ML20046D044

Proposed Tech Specs,Proposing 24 Month Fuel Cycle

ML20046D044
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Site:	Pilgrim
Issue date:	08/09/1993
From:	BOSTON EDISON CO.
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ML20046D042	List: ML20046D041 ML20046D044
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NUDOCS 9308160069
Download: ML20046D044 (15)

Text

PNPS Table 3.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Operable Inst. Modes in Which Function Channels per Trip Function Trip Level Setting Must Be Operable Action (I) -

Trio System (1) Refuel (7) Startup/ Hot Run MinimumlAvail. Standby mg 1 1 Mode Switch in Shutdown X X X A 20

$ 1 1 Manual Scram X X X A

> c-88 IRM Q$ 3 4 High Flux s120/125 of full scale X X (5) A g

3 4 Inoperative X X (5) A OS APRM co$ 2 3 High Flux (15) (17) (17) X A or B E@* 2 3 Inoperative (13) X X(9) X A or B U 2 3 High Flux (15%) sl5% of Design Power X X (16) A or B m-7; 2 2 High Reactor Pressure s1085 psig X(10) X X A 2 2 High Drywell Pressure s2.5 psig X(8) X(8) X A 2 2 Reactor low Water Level 29 In. Indicated Level X X X A SDIV High Water Level: s38 Gallons X(2) X X A l 2 2 East 2 2 West 2 2 Main Condenser low Vacuum =23 In. Hg Vacuum X(3) X(3) X A or C 2 2 Main Steam Line High s5.5X Normal Full Power Radiation Background (18) X X X(18) A or C 4 4 Main Steam Line Isolation Valve Closure s10% Valve Closure X(3)(6) X(3)(6) X(6) A or C 2 2 Turbine Control Valve =150 psig Control Oil Fast Closure Pressure at Acceleration Relay X(4) X(4) X(4) A or D 4 4 Turbine Stop Valve s10% Valve Closure X(4) X(4) X(4) A or D Closure Amendment No. 151 -42,-86 5 -92 1 -117, 133, 147 27

~_

- I 3.1 BASES (Cont'd)  ;

range of applicability of the fuel cladding integrity safety limit. In  :

addition, the isolation valve closure scram anticipates the pressure and  !

flux transients that occur during normal or inadvertent isolation valve closure. With the scrams set at 10 percent of valve closure, neutron flux .

does not increase. j l'

Hiah Reactor Pressure The high reactor pressure scram setting is chosen slightly above the maximum  ;

normal operating pressure to permit normal operation without spurious scram, '

yet provide a wide margin to the ASME Section III allowable reactor coolant i system pressure (1250 psig, see Bases Section 3.6.D).

Hiah Drywell Pressure Instrumentation for the drywell is provided to detect a loss of coolant - l accident and initiate the core standby cooling equipment. A high drywell  !

pressure scram is provided at the same setting as the Core Standby Cooling  :

Systems (CSCS) initiation to minimize the energy that must be accommodated  !

during a loss of coolant accident and to prevent return to criticality. This instrumentation is a backup to the reactor vessel water level 1 instrumentation.

Main Steam Line Hiah Radiation  ;

i High radiation levels in the main steam line tunnel above that due to the ,

normal nitrogen and oxygen radioactivity is an indication of leaking fuel. l A scram is initiated whenever such radiation level exceeds 5.5 times normal background. The purpose of this scram is to reduce the source of such l radiation to the extent necessary to prevent excessive turbine l contamination. Discharge of excessive amounts of-radioactivity to the site  ;

environs is prevented by the air ejector off-gas monitors that cause an: j isolation of the main condenser off-gas line. i Reactor Mode Switch  !

The reactor mode switch actuates or bypasses the various scram functions  ;

appropriate to the particular plant operating status (Reference FSAR Section  !

7.2.3.9).  :

Manual Scram  !

l The manual scram function is active in all modes, thus providing for a l manual means of rapidly inserting control rods during all modes .of reactor '

operation. j

-j Amendment No. 6, 79, 133,-147 39

3.1 BASES (Cont'd)

Scram Discharce Instrument Volume The control rod drive scram system is designed so that all of the water that is discharged from the reactor by a scram can be accommodated in the discharge l piping. The two scram discharge volumes have a capacity of 48 gallons of water I each and are at the low points of the scram discharge piping. l During normal operation the scram discharge volume system is empty; however, should it fill with water, the water discharged to the piping could not be accommodated which would result in slow scram times or partial control rod insertion. To preclude this occurrence, redundant and diverse level detection devices in the scram discharge instrument volumes have been provided. From a l reference zero established by analysis, the instruments are set to alarm at a '

water level less than 4.5 gallons, initiate a control rod block before the 17 gallon water volume, and scram the reactor before the water volume reaches 38 i

gallons. As indicated above, there is sufficient volume in the piping to I

accommodate the scram without impairment of the scram times or amount of insertion of the control rods. This function shuts the reactor down while-sufficient volume remains to accommodate the discharged watcr and precludes the situation in which a scram would be required but not be able to perform its function properly.

