Text

Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation
	ML20236S492
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Site:	Beaver Valley
Issue date:	07/15/1998
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ATTACHMENT A-218 1

Unit No.1 Technical Specification Pages i

9007240300 900715 PDR ADOCK 05000334 PDR:

P

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 i

l Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated.

The revised pages are identified by amendment number and contain vertical lines indicating

. the areas of change.

Remove Insert 3/4 3-2 3/4 3-2 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-11 3/4 3-11 3/4 3-13 3/4 3-13 B 3/4 3-ic B 3/4 3-1c B 3/4 3-id B 3/4 3-le B 3/4 3-1f B 3/4 3-1g B 3/4 3-lh l

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DPR-66 TABLE 3.3-1 (Continued)

With the number of channels OPERABLE one less than

' ACTION 3 required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

l b.

Above P-6 but below 5 percent of RATED THERMAL POWER, l

restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5 percent of RATED THERMAL POWER.

c.

Above 5

percent of RATED THERMAL

POWER, POWER OPERATION may continue.

ACTION 4 - a.

MODE 2 (Below P-6); with one source range neutron flux channel inoperable, immediately suspend l

operations involving positive reactivity additions.

b.

MODE 3, 4 and 5; with one source range neutron flux channel inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

c.

MODE 2 (Below P-6),

3, 4 and 5; with two source range neutron flux channels inoperable, immediately open the reactor trip breakers.

With the number of OPERABLE channels one less than ACTION 5 the Minimum Channels OPERABLE requirement:

suspend o

rations. involving positive-reactivity a.

additions,pIand

.b.

Close unborated water source isolation valve (s) (1CH-

90) or (1CH-91 and 1CH-93) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and c.

Perform Surveillance Requirement 4.1.1.1.1 or 4.1.1.2, as applicable, within the next hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

Not Applicable.

ACTION 6 (7)

Plant cooldown is allowable provided the temperature change is l

accounted for in the calculated shutdown margin.

BEAVER VALLEY - UNIT 1 3/4 3-6 Amendment No.

DPR-66 TABLE 3.3-1 (Continued)

With che number of OPERABLE channels (0) one loss than ACTION,7 the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

i

-a.

The inoperable channel is placed in the tripped l

condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and l

j b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for -surveillance testing of other channels per Specification 4.3.1.1.1.

l l

ACTION 8 With the number of OPERABLE channels one less than the Total Number of Channels and with the THERMAL l

POWER level above P-7, place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.

Not' applicable.

ACTION 9 Not applicable.

-ACTION 10 With less-than the Minimum Number of Channels ACTION 11

OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With the number of channels OPERABLE one less than ACTION 12 required by the Minimum Channels OPERABLE requirement r

the inoperable channel to OPERABLE stbus estore within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

With the number of OPERABLE channels one less than ACTION 39 the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

(6)

An OPERABLE hot leg channel consists of:

1) three RTDs per hot

leg, or 2) two RTDs per hot leg with the failed RTD disconnected and the required bias applied.

l BEAVER VALLEY - UNIT 1 3/4 3-7 Amendment No.

I

DPR-66 TABLE 3.3-1 (Continued)

ACTION,4 0 - a.

With one of the diverse trip features (und:-

.tage or shunt trip attachment) of a reactor trip

<eaker

. inoperable, restore the diverse. trip femeure to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker = inoperable and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Neither breaker shall be bypassed while one of the diverse trip features is taaperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

I b.

With one reactor trip breaker inoperable as e result of something other than an inoperable divers 6 trip feature, be in.at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1, provided the other channel is OPERABLE.

BEAVER VALLEY - UNIT 1 3/4 3-8 Amendment No.

(Next page is 3/4 3-11)

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DPR-66 TABLE 4.3-1 (Continued)

NOTATION (l')

If.not. performed in previous 31 days.

(2)

Heat balance only, above 15 percent of RATED THERMAL POWER.

' At least once every 31 Effective Full Power Days (EFPD)

(3)'

l compare incore to excore axial imbalance above 15 percent of RATED THERMAL POWER.

Recalibrates if absolute difference greater than or equal to 3 percent.

I (4)

(Not Used)

Each' train tested every other month.

(5)

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-10.

Below P-6, not required to be performed for source range (8) instrumentation prior to entering MODE 3 from MODE 2 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entry into MODE 3.

(Not Used)

(9)

The CHANNEL FUNCTIONAL TEST shall independently verify the (10)

OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

The CHANNEL FUNCTIONAL TEST shall independently verify the (11)

OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

Local manual shunt trip prior to placing breaker in (12) service.

