

reactor pressure vessel.

4.4.1.1.3 Each oumo MG set scoop tues mechanical and electrical stoo sna11 demonstrated OPERA 8LE with overspeed setpoints less than or equal to 109% and ee 107%. respectively, of rated core flow, at least once per 18 months.

4.4.1.1.4 Establish a baseline APRM and LPRM" neutron flux noise value witnta the regions for which monitoring is reovired (Specification 3.4.1.1, ACTION c t within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for which monitoring is required unless caselining has previously caen performed in the region since the last refuel'ag outage.

i i

?

" Detector levels A and C of one LP4M string per core octant plus detectors A

^i and C of one LPRM string in the center of the core should be monitored.

,p --

1. initfel valee!.

c!n:! ::!e:: to-t: ceter:fr.;c cur 4ng St: rte: esting besed T

"De 'Aa 'h*esheld N TL WE9se ::inu!!?n M: *b"4-*

-411

-s- - ? ' ka cc M e:tes-t m th: :::::t t:ttr h.::: ; ;;;nt4eg :trettricet ca i

HOPE CREEK 3/4 4-Za Amenonent No. 15

7 I

3/4.0 APPLICABILITY BASE 5 (Con't) allowacle time to reach COLD SHUT 00VN, or othe For example, if STARTUP is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to-reducea.

reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total SHUT 00WN is not recuced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed that would permit a return to POWER coera a penalty is not incurred by having to reach a lower CONDITION of operation i less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in antry into an OPERATIONALCONDITION or condition of Concition for Operation are not met. operation for.nother specification in wh If the new speci.. cation becomes appli-cable in less time than specified, the difference may be added to the allowable outage time limits of the second specification.

However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not Condition for Operation is not met in a lower CONDITION o The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Soecification 3.0.4 establishes limitations on a change in OPERATIONAL CONDI-TICNS wnen a Limiting Condition for Operation is not met.

It precludes placing the facility in a higher CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to coecly with the ACTION require-ments if a change in CONDITIONS were permitted.

The purpose of this specifi-cation is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERA 8LE status or parameters to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS.

Therefore, in this case, entry into an OPERATIONAL CON 0! TION or other specified condition may be made in accordance with the provisions of the ACTION require-The provisions of this specification should not, however, be inter-ments.

preted as endorsing the failure to exercisa good practice in restoring systems or components to OPERA 8tE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions I

of Specification 3.0.4 do not apply because they would delay placing the facility in a lower CONDITION of operation.

INSERT B

HOPE CREEK 8 3/4 0-3 Amendment No. 19 SEP 2 g iggg

1 3/4.a REACTOR COCLANT SYSTEM BASES i

3/4.4.1 RECIRCULATION SYSTEM The impact of single recirculation loop operation upon plant safety is assessed and shows that single loop operation is permitted if the MCPR fuel cladding Safety Limit is increased as noted by Specification 2.1.2, APRM and 3.3.6-2, respectively. scram and control rod block setpoints are adjusted as in Specification 3.2.1, and MCPR operating limits are adjusted perM Specification 3/4.2.3.

3gw loop is imposed to exclude the possibility of excesh ve i

The surveillance on differential temperatures below'4048) THERMAL POWER o rated recirculation loop flow is to mitigate the undue thermal stress on vesse'

~

nozzles, retirculating pump and vessel bottom head during the extenced operation of the single recirculation loop mode.

An inoperable jet pump is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does, in case of a design-basis-eccident increase the blowdown area and reduce the capability of reflooding the cc e; thus, the requirement for shutdown of the facility with a jet pump inoperable Jet pump failure can be detected by monitoring jet pump performance on a prescrioed schedule for significant degradation.

LOCA analysis design criteria for two recirculation loop opera will ensure an adequate core flow coastdown from either recirculation loce

'c'-

The lie ts i

lowing a LOCA.

two loop operation, continued operation is permitted in a sing

'g loop mode.

In order to prevent undue stress on the vessel nozzles and bottom heac reginn, the recirculation loop temperatures shall be within 50*F of each ota prior to startup of an idle loop.

e-The loop temperature must also be witnin 50*F of the reactor pressure vesse_l coolant temperature to prevent thermal ss c to the recirculation pump and recirculation nozzles.

o Sudden equalization of temperature difference > 145'F between the reactor vessel bottom head coolant a

and the coolant in the upper region of the reactor vessel by increasing core flow rate would cause undue stress in the reactor vessel bottom head.

with margin over the normal operating domain.The objective of GE B However, at the high power /lo.

flow corner of the operating domain, a small probability of limit cycle neuteca flux oscillations exists depending on combinations of operating conditions (e g rod pattern, power shape).