4.1 BASES The reactor protection system is made up of two independent trip systems.

There are usually four channels to monitor each parameter with two channels in l each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both trip systems will produce a reactor scram. . The system meets the intent of IEEE-279 for nuclear power plant protection systems. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with General Electric Company Topical Report NEDC-30851P-A,  !

" Technical Specification Improvement Analysis for BWR Reactor Protection System," as approved by the NRC and documented in the safety evaluation report (NRC letter to T. A. Pickens from A. Thadani dated July 15,1987).

A comparison of Tables 4.1.1 and 4.1.2 indicates that two instrument channels have not been included in the latter table. These are: mode switch in shutdown and manual scram. All of the devices or sensors associated with these scram functions-are simple on-off switches and, hence, calibration during operation is not applicable (i.e., the switch is either on or off).

The sensitivity of LPRM detectors decreases with exposure to neutron flux at a slow and approximately constant rate. This is compensated for in the APRM system by calibrating every three days using heat balance data and by calibrating individual LPRM's every 1000 effective full power hours using TIP traverse data.

Amendment No. 42, 133, 138, 147 '40

PHPS TABLE 3.2.B

. INSTRUMENTATION THAT' INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum # of Operable Instrument Channels Per Trio System (1) Trio Function Trip level Setting Remarks 2 Reactor Low-Low Water Level at or above -49 in. 1. In conjunction with low indicated level (4) Reactor Pressure, initiates Core Spray and LPCI.

2. In conjunction with High Drywell Pressure, 120 second time delay and LPCI or Core Spray pump interlock initiates Auto Blowdown (ADS).

3. Initiates HPCI; RCIC.

4. Initiates starting of Diesel Generators.

2 Reactor High Water Level i48" indicated level Trips HPCI and RCIC turbines.

1 Reactor low Level >-151" indicated Prevents inadvertent operation I (inside shroud) level of containment spray during accident condition.-(Indicative of 2/3 core coverage) 2 Containment High Pressure 1.55 < p < 1.82 psig Prevents inadvertent operation I of containment spray during accident condition. Instrument is set to trip before 1.82 increasing and reset before 1.55 decreasing.

Amendment No. 90 47

_. . . - . . , , , . . . . .- .- . . - - . - . .-.. .. , - . . - . -- .. - . - _ . . . - . - . . - . - - _ . . - . - . ~.

PNPS TABLE 3.2.B (Cont'd)

INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTENS Minimum # of Operable Instrument Channels Per Trio System (1) Trio Function Trio Level Setting Remarks 2 High Drywell Pressure $2.22 psig 1. Initiates Core Spray; LPCI; HPCI.

2. In conjunction with Low-Low Reactor Water Level,120 second time delay and LPCI or Core Spray pump running, initiates Auto Blowdown (ADS)

3. Initiates starting of Diesel Generators

4. In conjunction with Reactor low Pressure initiates closure of HPCI vacuum breaker containment isolation valves.

1 Reactor Low Pressure 400 psig 25 Permissive for Opening Core Spray and LPCI Admission valves.

1 Reactor Low Pressure $110 psig In conjunction with PCIS signal permits closure of RHR (LPCI) injection valves.

1 Reactor Low Pressure 400 psig i 25 In conjunction with Low-Low Reactor Water Level initiates Core Spray and LPCI.

2 Reactor Low Pressure 900 psig 25 Prevents actuation of LPCI break detection circuit.

2 Reactor Low Pressure 100>P>50 psig Isolates HPCI and in conjunction with High Drywell Pressure initiates closure of HPCI vacuum breaker containment isolation valves.

