ML20035D082
| ML20035D082 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/02/1993 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML20035D081 | List: |
| References | |
| NUDOCS 9304120117 | |
| Download: ML20035D082 (9) | |
Text
.
TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTI1 TION INSTRUMENTATION TABLE NOTATIONS When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
Required when ESF equipment is required to be OPERABLE.
(a)
When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Conditions and required ACTIONS may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function or the redundant function maintains ECCS initiation capability.
(b)
Also actuates the associated division diesel generator.
(c)
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
(d)
The injection function of Drywell Pressure High and Manual Initiation is not required to be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than level 8 setpoint coincident with the vessel pressure less than 600 psig because of hot calibration / cold t
operation level error.
(e)
Provides signal to close HPCb pump injection valve only.
I (f)
Provides signal to HPCS pump suction valves only.
ACTION i
ACTION 30 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:
a.
With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- or declare the associated l
l system inoperable.
b.
With more than one channel inoperable, declare the associated system inoperable.
ACTION 31 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel l
+
in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; restore l
the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.
The provisions of Specification 3.0.4 are not applicable.
NINE MILE POINT - UNIT 2 3/4 3-33 AMENDMENT NO.
9304120117 930402 PDR ADOCK 05000410 P
t TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 32 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> declare the l
associated ADS Trip System or ECCS inoperable.
t 4
ACTION 33 -
With the number of OPERABLE channels less than i
required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l ACTION 34 -
Not used.
ACTION 35 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ADS valve or ECCS inoperable.
ACTION 36 -
With the number of OPERABLE channels one less than
,~
required by the Minimum OPERABLE Channels per Trip Function requirement:
a.
For one Trip System, place that Trip System in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- or l
declare the HPCS system inoperable.
b.
For both Trip Systems, declare the HPCS system inoperable.
I With the number of OPERABLE channels less than ACTION 37 required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- or l declare the HPCS system inoperable.
ACTION 38 -
With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.
ACTION 39 -
With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> *;
operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.
The provisions of Specification 3.0.4 are not applicable.
NINE MILE POINT - UNIT 2 3/4 3-34 AMENDMENT NO.
3/4.3 INSTRUMENTATION BASES REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4.3.1 The reactor protection system (RPS) automatically initiates a reactor scram to:
r Preserve the integrity of the fuel cladding.
a.
Preserve the integrity of the reactor coolant system.
b.
Minimize the energy which must be adsorbed following a loss-c.
of-coolant accident, and d.
Prevent inadvertent criticality.
This specification provides the Limiting Conditions for Operation necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service because maintenance is being performed.
When necessary, one channel may be made inoperable for brief intervals to conduct required surveillance.
The reactor protection system is made up of two independent trip There are usually four channels to monitor each systems.
The parameter, and there are two channels in each trip system.
outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system.
The tripping The system of both trip systems will produce a reactor scram.
for nuclear power plant protection meets the intent of IEEE-279 Specified surveillance intervals and surveillance and systems.
maintenance outage times have been determined in accordance with
" Technical Specification Improvement Analyses for l
" Technical BWR Reactor Protection System," and MDE-78-0485, Specification Improvement Analysis for Nine Mile Point Nuclear Station, Unit 2."
The bases for the trip settings of the RPS are When a channel discussed in the bases for Specification 2.2.1.
is placed in an inoperable status solely for performance of required surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains RPS trip 4
capability.
The measurement of response time at the specified frequencies provides assurance that the protective functions associated with each channel are completed within the time limit assumed in the No credit was taken for those channels with safety analyses.
response times indicated as not applicable.
Response time may be i
demonstrated by any series of sequential, overlapping or total channel test measurement, provided such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either (1) inplace, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response times.
NINE MILE POINT - UNIT 2 B3/4 3-1 AMENDMENT NO.
INSTRUMENTATION BASES ISOLATION ACTUATION INSTRUMENTATION 3/4.3.2 This specification ensure the effectiveness of the instrumenta-tion used to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints and response times for When necessary, one channel isolation of the reactor systems.
may be inoperable for brief intervals to conduct requiredSpec surveillance.
and maintenance outage times have been determined in accoydance
" Technical Specification with NEDC-30851P-A, Supplement 2, Instrumentation Common to Improvement Analyses for BWR Isolatio.
" Technical 5
RPS and ECCS Instrumentation," and with NEDC-31677P-A, Specification Improvement Analyses for BWR Isolation Actuation When a channel is placed in an inoperable Instrumentation."
status solely for performance of required surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains primary containment isolation Some of the trip settings.may have tolerances explicitly stated where both the high and' low values are critical capability.
The setpoints of and may have a substantial effect on safety.
other instrr'antation, where only the high or low end of the uirect bearing on safety, are established at a level away from the normal operating range to prevent inadvertent setting has 2 j
actuation of the systems involved.
the FSAR Chapter 15 safety analysis does Except for the MSIVs, not address individual sensor response times or the response times of the logic systems to which the sensors are connected.it is a i
For AC-operated valves, lost and is restored by startup of the emergency diesel a time of 13 seconds is assumed generators.