Automatic undervoltage trip.

(13)

With the reactor trip system breakers closed and the (14) control rod drive system capable of rod withdrawal.

i Surveillance Requirements need not be performed on (15) alternate detectors until connected and required for OPERABILITY.

BEAVER VALLEY - UNIT 1 3/4 3-13 Amendment No.

2

DPR-66 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINRRnRn SAFETY FEATURES (ESF)

INSTRUMENTATION (Continued)

The ' instrumentation functions that receive input from neutron detectors are modified by a note stating that neutron detectors are excluded from the CHANNEL CALIBRATION.

The CHANNEL CALIBRATION for the power range neutron detectors consists of a normalization of the detectors based on a power calorimetric and flux map performed above i

15% RATED THERMAL POWER.

The power range neutron detector CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 or 1 on unit startup because the unit must be in at least MODE 1 to perform the test.

The neutron detector CHANNEL CALIBRATION for the source range and intermediate range detectors consists of obtaining detector characteristics and performing an engineering evaluation of those characteristics.

The intermediate range. neutron detector CHANNEL CALIBRATION is performed every

'18 months but is not required for entry into MODE 2 on unit startup because the unit must be in at least MODE 2 to perform the test.

The source range neutron detector CHANNEL CALIBRATION is performed every 18 months but is not required for entry into MODE 2 or 3 on

~ unit shutdown because the unit must be in at least MODE 3 to perform the test.

The P-6 permissive neutron detector CHANNEL CALIBRATION is performed in conjunction with the intermediate range neutron detectors.

The overtemperature AT, P-8, P-9 and P-10 permissive neutron detector CHANNEL CALIBRATIONS are performed in conjunction with the power range neutron detectors.

Source Ranoe Neutron Flux The limiting con:11 tion for operation (LCO) requirement for the source range neutron flux trip function ensures that protection is provided against a n uncontrolled rod cluster control assembly (RCCA) bank rod withdranal accident from a subcritical condition during startup with the reactor trip breakers (RTBs) closed.

This trip function' provides redundant protection to the Power Range Neutron Flux-Low Setpoint and Intermediate Range Neutron Flux trip functions

]

(See UFSAR Section 14.1.1 and Specification 2.2.1 Bases).

In MODES l

3, 4,

and 5,

with the RTBs closed, administrative controls also l

prevent the uncontrolled withdrawal of rods.

The nuclear instrumentation system (NIS) source range detectors are located l

external to the reactor vessel and measure neutrons leaking from the core.

The NIS source range detectors do not provide any inputs to control systems.

The source range trip is the only reactor trip sp *en (RTS) automatic protection function required in MODES 3,

4, ana 5.

Therefore, the functional capability at the specified trip setpoint is assumed to be available.

BEAVER VALLEY - UNIT 1 B 3/4 3-ic Amendment No.

DPR-66 INSTRUMENTATION BASES I

1 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINRRnun SAFETY FEATURRM (ESF) i INSTRUMENTATION (Continued) l The LCO requires two channels of source range neutron flux to be i

OPERABLE when the RTBs are closed.

Two OPERABLE channels are sufficient to ensure no single randon failure will disable this trip function.

The LCO also requires one channel of the source range l

neutron flux to be OPERABLE in MODE 3, 4,

or 5 with RTBs open.

In this case, the source range function is to provide control room indication and the high flux at shutdown alarm.

The outputs of the function to RTS logic are not required OPERABLE when the RTBs are l

open.

The source range neutron flux function provides protection for control rod withdrawal from subcritical, boron dilution and control rod ejection events.

The function also provides visual neutron flux indication in the control room.

1 In MODE 2 when below the P-6 setpoint during a reactor startup, the source range neutron flux trip must be OPERABLE.

Above the P-6 setpoint, the Intermediate Range Neutron Flux trip and Power Range Neutron Flux-Low Setpoint trip will provide core protection for reactivity accidents.

Above the P-6 setpoint, the NIS source range detectors are de-energized and not functional.

i In MODE 3, 4,

or 5 with the reactor shut down and with the control i

rod drive (CRD) system capable of rod withdrawal, the source range neutron flux trip function must also be OPERABLE. If the CRD system is not capable of rod withdrawal, the source range detectors are not required to trip the reactor.

However, their monitoring function must be OPERABLE to monitor core neutron levels and provide indication of reactivity changes that may occur as a result of events like a boron dilution.

