ML20033H035

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Proposed Tech Specs Re APRM Scram Trip Setting & APRM Rod Block Trip Setting
ML20033H035
Person / Time
Site: Pilgrim
Issue date: 04/02/1990
From:
BOSTON EDISON CO.
To:
Shared Package
ML20033H034 List:
References
NUDOCS 9004160222
Download: ML20033H035 (17)
v • d • e


Text

.

Attachment B to BECo 90-48 Amended Technical Snecification Paaes The proposed change amends the PNPS Technical Specifications with the attached pages as follows:

Remove Pact Insert Paae 7

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8 8a 8a 26 26 54 54 55a 55a 71 71 k

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9004160222 900402 l

PDR ADOCK 0500 j5, P

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1.1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING D.

Whenever the reactor is in the In the event of operation with a cold shutdown condition with maximum fraction of limiting power irradiated fuel in the reactor density (MFLPD) greater than the vessel, the water level shall not fraction of rated power (FRP), the be less than 12 in, above the top setting shall be modified as follows:

of the normal active fuel zone.

~

~

FRP S 1 (0.58H + 62%)

MFLPD 2 Loco

Where, FRP =

fraction of rated thermal power (1998 MHt)

MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 KH/ft for all fuel.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

For no combination of loop recirculation flow rate and core thermal power shall the APRM flux scram

, trip setting be allowed to exceed 120%

of rated thermal power.

b. APRM Flux Scram Trio Settina (Refuel or Start and Hot Standby Mode)

When the reactor mode switch is in the REFUEL or STARTUP position, the APRM scram shall be set at less than or equal to 15% of rated power.

I

c. IRM l

The IRM flux scram setting shall be 1120/125 of scale.

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r Amendment No. 75, 42, 72, 105 7

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1.1 S&((Iy LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING B. APRM Rod Block Trio Settina 1.

ARM Rod Block Trio Settina (Run 162d21 When the mode switch is in the run position, the APRM rod block trip setting shall be:

SRB 1 0.58H + 50% 2 Loop

Where, SRB "

Rod block setting in percent of rated thermal power (1998 MHt)

Percent of drive flow i

H required to produce a rated core flow of 69 M1b/hr.

In the event of operating with a maximum fraction limiting power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows:

~

~

FRP S 1 (0.5BN + 50%)

MFLPD 2 Loop i

Hhere, FRP =

fraction of rated thermal power l

MFLPD - maximum fraction of limiting power density where the limiting power density is 13.4 KH/ft for all fuel.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case i

the actual operating value will be used.

e Amendment No. 15, 42, 72, 105 8

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).1 SAFETY LIMIT 2.1 LIMITING SAFETY SYSTEM SETTING 2.

APRM Rod Block Trio Settina (Refuel and Startuo Modes)-

When the reactor mode switch is in the refuel or startup positions, the APRM rod block trip setting shall be set at less than or equal to 13% of rated power, but always l

1ess than the APRM flux scram trip setting in Specification 2.1.A.l.b.

C.

Reactor low water level scram i

setting shall be 1 9 in, on level instruments.

D.

Turbine stop valve closure scram settings shall be i 10 percent valve closure, t

E.

Turbine control valve fast closure setting shall be 1 150 psig control oil pressure at i

acceleration relay.

F.

Condenser low vacuum scram setting shall be 1 23 in. Hg. Vacuum.

G.

Main steam isolation scram setting shall be 1 10 percent valve closure.

H.

Main steam isolation on main steam line low pressure at inlet to turbine valves.

Pressure setting shall be'l 880 psig.

I.

Reactor low-low water level l

initiation of CSCS systems setting shall be at or above -49 in.

l indicated level.

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l 1

- Amendment No. d2

.8a t

i 3.1 LIMITING CONDITION FOR OPERATION 4.1 SURVEILLANCE REOUIREMENTS 3.1 REACTOR PROTECTION SYSTEM REACTOR PROTECTION SYSTEM i

bpolicability:

Aeolicability:

Applies to the instrumentation Applies to the survoillance of the and associated devices which instrumentation and associated initiate a reactor scram.

devices which initiate reactor l

scram.

