ML20128F182

Proposed Tech Specs,Revising TS 3.4.1.1, Recirculation Sys Recirculation Loops, to Delete Existing Action a.1.e to Incorporate Affected Requirements Into New Actions a.2,a.3 & a.4 to Reduce APRM Setpoints

ML20128F182
Person / Time
Site:	Hope Creek
Issue date:	02/02/1993
From:	Public Service Enterprise Group
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ML20128F180	List: ML20128F175 ML20128F182
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NUDOCS 9302110287
Download: ML20128F182 (10)

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ATTACllMENT 2 TECIINICAL SPECIFICATION PAGES WITil PEN AND INK CHANGES LICENSE AMENDNENT APPLICATION 92-10, NLR-N92187 INSTRUMENTATION-REQUIRFMENTS FOR SINGLE IDOP ' OPERATIONS FACILITY OPERATING-LICENSE NPF-57 '

HOPE CREEK GENERATING STATION i

DOCKET NO. 50-354 l

1 The following Technical Specifications have l

been revised to reflect the proposed changest T_ochnical SpecificatiQD Paae

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2.2.1, Tablo 2.2.1-1 2-4 3.2.2-3/4 2-2 3/4,1.1 3/4'4-1

~3/4 4-2 3/4 4-2a-Bases Specification 3.0.2 B 3/4-0-2 q

Basos B 3/4 4-1 B 3/4'4-1.

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t 3

.a 5

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TABLE 2.2.1-1 2

REACTOR PROTECTION SYSTEN INSTRUMENTATION SETPOINTS Q'

ALLOWA8LE

'y FUNCTIONAL UNIT-TRIP SETPOINT VALUES n

1.

Ini.ermediate Range Manitor, Neutron Flux-High

$ 120/125 divisions

$ 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

$ 20% of RATED THEIMAL PohER b.

Flow 81ased Simulated Thermal Power-Upscale

1) Flow Blased

-< 0.66(w-aw)+51%** with

- with a maximum of

( 0.66(w-aw)+54%"*

a maximum of

2) High Flow Clamped

$ 113.5% of RATED

$ 115.5%'of RATED.

THEINAL POWER THERMAL POWER 4p c.

Fixed Neutron Flux-Upscale i 118% of RATED THERMAL POWER 1120% of RATED

~*

THERMAL POWER

- d.

Inoperative NA NA

3.. Reactor Vessel Steam Dame 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 1 8% closed 5 12% closed

• See Bases Figure 5'3/4 3-1.-

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

~

~

g.l Aw is defined as-the' difference in indicated drive flow (in percent of. drive flow which produces rated

• ?

core flow) between two loon and sinale loan aneration at the same core flow. ow = 0 for two' recirculation L

loop operation.: aw =["Tgrbe depreine4 fat a Ider dat/lfsr single recirculation 1000 operation.

.g4 A.

E 9%

w N

POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTO LIMITING CONDITION FOR OPERATION 3.2.2 The aPRM flow biased simulated thermal power upscale scram trip setpoint (S) and flow biased neutron flux upsca'e control rod block trip setpoint (SRB) shall be established according to the following relationships:

TRIP 5tiPOINT ALLOWABLE VALUE 5 < (0.66(w-aw)" + 51%)T S < (0.66(w-aw)" + 54%)T S f 1 (0.66(w-ow)" + 42%)T S 5 5- (0.66(w-aw)" + 45%)T p

R where:

S and Skg are ir, percent of RATED THLRMAL POWER, W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 100 million lbs/hr, T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER (FRTP) divided by the CORE MAXIMUM FRACTION OF LIMITING POWlR DENSITY (CMFLPD).

T is applied only if les 4han or equal to 1.0.

APPLICABILITY:

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

ACTION:

With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased neut.'on flux-upscale control rod block trip setpoint less-conservative than the value shown in the Allowable Value column for S or S as abovedetermined,initiatecorrectiveactionwithin15minutesandadjust$0,nd/

a or S to be consistent with the Trip Setpoint values

• within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or reduce THERML POWER to less than 25% of RATED THERMAL POWER within the SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP.and the CMFLPD shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and flow biased reutron flux upscale control rod block trip setpoints verified to be within the above limits or_ adjusted, as required:

a.

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

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b.

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 lert 15% of RATEL 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 c.

with CMFLPD greater than or equal to FRTP.

d.