Suitable detectors used in place of primary source range neutron flux monitors are recognized as alternate detectors.

Alternate detectors may be used in place of primary source range neutron flux monitors as long as the required neutron flux indication, high flux at shutdown alarm, and source range high neutron flux trip functions are provided.

BEAVER VALLEY - UNIT 1 B 3/4 3-1d Amendment No.

i

DPR-66 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINRRRED SAFETY FEATURES (ESF)

INSTRUMENTATION fContinued)

I ACTION 4 Item '(a) applies to one inoperable source range neutron flux trip channel when in MODE 2,

below the P-6 setpoint, and performing a i

reactor startup.

With the unit in this condition, below P-6, the l

NIS source range performs the monitoring and protection functions.

1 With one of the two channels inoperable, operations involving positive reactivity additions shall be suspended immediately.

This will preclude any power escalation.

With only one source range channel

OPERABLE, core protection is severely reduced and any l

actions that add positive reactivity to the core must be suspended I

immediately.

' Item (b) applies to one inoperable source range neutron flux trip l

channel when in MODE 3, 4,

or 5, with the RTBs closed and the CRD system capable of rod withdrawal.

With the unit in this condition, the NIS source' range performs the monitoring and protection functions.

With one of the source range channels inoperable, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is allowed to restore it to OPERABLE status.

If the channel cannot be returned to an OPERABLE status, 1 additional hour is allowed to open the RTBs.

Once the RTBs are open, rod withdrawal is not possible and the unit enters ACTION 5.

The allowance of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to restore the channel to OPERABLE

status, and the additional hour to open the RTBs, are justified in WCAP-10271-P-A, Supplement 2, Rev.

1, June 1990.

Item (c) applies to two inoperable source range neutron flux trip channels when in MODE 2, below the P-6 setpoint, and performing a reactor startup, or in MODE 3, 4,

or 5 with the RTBs closed and the CRD system capable of rod withdrawal.

With the unit in this condition, below P-6, the NIS source range performs the monitoring and protection functions.

With both source range channels I

inoperable, the RTBs must be opened immediately.

With the RTBs open, rod withdrawal is not possible and the unit enters ACTION 5.

l l

l BEAVER VALLEY - UNIT 1 B 3/4 3-le Amendment No.

DPR-66 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINRRnRn SAFETY FEATURES (ESF)

INSTRUMENTATION (Continued)

&GTJON 5 This ACTION applies. when the required number of OPERABLE source range neutron flux channels is not met in MODE 3, 4,

or 5 with the RTBs open.

With the unit in this condition, the NIS source range performs the monitoring function.

With less than the required number of ~ source range channels

OPERABLE, operations involving positive reactivity. additions shall be suspended immediately.

This will preclude any power escalation.

However, a note applicable to this ACTION allows plant cooldown as long as the shutdown margin-is

' adequate to account for the positive reactivity addition resulting from the temperature change.

This ensures the core is controlled and the shutdown margin requirements are satisfied for all

-applicable events.

In addition to suspension of positive reactivity additions, the valve (s) that controls the addition of unborated water to the RCS must be closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The isolation of unborated water sources will preclude a boron dilution accident.

Also, the shutdown margin (SDM) must be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereaf ter as per SR 4.1.1.1.1 or 4.1.1.2, SDM verification.

With no source range channels

OPERABLE, core protection is severely reduced.

Verifying the SDM within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months allows sufficient - time to perform the calculations and determine that the SDM requirements are met. The SDM must also be verified

-once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter to ensure that the core reactivity.has not changed.

Item (a) precludes any positive reactivity additions; i

therefore, core reactivity should.not be increasing, and a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months frequency is adequate.

This does not include xenon decay which is accounted for in the shutdown margin surveillance.

The completion l

times of within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are based on operating

)

. experience in performing the ACTIONS and the knowledge that unit conditions will change slowly.

SOURCE RANGE NEUTRON FLUX i

SURVEILLANCE REQUIREMENTS (SR)

CHANNEL CHECK The alternate source range detectors are modified by a note to indicate they are not subject to the source range detector surveillance requirements until they have been connected to the applicable circuits and'are required to be OPERABLE.

This complies with the testing requirements for components that are required to be OPERABLE.

BEAVER VALLEY - UNIT 1 B 3/4 3-1f Amendment No.

DPR-66 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINRRnRn SAFETY FEATURRit: (ESF)

INSTRUMENTATION (Continued)

Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ensures that gross failure of instrumentation has not occurred.