Qbiettive:

Obiet.eive:

To assure the operability of the To specify the type and frequency f

reactor protection system, of surveillance to be applied to the protection instrumentation.

Soecification:

Specification:

l A.

The setpoints, minimum number of A.

Instrumentation systems shall trip systems, and minimum number be functionally tested and of instrument channels that must calibrated as indicated in be operable for each position of Tables 4.1.1 and 4.1.2 the reactor mode switch shall be respectively, as given in Tcble 3.1.1.

The system response times from the B.

Verify the maximum fraction of opening of the sensor contact up limiting power density is less to and including the opening of than or equal to the fraction the trip actuator contacts shall of rated power once within 12 not exceed 50 milli-seconds.

hours after thermal power is greater than or equal to 25%

B.

The maximum fraction of limiting of rated thermal power and power density (MFLPD) shall be every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, less than or equal to the fraction of rated power (FRP) when thermal power is greater than or equal to 25% of rated thermal power.

C.

If MFLPD is greater than FRP, adjust the APRM high flux setpoints to the relationships given in Specification 2.1. A.1.a and 2.1.B.1 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D.

If the required actions and associated completion times of Specification 3.1.C cannot be met, reduce thermal power to less than 25% of rated thermal power l

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

AmendmentNo.//,

26

FNPS f

TABLE 3.2.C-1 INSTRtMENTATION THAT INITIATES CONTROL ROD BLOCKS Minimum Operable Channels Required Trio Function per Trio Function Operational Conditions Action APRM Upscale (Flow Biased) 4 Run (1)

APRM Upscale (Setdown) 4 Startup/ Refuel (1)

AFRM Inoperative 4

Run/Starup/ Refuel (1)

APRM Downscale 4

Run-(1)

Rod Block Monitor (Flow Biased) 2 Run, except trip is bypassed when (1) (2) reactor power is i 30%

Rod Block Monitor Inopera*ive 2

Run, except trip is bypassed when (1) (2) reactor power is i 30%

~

Rod Block Monitor Downscale 2

Run, encept trip is bypassed when (1) (2) reactor power is i 30%

IRM Downscale 6

Startup/ Refuel, encept trip is bypassed (1) when IRM is on its lowest range IRM Detector not in Startup Position 6

Startup/ Refuel, trip is bypassed (1) when mode switch is placed in Run IR11 Upscale 6

Startup/ Refuel (1)-

IRM Inoperative 6

Startup/ Refuel (1)

SRM Detector not in Startup Position 3

Startup/ Refuel, except trip is bypassed (1) when SRM count rate is 1100 counts /

second or IRMs on Range 3 or above. (4)

SRM Downscale 3

Startup/ Refuel, encept trip is bypassed (1) when IRMs on Range 3 or above. (4; SRM Upscale 3

Startup/ Refuel, except trip is bypassed (1) when the IRM range switches are on Range 8 or above. (4)

SRM Inoperative 3

Startup/ Refuel, except trip is (1) bypassed when the IRM range switches are on Range 8 or above. (4)

Scram Discharge Instrument Volume Water Level - High 2

Run/Startup/ Refuel (3)

Scram Discharge Instrument Volume - Scram Trip Bypassed 1

Run/Startup/ Refuel (3)

Recirculation Flow Converter - Upscale 2

Run (1)

Recirculation Flow Converter - Inoperative 2

Run (1)

Recirculation Flow Con <erter - Comparator Mismatch 2

Run (1)

Amendment No.15, Z7, 4Z, E?. 7Z, 72,110, S4

h, l

PNPS TABLE 3.2.C-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS Trio Function Trio Setooint APRM Upscale See $pecification 2.1.5 l

APRM Inoperative Not Applicable APRM Downscale 1.2.5 Indicated on Scale Rod Block Monitor 1 (0.65 W + 42%)

FRP (1)

(Flow Biased)

MFLPD Rod Block Monitor Inoperative Not Applicable Rod Block Monitor Downscale 15/125 of Full Scale IRM Downscale 15/125 of Full Scale IRM Detector not in Not Applicable Startup Position IRM Upscale i 108/125 of Full Scale IRM Inoperative Not Applicable SRM Detector not.in Not Applicable Startup Position SRM Downscale 1 3 counts /second 5