The provisions of Specification 4.0.4 are not applicable.

"With CMFLPD greater than the FRTP, ratfier than adjusting the APRM.setpoints, the APRM gain may be adjust.ed siuch that the APRM readings are greater than or equal.

to 100% times CMFLPD provided that the adjusted APRM_ reading does not exceed 100% of. RATED THERMAL P0FER and a notice of adjustment is posted on the reactor control panel._ _ __.

"The Average Power Range Monitor Scram function varies as a function of recircu-lation loop drive flow (w).

Aw is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop andsingleloopoperat/".nn at ca ma ma n nw-Aw = 0'for two recirculation loop operation.' aw =l To /deterptied at @ter da1#" for single recirculation loop operation.-

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HOPE CREEK g yo 3/4 2-2 Amendment No. 34

3/4L4 4EAC'OR CCOLANT SYSTEM _

3/4.4.1 RECIRCULAT!CN-SYSTEM RECTECULATION LOOP 3 L*MI'!NG 00N0!T!0N FOR OPERATION 3.4.1.1 Two reactor coolant system recircultc' ~ ' cops shall'ba in operation with:

Total core flow greater than or equat to_45% of rated core flow, s.

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or-b.

THERMAL POWER less-than or equal-to the limit specified'in Figure 3.4.1.1-1.

APPLICA8!LITY: OPERATIONAL CON 0!TIONS la and 2*.

ACTION:

With one reactor coolant systeerrWCTrculation loop 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:

a) mee the recirculstion flow control system in the Local A#1ual mode, and b).

Rv1uce THERMAL POWER to 1705 of RATED THERMAL POWER, and

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c)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety.

Limit by 0.01 to 1.08 per Specification 2.1.2, and I

d) -Reduce the Maximus Average Planer Linear Heat Generation

"*** ("""'"'")

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' ' ' ' ' ' ** * $ ** ' t h' * *'

DELE TED y recircuiation ioop u.it p.c s"p.cification s.'2.1, and g- -

e)

' Re a the-erage P r Range itor (APRM) 5 as and Rod 8 ck Mon or Trip tpoints a Allowable va es to thos itca for si le rectre ation loop op ation per g) 38*/o Specif ations

.2.1,-3.2.2 nd J.3.6, an

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f)

Lielt the speed of the opefM,ing recirculation pump to b[3g\\

6

),,,,than or equal to 905 of rated pump speed, and' Y.['Y$ y @of

^

4%

Q g)

Perfem nume111ance requirement 4.4.1.1.2 if TNERMAL POWER.

is GSFef RATED THERMAL POWER recirculation loop A

flow 'n the operating loop 1ts 1 505 of rated loop flow, b

{

gThe provisions of Specification 3.0.4 are not appitcable, g,

Q Otherwise_be in at least HOT'5 HUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• 5ee Special Test Exception 3.10.4

""Ini tial lues. Final val s to be determined duri Startus Testing bas up'on threshold THE POWER and recirculati

. loop flow which wil swo the cold water ce the vessel bottom preventing stratif 1on.

HOPE CREEK 3/4 4-1 lwendment No. 15

'I

-l ACTIONS #2; 3.

AND 4 TO BE 7HSERTED AS IllDICATED 'ONT PAGE 3/4 4 -1 : -

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 I

applicable for single recirculation loop operation per Specifications'2.2.1 and 3.2.2; otherwise, with tha Trip Setpoints and Allowable 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 and within the following 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 Allowable values ofLthe affected channels to those applicable for single recirculation loop operation por 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 Allowable values toLthose applicable:for single recirculation loop operation per Specifications 3.2.2 and 3.3.6; otherwise, with the Trip Setpoints and Allowable Values associated with one trip function-not reduced to-those applicable for single recirculation loop operation, place at!1 east one affected channel in the

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tripped condition and within the fo1}owing 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 Allowable Values of'the affected channels-to those applicable'for single recirculation loop operation per Specifications 3.2.2 and.3.3.6.