A CHANNEL CHECK is a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is. based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the

-two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious.

A CHANNEL CHECK for a

single channel involves a

qualitative. assessment of the channel indication to verify the channel is operating in the approximate range for the expected plant conditions.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the unit staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the match criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit.

The frequency is based on operating experience that demonstrates channel failure is rare.

Thus, performance of the CHANNEL CHECK ensures that undetected overt channel failure is limited to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels.

When the control rods are fully inserted and are not capable of withdrawal, inadvertent control rod withdrawal is not a concern and one source range detector can adequately monitor the core.

CHANNEL FUNCTIONAL TEST The alternate source range detectors are modified by a note to indicate they are not subject to the source range detector surveillance requirements until they have been connected to the l

applicable circuits and are required to be OPERABLE.

This complies with the testing requirements for components that are required to be l

OPERABLE.

1 BEAVER VALLEY - UNIT 1 B 3/4 3-1g Amendment No.

DPR-66 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGIN m vn SAFETY FEATURES (ESF) l INSTRUMENTATION (Continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel every 92 days to ensure the entire channel will perform the intended function.

.Satpoints must be within the Allowable Values.

The frequency of 92 days is justified in WCAP-10271-P-A, Supplement 2,

Rev.

1, June 1990.

This surveillance is modified by a Note that specifies. testing when below P-6 and is clarified to address the transition from MODE 2 to MODE 3.

A transition into MODE 3 with the reactor trip breakers closed is often made for a short period of time during plant shutdown.

During a normal shutdown, the reactor trip breakers are opened shortly after entering MODE 3.

The transition time in MODE 3 from when the reactor trip breakers are closed to when they are opened is less than the time required to perform the CHANNEL FUNCTIONAL TEST prior to entering MODE 3.

Therefore, an allowance to enter MODE 3 without first performing the source range CHANNEL FUNCTIONAL TEST is warranted.

CHANNEL CALIBRATION The alternate source range detectors are modified by a note to 1

indicate they are not subject to the source range detector surveillance requirements until they have been connected to the applicable circuits and are required to be OPERABLE.

This complies with the testing requirements for components that are required to be OPERABLE.

A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling.

The CHANNEL CALIBRATION for the source range neutron detectors consists of obtaining the detector plateau and preamp discriminator

curves, evaluating those

curves, and establishing detector operating conditions as directed by the detector manufacturer.

The 18 month frequency is based on the need to perform this surveillance under the conditions that apply during a plant outage since performance at power is not possible.

The l

protection and monitoring functions are also calibrated at an 18 month frequency as is normal for reactor protection instrument l

channels.

Operating experience has shown these components usually i

l pass the surveillance when performed on the 18 month frequency.

BEAVER VALLEY - UNIT 1 B 3/4 3-lh Amendment No.

{

l 1

ATTACHMENT A-85 Unit No. 2 Technical SDeciflCation Panes l

J i

l l

\\

l i

l ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, l

with the enclosed pages as indicated.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

l Remove Insert X

X 3/4 3-2 3/4 3-2 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-10 3/4 3-10 3/4 3-13 3/4 3-13 B 3/4 3-5 B 3/4 3-5 B 3/4 3-6 B 3/4 3-6 B 3/4 3-7 B 3/4 3-7 B 3/4 3-8 B 3/4 3-9 B 3/4 3-10 B 3/4 3-11 B 3/4 3-12 i

l l

NPF-73 INDEX BASES l

SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS i

3/4.2.1 AXIAL FLUX DIFFERENCE (AFD)...................B 3/4 2-1

)

l 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOTCHANNELFACTORSF(Z);ANDFh.............B3/42-2 g

3/4.2.4 QUADRANT POWER TILT RATIO.....................B 3/4 2-5 3/4.2.5 DNB PARAMETERS................................B 3/4 2-5 3/4.3 -INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...........B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION........................B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.'3.1 Radiation Monitoring Instrumentation..........B 3/4 3-10 l 3/4.3.3.2 Movable Incore Detectors......................B 3/4 3-10 l 3/4.3.3.3 Seismic Instrumentation....................... B 3 /4 3-11 l 3/4.3.3.4 Meteorological Instrumentation................B 3/4 3-11 l 1

3/4.3.3.5 Remote Shutdown Instrumentation...............B 3/4 3-11 l 3/4.3.3.7 Chlorine Detection Systems....................B 3/4 3-11 l 3/4.3.3.8 Accident Monitoring Instrumentation...........B 3/4 3-12 l 3/4,3.3.11 Explosive Gas Monitoring Instrumentation......B 3/4 3-12 l

)

3/4.3.4-TURBINE OVERSPEED PROTECTION..................B 3/4 3-12 l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...................................B 3/4 4-1 3/4.4.2 AND 3/4.4.3 SAFETY VALVES.........................B 3/4 4-2 3/4.4.4 PRESSURIZER...................................B 3/4 4-2 BEAVER VALLEY - UNIT 2 X

Amendment No.