SRM Upscale i 10 counts /second SRM Inoperative Not Applicable

. Scram Discharge Instrument Volume i 18 gallons

. Water Level - High Scram Discharge Instrument Volume -

Not Applicable Scram Trip Bypassed Recirceslation Flow Converter - Upscale i 120/125 of Full Scale' Recirculation Flow Converter - Inoperative Not Applicable Recirculation Flow Converter - Comparator -

Mismatch 110% Flow Deviation for > 80% Rated Power, and

- 115% Flow Deviation for i 80% Rated Power (1) W is-the percent of drive flow required to produce a rated core flow of 69 M1b/hr.

Trip level setting is in percent of design power (1998 IWt). For flows of '00% or greater, the roj block monitor maximum trip level setting shall be 107% power.

Amendment No. 42, 118, 55a

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'3.2 BA ES (Cont'd) l The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the Safety Limit MCPR.

The trip logic for this function is 1 out of n:

e.g., any trip on one of six APRM's, eight IRM's, or four SRM's will result in a rod block.

The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.

The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or calibration. This time period is only 3% of the operating time in a month and does not significantly increase r

the risk of preventing an inadvertent control rod withdrawal.

The APRM rod block function is flow biased in the run mode and prevents a significant reduction in MCPR, especially during operation at reduced flow.

In the startup and refuel modes, the APRM rod block function is setdown below the APRM flux scram trip, as specified in Specification 2.1.B.2.

The APRM provides gross core protection; i.e., limits the i

gross core power increase from withdrawal of control rods in the normal withdrawal sequence.

The trips are set so that MCPR is maintained greater than the Safety Limit MCPR.

The RBM rod block function provides local protection of the core, for a single rod withdrawal error from a limiting control rod pattern.

The IRM rod block function provides local as well as gross core protection.

The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level.

A downscale indication on an APRM or.IRM is an indication the instrument has failed or the instrument is not sensitive enough.

In either case the instrument will not respond to changes in control rod motion and thus, control rod motion is prevented. The downscale trips are as shown in Table 3.2.C.

The flow comparator and scram discharge volume high level components have only one logic channel and are not required for safety.

The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.

For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapidly

[

enough to allow either core spray or LPCI to operate in time.

The automatic pressure relief function is provided as a backup to the j

Amendment No. 75. 42, 770, 71

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Attachment C to BECo 90-48 i

Marked-un Paaes from Current Technical Snecifications l

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D.

Whenever the reactor is in the 1n the event of operation with a cold shutdown condition with maximum fraction of limiting power irradiated fuel in the reactor density (MFLPD) greater than the vessel, the water level shall not fraction of rated power (FRP), the be less than 12 in, above the top setting.shall be modified as of the normal active fuel zone, follows:

' FRP '

S 1 (0.5BH + 62%)

MFLPD 2_ Loop

Where, FRP = fraction of rated thermal power (1998 MWt)

MFLPD - maximum fraction of limiting power density where the limiting power density is 13.4 KH/ft for all fuel.

l The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

For no combination of loop recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power.

b. APRM Flux Scram' Trio Settina

_(Refuel or Start and Hot Standbv Modit),'-

When the reactor mode switch is in the REFUEL or STARTUP position, the APRM 3

scram shall be set at less than or equal to 15% of 4

rated power.

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The IRM flux scram setting shall be 1120/125 of scale.

B.

APRM Rod Block Trio'Settina

.1.Mffl Rwl Wek TNp bettw (Rum t%%\\

-g7he APRM rod block tripisettiIig

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shall be:

SRB 1 0.58H + 50% 2 Loop

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U_11MIM.iM[lL5152tM..Stilha hhere.

See. Rod block setting in perctht of rated therma)

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poor (1996 MWt)

N Percent of drive flow w

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,y M1b/hr.

IdlWl'/J, ALM M M r#WW5k In the event of cperating with a makimum fraction limiting power density (MFLPD) greater than the

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y fraction of rated power (FRP), the WJ NRJ11 &

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N( %

  • tag o/M 6 Int S 1 (0.$tH + 50%)

MFLPD 2_1cter a& ce& K cfwn n.

wf N Ib '/D } & ys+ v 4 A., bd Where.