Amendment No. 421-113,-148 48

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~

. PNPS TABLE 3.2.0-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS Trio Function Trio Setooint APRM Upscale (1) (2)  :

APRM Inoperative Not Applicable APRM Downscale 2 2.5 Indicated on Scale  !

i Rod Block Monitor (Power Dependent) (1) (3) -j Rod Block Monitor Inoperative Not Applicable i

Rod Block Monitor Downscale (1) (3) .j IRM Downscale 2 5/125 of Full Scale .l IRM Detector not in Startup Position Not Applicable IRM Upscale s 108/125 of Full Scale l 1

IRM Inoperative Not Applicable SRM Detector not in Startup Position Not Applicable  ;

SRM Downscale 2 3 counts /second 5

SRM Upscale 1 10 counts /second i

SRM Inoperative Not Applicable l Scram Discharge Instrument Volume s 17 gallons l t Water Level - High 1 Scram Discharge Instrument Volume - Not Applicable f Scram Trip Bypassed l Recirculation Flow Converter - Upscale s 120/125 of Full Scale j Recirculation Flow Converter - Not Applicable Inoperative '

Recirculation Flow Converter - 5 10% Flow Deviation for > 80% l Comparator Mismatch Rated Power, and  ;

5 15% Flow Deviation _for s 80%

Rated Power j (1) The trip level setting shall' be as 'specified in the CORE OPERATING '

LIMITS REPORT.-

~ (2) When the reactor mode switch is in the refuel or startup pos'itions,

_ the APRM rod block trip setpoint. shall be less than or equal to 13%' i of rated thermal power, but always less than the APRM flux scram  !

trip setting. .

j (3) The RBM bypass time delay-(td2) shall be < 2.0 seconds. j Amendment No. 42, 110, 129, 133, 138 55a j H

-j

, PNPS TABLE 3.2-G INSTRUMENTATION THAT INITIATES RECIRCULATION PUMP TRIP .;

AND [

ALTERNATE R0D INSERTION

{

Minimum Number of r Operable or Tripped I Instrument Channels -?

Per Trio System (1) Trio Function Trio level Settina l 2 High Reactor Dome 1175 5 PSIG l Pressure  !

2 Low-Low Reactor >-46.3" indicated -!

Water Level level l

Actions (1) There shall be two (2) operable trip systems for each function. .i (a) If the minimum number of operable or tripped instrument l channels for one (1) trip system cannot be met, restore the l trip system to operable status within 14 days or be in at  ;

least hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '}

}

(b) If the minimum operability conditions (1.a) cannot be met l for both (2) trip systems, be in at least hot shutdown  ;

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

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[ ~PNPS Table ~3.1.1 REACTOR PROTECTION " TEM (SCRAM) INSTRUMENTATION REQUIREMENT'  !

Operable Inst. .

Modes in Which Function Channels per Trip Function Trip Level Setting Must Be Operable Action (I)

• Trio System (1) Refuel-(7) Startup/ Hot Run MinimumiAvail. Standb_y

) --

1 1 Mode' Switch in Shutdown X X X A

]L Manual Scram 1 1 X X X A

/

IRM 3 4 High Flux s120/125 of full scale X X (5) A 3 4 Inoperative X X (5) A h

APRM 2

2 3

3 High Flux Inoperative (15) (17) (17) X A or B A or B s

( '

(13) X X(9) X 2 3 High-Flux (15%) sl5% of Design Power X X (16) A or B ,

2 2 High Reactor Pressure . s1085 psig X(10) X X A ,

2 2 High Drywell Pressure s2.5 psig X(8) X(8) X A -

/

2 2 React _or low Water level a9 In. Indicated Level X X X A kg SDIV High Water level: Gallons X(2) X X A 2 2 East 2 2 West 2 2 Main Condenser low '

Vacuum a23 In. Hg Vacuum X(3) X(3) X A or C SSX '

2 2 Main Steam Line High s h rmal Full Power Radiation. Background (18) X X X(18) A or C (

4 4 Main Steam Line .

. Isolation Valve Closure s10% Valve Closure X(3)(6) X(3)(6) X(6) A or C $

2 2 Turbine Control Valve al50 psig Control Oil ,

. Fast Closure Pressure at -

Acceleration Relay _ X(4) _X(4) X(4) A or D y

'4 4 Turbine.Stop Valve s10% Valve Closure X(4)~ X(4) X(4) A or D i Closure OevisionISMe.

Amendmen D o. 15r-42,-86 1 -92r-117, 133, # 4 27

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3.1 BASES (Cont'd) range of applicability of the fuel cladding integrity safety limit. In i

'f

' addition, the isolation valve closure scram anticipates the pressure and ,

flux transients that occur during normal or inadvertent isolation valve F closure. With the scrams set at 10 percent of valve closure, neutron flux jd ' '

does not increase. k 1:

Hioh Reactor Pressure -

The high reactor pressure scram setting is chosen slightly above the -

i maximum norm;.1 operating pressure to permit normal operation without spurious scram, yet provide a wide margin to the ASME Section III

('

)

allowable reactor coolant system pressure (1250 psig, see Bases Section i 3.6.D). ,

Hiah Drvwell Pressure F

Instrumentation for the drywell is provided.to detect a loss of coolant -/

accident and initiate the core standby cooling equipment. A high drywell e pressure scram is provided at the same setting as the Core Standby Cooling f Systems (LSCS) initiation to minimize the energy that must be accommodated ' '

during a loss of coolant accident and to prevent return to criticality.