To provide assurance that neutron flux limit cycle oscillations are detected and suppressed, APRM and LPRM neutron flux noise leveis should be monitored while operating in this region.

M Wit 44bvahet.

rin:1 value: vi" bc kt+mbed tring Stav4up-T+ sting tmc

-upon-the-thrc:h:1d THER"M POWER and recirculat4en 1:cp-flcu etch uf : ::p

-the-co H-water frc. the-vesu l batte: F.;ed. Or:v;ntinc ;eter:tien c HOPE CREEK B 3/4 4-1 8=ndment No. 3

l 4

- Attachment 2 NLR-N93161 i

Inserts for Marked-Up Pages Revision to LCR 92-10 l

INSERT A 3.0.5 Equip:ent rtrcreed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to l

perform testing required to demonstrate its OPERABIIIIY or the OPERABIIIIY of l

other equipment. 'Ihis is an exception to lfD 3 0 2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABIIlTY.

i INSERT C t

2.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reduce the Average Power Range Monitor (APRM) Scram Trip Setpoints and Allowable Values to those applicable for sirgle recirculation loop operation per Specifications 2.2.1 ard 3.2.2; otherwise, with the Trip Setpoints and Allwable Values associated with one trip system not reduced to those applicable for single recirculation loop operation, place the affected trip system in the tripped condition l

and within the follwing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, reduce the Trip Setpoints and Allwable Values of the affected channels to those applicable for siIgle recirculation loop operation per Specifications 2.2.1 and 3.2.2.

3.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reduce the APRM Control Rod Block Trip Setpoints and f

Allowable Values to those applicable for sirgle recirculation loop operation per Specifications 3.2.2 and 3.3.6; otherwise, with the Trip l

Setpoints and Allowable Values associated with one trip function not r*rwl to those applicable for sirgle recirculation loop operation, place at least one affected channel in the tripped cordition and within the followirg 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, reduce the Trip Setpoints and Allwable Values of the affected channels to thoea applicable for single recirculation loop i

operation per Specifications 3.2.2 aM 3.3.6.

t 4.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reduce the Rod Block Monitor Trip Setpoints and Allowable values to those applicable for sirgle recirculation loop operation per Specification 3.3.6; otherwise, with the Trip Setpoints ard A11mable l

Values associated with one trip function not reduced to those applicable f

for single recirculation loop operation, place at least one affected channel in the tripped condition ard within the follwing 6 hcurs, reduce the Trip Setpoints aM Allowable Values of the remainity channels to j

those applicable for single recirculation loop operation per Specification 3.3.6.

I i

i i

Insert Page 1 of 2 t

1,rr

• Attachment 2 NLR-N93161 j

Inserts for Marked-Up Pages Revision to LCR 92-10 INSERT B i

Sr>ecification 3.0.5 establishes the allowance for restorirg equipment to service urder administrative controls when it has been renoved fram service or declami inoperable to canply with ACTIONS. The sole purpose of this l

Specification is to provide an exception to IID 3.0.2 (e.g., to not comply with the applicable Required Action (s)) to allow the performance of testing i

required to restore ard denenstrate:

a.

The OPERABILITY of the cquipment beirg returned to service; or r

b.

The OPERABILITY of other equipment.

r i

The administrative controls ensure the time the equi; rent is returned to service in conflict with the requirenents of the ACTIONS is limited to the time absolutely necessary to perform the testirg required to restore ard demonstrate the OPERABIIJTY of the equipment. This Specification does not provide time to perfom any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment beirg returned to

[

service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the testing required to restore ard demonstrate OPERABILITV.

{

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped cordition to prevent the trip function from occurrirg durity the performaru of testing regaired to

[

restore OPERABILITY on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipnent is takiry an inoperable channel or trip system out of the tripped cordition to permit the logic to function ard indicate the appropriate response during the performance of testing required to restore and demonstrate OPERABILITY on another channel in the same trip system."

?