FRP. fraction of rated thermal j

d w p b n TJ u -t h t9t'RJ11 V***'

MFLPD. maximum fraction of l

gb.Wih Mu.

f limiting power density where the limiting power

/p%M A /. M. /. 6.

d sit is 13.4 KH/ft for

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j The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

p A

C.

Reactor low water level scram setting shall be 19 in, on level instruments.

D.

Turbine stop valve closure scram settings shall be 1 10 percent valve closure.

E.

Turbine control valve fast closure settiag shall be 1 150 psig control oil pres;ure at acceleration relay.

F.

Condenser low vacuum scram setting shall be 2 23 in. Hg. vacuum.

G.

Main steam isolation scram setting shall be 1 10 percent valve WO3 fJo, /

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1.'1 S ATEM LPffT 2.1 LDt1 Tiles RArtTT ntTDI SETTDG t,

R.

Wata atena Leetaties sa mata stoaa line low presours at talat to turbina valves. pressura seat.1as shall be 2 840 pois.

1.

Baatter low-lew water level tattiattaa of CSC8 erstems set-

t. Lag shall be at er above -49 la.

tadicated level.

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s Sa Amendment No. 42

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I i.tIMITIM Co@1TIDH POR CFDATION 4.1 57Evrrt.Luct trtT!,WEFTI o

a.1 an_mR PRettCT10N STsm n'APTOR PROTECTION FTSTDI Aeolicabilityt Aeottesbilit?t Appitas to the instruneatation Applias to the survet11ance of and aseeciated devitas whit.h the instrumentation and associ-ated.ievises whis.h initiate re-Laitiata a reactet scram.

aster ot:as.

Ob$ettivet

.9 hit 111vt.8 To assure the operability of the To opstify the type and frequency of surveillanca to be applied to reacter protection system.

the protection instavaantaties.

BP*tifA4811FB8 Seecificatient A.

Eastransatatten systeam shalf

4. The satpetats

=4m4== moaber of be functionally tastad M.t trip systems, and minimum number calibrated as indicated in of instr. ament e.hennels that sust Tables 4.1.1 and 4.1.2 re-be operabia for each position of the reactor mode evitch shall be spectively, as given in Table 3.1.1.

The r

3.

Daily durias rateter power syatse reoponse tinas frpa the eparaties, the manimue frac-opening of the seascr contact up to and including the opening of tien e M *he4*g power p ry shall w t d

e scram e

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the trip actuator contacts shall and AtaM settings met estead 50 milli-seconds.

given by og tions in Spacifica 'en 2.1. A.1 and 2.1.3 shall be calculatad it v==4==

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P98P5 TABLE 3.2.C-1

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IMSTRUMENTATI rm-==_ q p.

Minimum Operable Channels Required Il P_.LU"Sli9n pfr irip Tun lion Optratignp M onditions Acting i

AF Upscale (Flow Biased) 4 Re,S r^

"'"o M i^o,T;rti.v>' & h )

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C/5";t J_ W

@1 APRM Downscal, a-Red Block Monitor (Flow Biased) 2 Ron ewcept trip is bypassed =Aen (1) (2) reactor pe=er is i 301 Rod Glock Monitor Inoperative 2

Ron escept trir-is bypassed =Aen (1) (2) reactor pe==r is i 30%

Rod Block Monitor Downscale 2

Ron, e= cept t;ip is bypassed Aen (1) (2) reactor pow c is i 301 IRM Downscale 6

Star N Refuel. e* cept trip is bypassed (1) e IRM is on its lowest range IRM Detector not in Startup Posit 4ye 6

Startop#efwel, trip is bypassed (1)

=Aen sede switch is placed in Ron IRM Upscale 6

Startoonefwel (1)

IRM Inoperative 6

StartspMefuel (1)

SRM Detector not in Startup Position 3

Startsp#efuel, encept trip is bypassed (1)

=Aen SRM count rate is 2100 counts /second or IRMs on Range 3 or above (4)