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NPF-73 TABLE 3.3-1 (Continued)

With the number of channels OPERABLE one less than ACTION 3 required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL l

POWER above the P-6 setpoint.

b.

Above P-6 but below 5 percent of RATED THERMAL

POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5 percent of RATED THERMAL POWER.

c.

Above 5 percent of RATED THERMAL POWER, POWER OPERATION may continue.

a.

MODE 2

(Below P-6);

with one source range ACTION 4 neutron flux channel inoperable, immediately suspend operations involving positive reactivity additions.

b.

MODE 3, 4 and 5; with one source range neutron flux channel inoperable, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

c.

MODE 2 (Below P-6),

3, 4 and 5; with two source range neutron flux channels inoperable, immediately open the reactor trip breakers.

With the number of OPERABLE channels one less than ACTION 5 the Minimum Channels OPERABLE requirement:

additions,(fations involving positive reactivity Suspend ope a.

and b.

Close unborated water source isolation valves (2CHS-91, 2CHS-96 and 2CHS-138) er (2CHS-37 and 2CHS-828) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and c.

Perform Surveillance Requirement 4.1.1.1.1 or 4.1.1.2, as applicable, within the next hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

This Action is not used.

ACTION 6 (7)

Plant cooldown is allowable provided the temperature change is accounted for in the calculated shutdown margin.

BEAVER VALLEY - UNIT 2 3/4 3-6 Amendment No.

NPF-73 TABLE 3.3-1 (Continued)

With the number of OPERABLE channels N one less than ACTION 7 l

the Total Number of Channels, STARTUP and/or POWER i

OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met;

however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1.1.

With the number of OPERABLE channels one less than ACTION 8 the Total Number of Channels and with the THERMAL POWER level above P-9, place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.

This Action is not used.

ACTION 9 This Action is not used.

ACTION 10 With less than the Minimum Number of Channels ACTION 11

OPERABLE, operation may continue provideu the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With the number of channels OPERABLE one less than ACTION 12 required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

With the number of OPERABLE channels one less than ACTION 39 the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

(6)

An OPERABLE hot leg ::hannel consists of:

1) three RTDs per hot

leg, or 2) two RTDs per hot leg with the failed RTD disconnected and the required bias applied.

I BEAVER VALLEY - UNIT 2 3/4 3-7 Amendment No.

3

NPF-73 TABLE'3.3-1 (Continued) a.

With one of the diverse trip features ACTION 40 (undervoltage or shunt trip attachment) of a reactor trip breaker inoperable, restore the diverse trip feature to OPERABLE status within l

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and be in HO? STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Neither brecker shall be bypassed while one of l

the diverse t?tip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status, b.

With one reactor trip breaker inoperable as a result of something other than an inoperable diverse trip feature, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;

however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1, provided the other channel is OPERABLE.

With less than the Minimum Number of Channels ACTION 44 OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

BEAVER VALLEY - UNIT 2 3/4 3-8 Amendment No.

(Next page is 3/4 3-10)

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NPF-73 TABLE 4.3-1 (Continued)

TABLE NOTATION If not performed in previous 31 days.

(1)

(2)

Heat balance only, above 15 percent of RATED THERMAL POWER.

(3)

At least once every 31 Effective Full Power Days (EFPD) compare incore to excore. axial imbalance above 15 percent of RATED THERMAL POWER.

Recalibrates if absolute difference greater than or equal to 3 percent.

(4)

.(Not Used).

Each train tested every other month on a STAGGERED TEST (5)

BASIS.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-10.

Below P-6, not required to be performed for source range (8) instrumentation prior to entering MODE 3 from MODE 2 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entry into MODE 3.

(Not Used)

(9)

The CHANNEL FUNCTIONAL TEST shall independently verify the (10)

OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

The CHANNEL FUNCTIONAL TEST shall independently verify the (11)

OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

Local manual shunt trip prior to placing breaker in

.(12) service.

Automatic undervoltage trip.