IID 3.0.5 is applicable to all Technical Specifications; however, the intent of IID 3.0.5 is not to supermde more specific guidance contained within any individual specification.

l t

i i

I Insert Page 2 of 2 i

i

ATI70ME2ff 3 DESCRII7 RIOT OF REVISIOE TO HDIE QEEK Im 92-10 REVISIQi 'IO IJCDEE AMDil24DTr APPLICWrIO4 IJUIMJMDTIATIOi RDQUIREMENIS Im SDCIE IOOP OPERATIONS IDIE QEEK GDIERATDC STATIO4 FACILITY OPERATDG IJCDEE NPF-57 NIR-N93161 DOCKLT 10. 50-354 REVISIOi 70 Im 92-10 1.

QWEES 'IO 7EE DFSCRIPTIOff OF 7HE PROPOSED OWCES Replam Section I.C of Attachrent 1 to NIR-N92187 with the follwing:

C.

Specification 3.0.5 Add Limiting Condition for Operation (IID) 3.0.5 of IUREG-1433 to the llope Creek Technical Specifications. She new IID 3.0.5 would state the follwing:

"Egaipment remcued fmm service or declared inoperable to comply with AcrIONS may be returned to service under administrative contml solely to perform testire required to demonstrate its OPERABIITrY or the OPERABIIITY of other equipment. This is an exception to IID 3.0.2 for the system returned to service under administrative contml to perform the testing required to demonstrate OPERABIIlTY."

Incorporate Bases for IID 3.0.5 which are similar to the IUROG-1433 Bases. 'Ihe new Bases would state the follwirg:

Specification 3.0.5 establishes the allwance for restorirg equipnent to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to 100 3.0.2 (e.g., to not comply with the epplicable Required Action (s)) to allw the perfomance of testing required to restore and denonstrate:

a.

3he OPERABILITY of the egaipment being Inturned to service; or b.

The OPERABIITTY of other equipment.

She administrative controls ensure the tire the equipment is retumed to service in conflict with the requirements of the ACTIGE is limited to the tire absolutely necessary to perfom the testing required to restore and demonstrate the OPERABIIJrY of the equipaent. This Specification does not provide tire to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABIIITY of the equipment being returned to service is reopeniIg a containment isolation valve that has been closed to cuply with Required Actions and must be reopened to perform the testirg required to restore and demonstrate OPERABIIITY.

Page 1 of 2

'* Attachment 3 NLR-N93161 Description of Revisions to Hope Creek LCR 92-10 An exampla of demnstmtire the OPERABIII1Y of other equip:ent is taking i

an inoperable channel or trip system out of the trippcd condition to prevent the trip function frun occurrirg during the performance of testiry requind to restore OPERABIIM on another channel in the other trip system. A similar example of demonstratire the OPERABIIIIY of other equipment is takiry an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the perfomance of testirq required to restore and denonstrate OPERABIl m on another channel in the same trip system."

IID 3.0.5 is applicable to all Ibchnical Specifications; however, the intent of IID 3.0.5 is not to super de more specific guidance containcd within any irdividual specification.

II.

OWGS TO MIE IEASON IOR VIE PIOPOSED OWGE P

Replace section II.C of Attachment 1 to NIR-N92187 with the following:

C.

Specification 3.0.5 PSE&G believes that it is not the intent of IID 3.0.2 that conformance to the action requirements for equipment removed frun service or declared inoperable preclude the performance of surveillance testirg to demonstrate the operability of that or other equipment. Therefore, the new IID 3.0.5 ard its associated Bases are being propcmi.

III.,0WEES TO MIE JLUPIFICATIQ4 FOR MIE PROTOSED GWJGES Replace Section III.C of Attachnent 1 to NIR-N92187 with the followirg:

C.

Specification 3.0.S PSE&G believes that adopting the propd IID 3.0.5 and the associated Bases maintains conpliance with the intent of IID 3.0.2.

IV.

SIGIIFICANT HAZA1HE OJNSIDERATIOT EVAILIATIOi r

The basis ard conclusions of the significant hazartis consideration evaluation contained in Attachment 1 of our original license amendment application (NIR-N92187) are unaffected by the charges contained in this revision.

V.

COKIIEIGE

'Ihe conclusions contained in Attachment 1 of our original license amendment application (NLR-N92187) are unaffected by the changes contained in this revision.

VI.

OWGS TO TEONICAL SPECIFICATIOT PAGFS The changes to the Bases for Specification 3.0.2 on Page B 3/4 0-2 are retracted and a new Specification 3.0.5 is added to Page 3/4 0-1 alorg with its associated Bases on Page B 3/4 0-3.

Page 2 of 2

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