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 single recirculation loop operation per Specification'3.3.6; otherwise, with the Trip-Setpoints and Allowable values associated with one trip function not reduced to those applicable for single recirculation loop operation, place at least one affected channel =in the.trinped condition and-within the following 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 Allowable Values of the remaining channels to those' applicable for single recirculation loop operation:per Specification 3.3.6.-

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ata.: :: :::. W !.$*?u 64v!:..as:! 4?:.:3!u!N*i

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etet:e :::' set t s.em ecG:.*at':n 'socs 'n ::e st :n, i

-rec' ate'j init' ate act'sn to.ecuce TaER.wAL DOWER to 'ess t a -: -

ecua to t*e 1 %it soecified in Figure 3.4.1.1-1 within 2 6:

Lsa:

'e t'ste measures to clace tne unit in at least STARTUD.i. - i h:ves-t amo a ~07 Snu!DOWN witnin tee next 6 nours with one or two reactor coolant system recirculation to c.

tion and total core flow less than 45% but greater than

y s - ~

!/0 '/o "

• s rated core flow ano THERMAL POWER greater tnan the limi spec'*ie:

4-Figure 3.4.1.1 1:

1.

Determine the APRM and LPRM" noise levels ($urveillance

]

4.4.1.1.4):-

m 4)

At least once car 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and 1

o)

Within 30 minutes after the completion of a THERMAt, DC' wit increase of at least 5% of RATED. THERMAL POWER.

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2.

With the APRM or LPRM* neutron flux' noise levels greater t ac three times their estaolisned baseline noise levels, 'tnin.'5.

minutes initiate corrective action to restore the noise *4 vets' i

to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by increasing sce.

flow to greater than 45% of rated core flow or by reducing imE'4 *'

mat. POWER to less than or equal to the liai". specified-in Fig-ure 3.4.1.1 1.

lyo $

With one or two reactor coolant system recy ation locos'in.oce sti:-

i d.

and total < core flow less than or equal to and THERNAL POWER g eater than the limit specified in Figure 3.4.1.:,

, within 15 minutes -'tiste i

cortcetive action ts reduce THERMAL POWER to less than or equal :

the li i specified.in Figure 3.4.1.1+1= or increase cure! flow ::

40 Tel than within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ener 4,4.1.1.1.With ine reactor coolant system recirculation Icop not in operati

a; 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:

Reheter THERMAL POWER'is j 70% of RATED. THERMAL POWER, and a.

The ref;irculation flow control systes is'in the Lecal Manual moce, b.

and The" speed of the operating recirculation rump is less than or equal c.

to 905 of rated pues speed, and yo g o.

Core flow-is greater than when THERMAL' POWER % greater'than the limit specified in-Figure 3.4.1.1-1.

" Detector levels A and C of one LPRM string per core. octant plus detectors.'A and C of one LPRM string in the center of the core should be monitored.

e einit values.

Final v ues to be determined ring St'artup Tes g (core-fl with both recire tion pumos at a mini puso speed).

HOPE CREEK 3/4 4-2 Amendment No. 3 4

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react 0R COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 414.1.1.2-With one reactor coolant system recirculation loop not in operation, witnin no more than'15 minutes prior to either THERMAL POWER increase or *ecir<-

culation 1o00 flow increase, verify that the following differential temocrature-requirements are met if THERMAL POWER is <

of RATED THERMAL POWER r the recirculation loop flow in the operating re ulation loop is < 50 ofLrated-loop flow:

y

< 145'F between reactor vessel steam space coolant and bottom need a.

Urain line coolant, and b.

< $0*F between the reactor coolant within the loop not in operation 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 loop.

The oifferential temperature requirements or $pecifications 4.4.1.1.2b and 4.4.1.1.2c do not apply wnen the loop not-in operation is isolated from the reactor pressure vessel.

4.4.1.1.3 Each pump MG set scoop tube mechanical and electrical stop shall be demonstrated OPERA 8LE with overspeed setpoints less.than or equal to 109% and 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 within the regions for which monitoring is required (Specification 3.4.1.1. ACTION c) 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 baselining has previously been performed in the region since the.last refueling.

outage.

4 l

" Detector levels A and C of one LPRM string per core. octant plus ~ detectors A

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

M

1. !nitial va es.

Final values be determined duri tartup Testing ba d upon the reshold THERMAL R and recirculatio oop flow which wi L

, sweep e cold water fr

. e vessel bottom hea reventing strati ation.

HOPE CREEK 3/4 4-2a Amendment.No. 15

3/4.0 APPLICABILITY BASES (Con't) time limits of the ACTION requirements would apoly from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Specificatinn 3.0.2 establishes that noncompliance with a specification exists wnen tne requirements of the limiting Condition for Operation are not met and 6

the associated ACTION reouirements have not been implemented within the g

specified time interval.