This instrumentation is a backup to the reactor vessel water level /

instrumentation. /

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/.-

Main Steam line Hioh Radiatio 9 High normalradiation nitrogenlevels in the main and oxygen steam line radioactivity tunnel is an aboveofthat indication due fuel.

eaking to the. /

A scram is initiated whenever such radiation level exceede sever times }, '

normal background. The purpose of this scram is to reduce M ource of ,

such radiation to the extent necessary to prevent excessive turbine- '

cohtamination. Discharge of excessive amounts of radioactivity to the .

site environs is prevented by the air ejector off-gas monitors that cause (

an isolation of the main condenser off-gas line. /

Reactor Mode Switch ',)

The reactor mode switch acttttes or bypasses the various scram functions (

appropriate to the particular plant operating status (Reference FSAR fd Section 7.2.3.9). f-if Manual Scram g(

The manual scram function is active in all codes, thus providing for a /

manual means of rapidly inserting control rods during all modes of reactor -

operation.

3"j DOR lY Emendmentl o. 6, 79, 133, 39

3.1 FASES (Cont'd) h Scram Discharge Instrument Volume The control rod drive scram system is designed so that all of the water [

that is discharged from the reactor by a scram can be accommodated in the p discharge piping. The two scram discharge volumes have a capacity of 48 gallons of water each and are at the low points of the scram discharge /

piping. ,.

During normal operation the scram discharge volume system is empty; '

however, should it fill with water, the water discharged to the pip ng 1 -

could not be accommodated which would result in slow scram times or \ .-

partial control rod insertion. To preclude this occurrence, redundirt and D- ,

diverse level detection devices in the scram discharge instrument vrilumes '

have been progi ed. From a reference zero established by analysis, the

% ,+%

~ instrumentr ' ' alarm at a r level lessgth n 4.5 gallons, initiate a Wi control rod ock ore the v before the wale g ~ reac s allon water gallons. As' cveTfandscramthereactor indicated above, there is [

E sufficient volume in the ping accommodate the scram without [,

impairment of the scram imes or mount of insertion of the control rods.

This function shuts th reactor do'r. 'hile sufficient volume remains to '

accommodate the disc rged water an precludes the situation in which a scram would be requ' red but not be a le to perform its function properly. 7 4.1 SAL /7 38 [,1

( ,

m The reactor protection system is made up of two independent trip systems. ,

There are usually four channels to monitor each parameter with two ,-

channels in each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both trip systems will prcduce a reactor scram. -

'he system meets the intent of IEEE-279 for nuclear power plant protection - .

systems. Specified surveillance intervals and surveillance and -'

maintenancr utage times have been determined in acccrdance with General [ 4 Electric f.

• Topical Report NEDC-30851P-A, " Technical Specification f Improvemen- - ;is for BWR Reactor Protection System," as approved by -

the NRC and d. x.ented in the safety evaluation report (NRC letter to T. '

A. Pickens frem A. Thadani dated July 15,1987).

A comparison of Tables 4.1.1 and 4.1.2 indicates that two instrument channels have not been included in the latter table. These are: mode ',

switch in shutdown and manual scram. All of the devices or sensors '-

associated with these sc."am functions are simple on-off switches and, , ,

hence, calibration during operation is not applicable (i.e., the switch is '

either on or off). 7

/ ,

The sensitivity of LPRM detectors decreases with exposure to neutron flux -

at a slow and approximately constant rate. Thisiscompensatedforinthef, APkM system by .? librating every three days using heat balance data and by /

calibrating io dual LPRM's every 1000 effective full power hours using /

TIP traverse - -

%) Q icn %

Amendment No. Y ,C 133, 38, 40

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a O O d -

PNPS ,

TABLE 3.2.B INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum # of Operable Instrument Channels.Per_Tr_1p System (1) Trip Function Trip Level Setting Rema rk.s 2 Reactor low-low Hater e or above -49 in. 1. In conjunction with low level indicated level (4) Reactor Pressure, initiates Core ',pi ay and LPCI.

2. In conjunction with High Drywell Pressure, 120

~

second time delay and LPCI or Core Spray pump interlock initiates Auto Blowdown (ADS).