SRM Downscale 3

Startup/ Refuel, escept trip is bypassed (1) when IRMs en Range 3 or abere (4)

SRM Upscale 3

Startup/ Refuel e= cept trip is bypassed (1)

=Aen the IRN range switches are on Range 8 er above (4)

SEM Inoperative 3

Startup/Refwel, e= cept trip is (1) bypassed when the IRM range switches are on Range 8 er above (4)

Scran Discharge Instrument Volume Water Level - High 2

Ran/Startup # efuel (3)

Scram Discharge Instrement Volume - Scram Trip Bypassed 1

Ren/Startoonefuel (3)

Recirculation Flow Converter - Upscale 2

Run (1)

Rerirculation Flow Converter - Ineperative 2

Run (1)

Reci4v14 tion Flow Converter - Cogarator Mismatch 2

  1. wn (1)

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PNPS TABLE 3.2.C-2 (pwT_0t_ ROD _BLKK_INSTRUMEMTATIO4J ETS IwTS TR Trip _fvoglion Ir_ip_5e_tppini APRM Upscale,

-i #?.5" Y IT ~_T(

{!){

tru s. %

.= = _e APRM Inoperative Not Applicable APRM Downscale 1 2.5 Indicated en Scale Rod Block Monitor 1 (0.65 W + 42%) ~ F*P ~

(1)

(Flow Biased)

_MF LPD, Rod Ctock Monitor Inoperative Not Applicable Rod 81eck Monitor Downscale 1 5/125 of Fell Scale IRM Downscale 2 5/125 of Fall Scale IRM Detector not in Not Applicable Startup Position IRM Upscale i 10L.25 of Fall Scale IRM Inoperative Not Applicable SRM Detector not in Not Applicable Startup Position SRM Downscale 13 counts /second 5 counts /second SRM Upscale i 10 SRM Inopers.tive Not Applicable Scram Discharge Instrument Volume i 18 gallons Weier Level - High Scram Discharge Instrument Volume -

Not Applicable Scram Trip Bypassed Recireviation Flow 6erter - Upscale i 12D/125 of Fell Scale siectreviation Flow Converter - Inoperative Not Appilcable Recircolation Flow Converter - Comparator i 10E Flow Deviation for > SOE Rated Power and Mismatch i 15E Flow Deviation fe" 1801 Rated Power (1) W is the percent of drive flow required to produce a rated core flew of 69 Mib/hr.

Trip level setting is in percent of design power (1996 Nt). Por flows of 1D0E or greater, the rod block monitor manimum trip level setting shall be 1071 power.

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c 3.2 EMi$ (Cont'd) f The control rod block functions are provided to prevent excessive control rod withdrawal so that HCPR does not decrease to the $4fety o

Limit MCPR.

The trip logic for this function is 1 out of n:

e.g., any trip on one of sin APRH's, eight IRH's, or four SRH's will result in a rod block.

The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.

The minimum instrument channel requirements for the RBH may be reduced by one for maintenance, testing, or calibration.

This time period is only Y4 of the operating time in a month and does not significantly increase the risk of preventing an inadvertent control rod withdrawal.

A ti.e > M TheAPRMrodblockfunctionisflowbiased[tionatreducedflow, and prevents a signifi ant reduction in HCPR, especially during opera he APRH provides gross core protection; i.e., limits the gross core power increase from withdrawa) of control rods in the normal withdrawal sequence. The trips are set 50 that MCPR is maintained greater than the Safety Limit MCPR.

The RBM rod block function provides local protection of the core, for a single rod withdrawal error from a limiting control rod pattern.

The IRH rod block function provides local as we11 as gross core protection. The scaling arran ement is such that trip setting is less than a factor of 10 above the ndicated level.

A downscale indication on an APRM or IRH is an indication the instrument has failed or the instrument is not sensitive enough.

In either case i

the instrument will not respond to changes in control rod motion and thus, control rod motion is prevented. The downscale trips are as shown in Table 3.2.C 2.

}

The flow comparator and scram discharge volume high level components have only ont logic channel and are not required for safety.

The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.

For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapidly enough to allow either core spray or LPCI to operate in time. The automatic pressure relief function-is provided as a backup to the f

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