(13)

With the reactor trip system breakers closed and the (14) control rod drive system capable of rod withdrawal.

l (15)

Surveillance Requirements need not be performed on l

alternate detectors until connected and required for l

OPERABILITY.

l BEAVER VALLEY - UNIT 2 3/4 3-13 Amendment No.

L

NPF-73 3/4.3 INSTRUMENTATION l

BASES 4

3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINRRnRn SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued) shutdown because the unit must be in at least MODE 3 to perform the test.

The P-6 permissive neutron detector CHANNEL CALIBRATION is performed in-conjunction with the intermediate range neutron detectors.

The overtemperature AT, P-8, P-9 and P-10 permissive neutron detector CHANNEL CALIBRATIONS are performed in conjunction with the power range neutron detectors.

Source Ranae Neutron Flux

The limiting condition for' operation (LCO) requirement for the source range neutron flux trip function ensures that protection is provided against an uncontrolled rod cluster control assembly (RCCA) bank rod withdrawal accident from a subcritical condition during startup with the reactor trip breakers (RTBs) closed.

This trip function provides redundant protection to the Power Range Neutron Flux-Low Setpoint and

-Intermediate Range Neutron Flux trip functions (see UFSAR Section 15.4.1 and Specification 2.2.1 Bases).

In MODES 3,

4, and 5, with the RTBs

closed, administrative controls e ?.so prevent the uncontrolled withdrawal of rods.

The nuclear instrumentation system (NIS) source range detectors are located external to the reactor vessel and measure neutrons leaking from the core.

The NIS source range detectors do not provide any inputs to control systems.

The source range trip is the only reactor trip system (RTS) automatic protection function required in MODES 3,

4, and 5.

Therefore, the functional capability at the specified trip setpoint is assumed to be available.

The LCO requires two channels of source range neutron flux to be OPERABLE when the RTBs are closed.

Two OPERABLE channels are sufficient to ensure no single randon failure will disable this trip l

function.

The LCO also requires one channel of the source range neutron flux to be OPERABLE in MODE 3, 4,

or 5 with RTBs open.

In this case, the source range function is to provide control room indication and the high flux at shutdown alarm.

The outputs of the function to.RTS logic are not required OPERABLE when the RTBs are open.

.The source range neutron flux function provides protection for i

control rod withdrawal from subcritical, boron dilution and control rod ejection events.

The function also provides visual neutron flux indication in the control room, l

BEAVER VALLEY - UNIT 2 B 3/4 3-5 Amendment No.

l NPF 'i3 3/4.3 INSTRUMENTATION 1

BASES

]

'3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINERnun SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTATION (Continued)

In MODE 2 when below the P-6 setpoint during a reactor startup, the source range neutron flux tr'.p must be OPERABLE.

Above the P-6 setpoint, the Intermediate Range Neutron Flux trip and Power Range Neutron Flux-Low Satpoint trip will provide core protection for reactivity accidents.

Above the P-6 setpoint, the NIS source range detectors are de-energized and not functional.

In MODE 3, 4, or 5 with the reactor shut down and with the control rod drive (CRD) system capable of rod withdrawal, the source range

. neutron flux trip function must also be OPERABLE.

If the CRD system is not capable of rod withdrawal, the source range detectors are not required to trip the reactor.

However, their monitoring function must be OPERABLE to monitor core neutron levels and provide indication of reactivity changes that may occur as a result of events like a boron dilution.

Suitable detectors used in place of primary source range neutron flux monitors are recognized as alternate detectors.

Alternate detectors may be used in place of. primary source range neutron flux monitors as long as the required neutron flux indication, high flux at shutdown

alarm, and source range high neutron flux trip functions are

.provided.

Note (8) limits the use of alternate detectors to a monitoring i

function until a plant design change can provide the capability for I

directly connecting these detectors into the source range circuits so l

they can provide the required alarm and trip functions.

j ACTION 4 Item (a) applies to one inoperable source range neutron flux trip channel when in MODE 2,

below the P-6 setpoint, and performing a reactor startup.

With the unit in this condition, below P-6, the NIS source range performs the monitoring and protection functions.

With one of the two channels inoperable, operations involving positive reactivity additions shall be suspended immediately.

This.will preclude any power escalation.

With only one source range channel OPERABLE, core protection is severely reduced and any actions that add positive reactivity to the core must be suspended immediately.

4 l

l BEAVER VALLEY - UNIT 2 B 3/4 3-6 Amendment No.