3. Initiates HPCI; RCIC.

4. Initiates starting of Diesel Generators.

2 Reat.or High Water Level 9 4f!" indicated Trips HPCI and RCIC turbines.

level 1 ~ Reactor Low I.evel lE7" = ve-ve+s M - Prevents inadvertent operation /

(Inside shroud) iero(fpproximately of containment spray during ,

/3 core height) accident condition. f j

> ~457 "Le Es-,u/

c[4 of -

2 Containment High Pressure . <p<@psig Prevents inadvertent operation a of containment spray during _ _ .

accident conditto y

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PNPS

• TABLE 3.2.B (Cont'd)' '

Minimum'** of INSTRUMENTATION THAT INITIATE 3 OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Operable Instrument Channel 5' Par Trip System (1) Trin Function Trio Level Settinz Remarks

-2 High Drywell Pressure ,_'.5 psig 1. Initiates Core Spray; LPCI;' HPCI.

2. In conjunction with Low-Low Reactor d'E E Water Level, 120 second time delay and LPCI or Core Spray pump running, initiates Auto Blowdown (ADS)

3. Initiates starting of Diesel Generators

4. In conjunction with Reactor Low Pressure initiates closure of HPCI vacuum breaker containment isolation -

valves. i 1 Reactor Low Pressure 400 psig i 25 Permissive for Opening Core Spray and LPCI Admission valves.

1 Reactor Low Pressure $110 psig In conjunction with PCIS signal permits closure of RHR (LPCI) inj ection valves.

1 Reactor Low Pressure 400 psig i 25 In contur.ettun with Low-Low Reactor Water leve'_ initiates Core Spray and LPCI .

-2 Reactor Low Pressure 900 psig i 25 Prevents actuation of LPCI break detection circuit.

-2 Reactor Low Pressure 100>P>50 psig Isolates HPCI and in. conjunction with High Drywell Pressure initiates closure f HPCI vacuum breaker containment isolation valves.

keigigiu103 il'.

AmeTidment No. 42,-113,h .48

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PNPS

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TABLE 3.2.C-2 -

CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS .i T'io r function . Trio Setooint j APRM UpscM e (1) (2)

APRM Inoperative Not Applicable }

i APRM Downstale 1 2.5 Indicated on Scale ] ,

Rod 31ock Monitor (Power Dependent) (1) (3)

{

Rod Block Monitor Inoperative Not Applicable I Rod Block Monitor Downscale (1) (3) p l IRM Downscale 15/125 of Full Scale  !

IRM Detector not in Startup Position Not Applicable l

IRM Upscale 1 108/125 of Full Scale l IRM Inoperative Not Applicable {

i SRM Detector not in Startup Position Not Applicable f

'i' SRM Downscale 1 3 counts /second

-s "Y SRM Upscale 1_105 counts /second SRM Inoperative Not Applicable _;

~

Scram Discharge Instrument Volume I gallons Hater Level - High p  ;

Scram Discharge Instrument Volume - Not Applicable  :

Scram Trip Bypassed l

Recirculation Flow Converter - Upscale I 120/125 of Full Scale- i Recirculation Flow Converter - Not Applicable  !

Inoperative l Recirculation Flow Converter - 1 10% Flow Deviation for > 80%- I Comparator Mismatch Rated Power, and' )

1 15% Flow Deviation'for 1.80%  !

Rated Power i

(1) The. trip level setting shall be as specified in the CORE OPERATING  !

LIMITS REPORT. . .

(2)- When the reactor mode. switch is in the refuel or startup positions, l the' APRM rod block trip setpoint shall be less than or equal--_to 13% . l of rated thermal power, but always less than.the APRM' flux scram. '

trip setting.

yf '(3) The-RBH bypass time delay-(td2) shall be < 2.0 seconds. @  ;

An.adment No. 42,-770.729,722,h 55a

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, ,_ PNPS

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TABLE 3.2-G

' INSTRUMENTATION THAT INITIATES RECIRCULATION PUMP TRIP AND ALTERNATE ROD INSERTION Hinimum Number of Operable or Tripped Instrument Channels Per Trio System (1) Trio Function Trio Level Settina 2 High Reactor Dome 1175 ~ PSIG Pressure g 2 Low-Low Reactor 1 " .25 inche:

Hater Level -above the top of y_g

-the,1c4iye fue1-

.Q  :

Actioni (1) There shall be two (2) operable trip systems for each function.

(a) If the minimum number of operable or tripped instrument channels for one (1) trip system cannot be met, restore the trip system to operable status within 14 days or be in at Q least hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g (b) If the minimum operability conditions (l.a) cannot be met for both (2) trip systems, be in at least hot shutdown '

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

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