The purpose of this specification is to clarify that

• g (1) implementation of the ACTION requirements within the specified time

% \\e".(

interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored Within the time interval speifiedintheassociatedACTIONrequirements.

/

y 51ecification3.0.3establishestheshutdownACTIONrequirementsthatmustbe implemented when a Limiting Condition for Operation is not met and the condi-tion is not specifically addressed by the associated ACTION requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown CONDITION when plant' operation ca'nnot be maintained within the limits for safe operation defined by the Limiting Conditions for-

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Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

One hour is allowed to prepare for an orderly shutdown before initiating a. change in plant operation.

This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

The tim limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly inanner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum rcquired equipment is OPERABLE.

This reduces thermal stresses-on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this-specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed.the shutdown may be terminated.

The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation.

Therefore, the shutdown may be terminated if the ACTION require-ments have been met or the time limits of the ACTION requirements have not-expired, thus providing an allowance for the completion of the required-actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation.

If the piant is in a lower CONDITION of operation when a shutdown is required, the time licit for reaching the next lower CONDITION of operation applies.

However, if s *,

HOPE CREEK B 3/4 0-2 Amendment No.

19.,

7--

.n

(:

l NEW PARAGRAPH TO BE INSERTED AS INDICATED ON PAGE B 3/4 0-2 It is not the intent of: Specification 3.0.2 that conformance to

- the-ACTION ' requirements preclude the performance of surveillance testing to demonstrate the OPERABILITY of a component which:is being returned to service.

For example, the ACTION statement for a malfunctioning instrument may require theLinstrument to be

~

placed in the. tripped condition.

After the-instrument is repaired, it is expected to be OPERABLE.

prior to-returning the' instrument to service and exiting the Limiting condition-for Operation, applicable Surveillance tests are performed-to-demonstrate that the instrument has, in fact, been restored to OPERABLE status.

In order'to conduct the required surveillance tests, the instrument may need to be taken out of_the tripped-condition.

Insofar as the instrument has been. repaired and is expected to be OPERABLE, it is permissible to take it~out.of the tripped condition to conduct surveillance testing since'this-action is nece"sary in order to demonstrate OPERABILITY.

It should be stressed however, that-the subject instrument remains administratively inoperable and all applicable action requirements'and time constraints' remain in effect, uninterrupted, until all applicable surveillance requirements are met.

3

3/4.4 REACTOR COOLANT SYSTEM BASES 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 scram and control rod block setpoints are adjusted as noted in Tables 2.2.1-1 and 3.3.6-2, respectively.

in Specification 3.2,1, and MCPR operating limits are aMAPLHGR limits are de usted per Specification 3/4.2.3.

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Additionally, surveillance on the pump speed of i e operating recirculation loop is imposed to exclude the possibility of exces The surveillance on differential temperatures below core internals vibrat ho

' THERMAL POWER or 50 W rated recirculation loop flow is to mitigate the un e thermal stress on vessel no n les, recirculating pump and vessel bottom head during the extended 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-accident, increase the blowdown area and reduce the capability of reflooding the core; 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 prescribed schedule for significant degradation.

Recirculation loop flow mismatch limits are in compliance with the ECCS-LOCA analysis design criteria for two recirculation loop operation. The limits will ensure an adequate core flow coastdown from either recirculation loop fol-lowing a LOIA.

two loop operation, continued operation is permitted in a single recirc loop mode.,

[

In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50*F of each other prior to startup of an idle loop. _The loop temperature must also be within 50*F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles. Sudden equalization of a-temperature difference > 145'F between the reactor vessel bottom head coolant l

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.

The objective of GE BWR plant and fuel design is to provide stable operation with margin over the normal operating domain.

However, at the high power / low flow corner of the' operating domain, a small probability of limit cycle neutron flux oscillations exists depending on combinations of operatir.g 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 levels should be monitored while operating in this region, p

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f l

• Ini values.

Final y es will be determine uring Startup Testing sed n the threshold TH L POWER and recircu ton loop flow which w sweep he cold water from e vessel bottom hea preventino saturation.

HOPE CREEK B 3/4 4-1 Amendment No. 3