_ _ - _ _ _ _ _ =

NPF-73 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINuruRn SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION ( (Continued)

Item (b) applies to one inoperable source range neutron flux trip channel when in MODE 3, 4,

or 5, with the RTBs closed and the CRD system capable of. rod withdrawal.

With the unit in this condition, the NIS source range performs the monitoring and protection functions.

With one of the source range channels inoperable, 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is allowed to restore it to OPERABLE status.

If the channel cannot be returned to an OPERABLE status, 1 additional hour is allowed to open the RTBs.

Once the RTBs are open, rod withdrawal is not possible and the unit enters ACTION 5.

The allowance of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to restore the channel to OPERABLE status, and the additional hour to open the RTBs, are justified in WCAP-10271-P-A, Supplement 2, Rev.

1, June 1990.

Item (c) applies to two inoperable source range neutron flux trip channels when in MODE 2,

below the P-6 setpoint, and performing a reactor startup, or in MODE 3, 4,

or 5 with the RTBs closed and the CRD system capable of' rod withdrawal.

With the unit in this condition, below P-6, the NIS source. range performs the monitoring and protection functions.

With both source range channels inoperable, the RTBs must be opened immediately.

With the RTBs open, rod withdrawal is not possible and the unit enters ACTION 5.

ACTION 5 This ACTION applies when the required number of OPERABLE source range neutron flux channels is not met in MODE 3, 4,

or 5 with the RTBs open.

With the unit in this condition, the NIS source range performs the monitoring function.

With less than the required number of source range channels

OPERABLE, operations involving positive i

reactivity additions shall be suspended immediately.

This will preclude any power escalation.

However, a note applicable to this l

ACTION allows plant cooldown as long as the shutdown margin is adequate to account for the positive reactivity addition resulting from the temperature change.

This ensures the core is controlled and the shutdown margin requirements are satisfied for all applicable events.

In addition to suspension of positive reactivity additions, the valves that control the addition of unborated water to the RCS must be closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The isolation of unborated water sources will preclude a boron dilution accident.

Also, the shutdown margin (SDM) must be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter as per SR 4.1.1.1.1 or 4.1.1. 2, SDM verification.

With no source range channels

OPERABLE, core protection is severely reduced.

Verifying the SDM within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months allows sufficient time to perform the calculations and determine that i

BEAVER VALLEY - UNIT 2 B 3/4 3-7 Amendment No,.

NPF-73 i

3/4.3 INSTRUMENTATION I

BASES

]

I 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINRRnRn SAFETY i

FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

)

the SDM requirements are met. -The SDM must also be verified once per

)

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter to -ensure that the core reactivity has not l

changed.

Item -(a) precludes any positive reactivity additions; therefore, core reactivity should not be increasing, and a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months frequency is adequate.

This does not include xenon decay which is accounted for in the shutdown margin surveillance.

The completion times of within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are based on operating experience in performing the ACTIONS and the knowledge that unit conditions will change slowly.

SOURCE RANGE NEUTRON FLUX SURVEILLANCE REQUIREMENTS (SR)

I CHANNEL CHECK The alternate source range detectors are modified by a note to indicate they are not subject to the source range detector surveillance requirements until they have been connected to the applicable circuits and are required to be OPERABLE.

This complies with the testing requirements for components that are required to be OPERABLE.

Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ensures that gross failure of instrumentation has not occurred.

A CHANNEL CHECK l

is a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is based on the assumption I

that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious._

A CHANNEL CHECK for a single channel involves a qualitative assessment j

of the channel indication to verify the channel is operating in the approximate range for the expected plant conditions. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying that the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

l Agreement criteria are determined by the unit staff based on a l

combination of the channel instrument uncertainties, including indication and ' readability.

If a channel is outside the match criteria, it may be an indication that the sensor or the signal i

processing equipment has drifted outside its limit.

BEAVER VALLEY - UNIT 2 B 3/4 3-8 Amendment No.

NPF-73 l

2/4.3 INSTRUMENTATION i

BASES 3 / 4 '. 3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINRRnRn SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

The frequency is based on cQaratir g experience that demonstrates channel failure is rare.

Thub, performance of the CHANNEL CHECK ensures that undetected overt channel failure is limited to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels.

When the control rods are fully inserted and are not capable of withdrawal, inadvertent control rod withdrawal is not a concern and l

one source range detector can adequately monitor the core.

CHANNEL FUNCTIONAL TEST The alternate source range detectors are modified by a note to indicate they are not subject to the source range detector surveillance requirements until they have been connected to the applicable circuits and are required to be OPERABLE.

This complies with the testing requirements for components that are required to be OPERABLE.

I A CHANNEL FUNCTIONAL TEST is performed on each required channel every 92 days to ensure the entire channel will perform the intended function.

Satpoints must be within the Allowable Values.

The frequency of 92 days is justified in WCAP-10271-P-A, Supplement 2,

Rev.

1, June 1990.

This surveillance is modified by a Note that specifies testing when below P-6 and is clarified to address the transition from MODE 2 to MODE 3.

A transition into MODE 3 with the reactor trip breatect closed is often made for a short period of time during g.lant shutdown.

During a normal shutdown, the reactor trip breakers are opened shortly after entering MODE 3.

The transition time in MODE 3 from when the reactor trip breakers are closed to when they are opened is less than the time required to perform the CHANNEL FUNCTIONAL TEST prior to entering MODE 3.

Therefore, an allowance to enter MODE 3 without first performing the source range CHANNEL FUNCTIONAL TEST is warranted.

CHANNEL CALIBRATION l

The alternate source range detectors are modified by a note to indicate they are not subject to the source range detector surveillance requirements until they have been connected to the applicable circuits and are required to be OPERABLE.

This complies with the testing requirements for components that are required to be OPERABLE.

BEAVER VALLEY - UNIT 2 B 3/4 3-9 Amendment No.

L

NPF-73 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM AND ENGINRRnRn SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling.

The CHANNEL CALIBRATION for the - source range neutron detectors consists of obtaining the detector plateau and preamp discriminator

. curves, eval 2ating those

curves, and establishing detector operating conditions as directed by the detector manufacturer.

The 18 month frequency is based on the need to perform this surveillance under the conditions that apply during a plant outage since performance at power is not possible.

The protection and monitoring functions are also calibrated at an 18 month frequency as is normal for reactor protection instrument

' channels.

Operating experience.has shown these components usually

~

pass the surveillance when performed on the 18 month frequency.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that:

1) the radiation levels are continually measured in the areas served by the -individual channels; 2) the alarm or automatic ' action is in.ttiated - when the radiation level trip setpoint is exceeded; and 3)-sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

This capability is consistent with the recommendations of NUREG-0737,

" Clarification of TMI Action Plan Requirements," October, 1980.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.

The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

t For the purpose of measuring Fg(Z) or y"

a full incore flux map is g,

used.

Quarter-core flux maps, as defined in WCAP-8648, June 1976, may l

be'used in re-calibration of the excore neutron flux detection system, l

and full incore flux maps or symmetric incore thimbles may be used for monitoring-the Quadrant Power Tilt Ratio when one Power Range Channel is inoperable, j

i BEAVER VALLEY - UNIT 2 B 3/4 3-10 Amendment No.

l

NPF-73 3/4.3 INSTRUMENTATION BASES 3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available.to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the facility and is consistent with the recommendations of Regulatory Guide 1.12, " Instrumentation for Earthquakes."

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient. meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for _ initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs."

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that j

sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.

This capability is required in the event control room habitability is lost and is consistant with General Design Criteria 19 of 10 CFR 50.

3/4.3.3.6 (This Specification number is not asad).

3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that sufficient capability is available to promptly detect and initiate l

protective action in the event of an accidental chlorine release, l

This' capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, l

" Protection of Nuclear Power Plant Control Room Operators Against an

'~

Accidental Chlorine Release," January 1977.

i BEAVER VALLEY - UNIT 2 B 3/4 3-11 Amendment No.

l l

NPF-73 3/4.3 INSTRUMENTATION BASES 3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following. an accident.

This capability is consistent with the recommendations of Regulatory-Guide 1.97,

" Instrumentation for Light-Water-cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Tern Recommendations."

3/4.3.3.11 RYDLOSIVE GAS MONITORING INSTRUMENTATION' This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas holdup system.

The OPERABILITY and use of this I

. instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4.3.4 TURBINE OVERSPrun PROTECTION

)

This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging miss:iles which could impact and damage safety related components, equipment or structures.

l l

l J

BEAVER VALLEY - UNIT 2 B 3/4 3-12 Amendment No.

l t

j

ATTACHMENT B Channe Summary License Amendment Unit Reauest Typed Panes Editorial Channes 1

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3/43-2 No additional changes are included.

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3/4 3-10 No additional changes are included.

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i B 3/4 3-5 B 3/4 3-6 B 3/4 3-7 B 3/4 3-8 These pages were added due to shifting.

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ML20236S492

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