In this event, In addition to the pipe break, before the valve starts to move.
the failure of the DC-operated valve is assumed; thus the signal is concurrent with the 13-second diesel delay (sensor response)The safety analysis considers an allowable inventory l
loss in each case which in turn determines the valve speed in startup.
2 It follows that checking conjunction with the 13-second delay.the valve speeds and the 13-sec emergency power will establish the response time for the isolation functions.
Operation with a trip set less conservative than its TripS on the basis that the difference between each Trip Setpoint and
)
1 the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analysis.
The Trip Sctpoint and Allowable Value also contain additional margin for instrument accuracy and calibration capability.
AMENDMENT NO. 13 NINE MILE POINT - UNIT 2 B3/4 3-2 i
e d
i
__ INSTRUMENTATION BASES t
EMERGENCY CORE COOLING SYSTEM ACTUATION 1
_3/4.3.3 i
is The emergency core cooling system actuation in f
to control.
accidents that are beyond the ability of the operator Trip This specification provides the OPERABILITY requiremen Setpoints, Although the the systems to provide the design protection.in some cases the same l
instruments are listed by system, instrument may be used to send
~
one system at the same time.
i i
Operation with a trip set less conservative than its Tr p t ble Setpoint but within its specified Allowable Value is accep a i t and on the basis that the difference between each Trip Setpo n i
the Allowable Value is an allowance for instrument dr ft i
The j
specifically allocated for each trip in the safety analys s.
in Trip Setpoint and Allowable Value also contain additional marg for instrument accuracy and calibration capability.
l The HPCS pump suction pressure-low represents an analytical feet at transfer level in the condensate storage tank of 14This is above the l
feet at minimum flow. feet at maximum flow and 2
1 maximum flow and 3.0 corresponding minimum tank level of 10.2 feet at minimum flow 2.9 it ce l
Specified surveillance intervals and surveillance and ma n enan EDC-30936P-l outage times have been determined in accordance with N(with
" Technical Specification Improvement Methodology, Parts 1 and Demonstration for BWR ECCS Actuation Instrumentation)" Te A,
the Emergency Core Cooling System Actuation Instrumentation for 2," and RE-026, l
When a channel is Nine Mile Point Nuclear Station, Unit 2."
i d
l placed in an inoperable status solely for performance of requ re entry into LCO and required ACTIONS may be provided the associated function or the redundant q
surveillances,
- delayed, function maintains ECCS initiation capability.
1 i
I AMENDMENT NO.
NINE MILE POINT - UNIT 2 B3/4 3-2a f
n
~
_ INSTRUMENTATION l
BASES RECIRCULATION PUMP TRIP ACTUATION INSTRUMENT 3/4.3.4 (Continued) between each Trip Setpoint and the Allowable Value is an h
allowance for instrument drift specifically allocated for,eacThe Trip Se d
trip in the safety analyses.
Value also contain additional margin for instrument accuracy an Specified surveillance intervals and i
d in calibration capability. surveillance and maintenance outage times ha accordance with GENE-770-06-1, d
Test Intervals and Allowed Out-Of-Service Times fo h
NRC D. Binz IV from C.
E.
(letter to R.
and documented in the SER When a channel is placed in an Rossi dated July 21, 1992).
inoperable status solely for performance of required 1
entry into LCO and required ACTIONS may be provided the associated function maintains EOC-RPT trip surveillances,
- delayed, capability.
f REACTOR CORE ISOLATION COOLING SYSTEM ACTUATIO 3/4.3.5 INSTRUMENTATION l
The reactor core isolation cooling system actuation instrumen-tation is provided to initiate actions to assure adequa l
t sink and the loss of feedwater flow to the reactor vessel.
Operation with a trip set less conservative than its Trip i
ble Setpoint but within its specified Allowable Value is a i
d the Allowable Value is an allowance for instrument drift The l
specifically allocated for each trip in the safety analyses.
i Trip Setpoint and Allowable Value also contain additional marg n Specified for instrument accuracy and calibration capability.
surveillance intervals and surveillance and maintenance outage times have been determined in accordance with GE 4
Allowed Out-Of-Service Times for Selected Instrumentation (BWR RCIC Instrumentation)," as Technical Specifications, (letter to G.
J.
approved by the NRC and documented in the SER Rossi dated September 13, 1991).
When a channel is placed in an inoperable status solely for performance ofen Beck from C.
E.
i' required surveillances,provided the associated function maintains RCIC f
be delayed, initiation capability.
The RCIC pump suction pressure-low represents i"
This is above the maximum flow and 2.53 feet at minimum flow. feet at maximum flow and corresponding minimum tank level of 5.02.5 feet at minimum AMENDMENT NO.
3 NINE MILE POINT - UNIT 2 B3/4 3-4 S
E
_ INSTRUMENTATION
~ BASES CONTROL ROD BLOCK INSTRUMENTATION 13/4.3.6 i h the The control rod block functions are provided consistent w t Control requirements of the specifications in Section 3/4.1.4, Power Distribution Rod Program Controls, and Section 3/4.2,The trip logic is arranged the inputs will result in a control rod block.
Limits.
i Operation with a trip set less conservative than its Tr p ble Setpoint but within its specified Allowable Value is a i
d ift the Allowable Value is an allowance for instrument dr The specifically allocated for each trip in the safety analyses.
i Trip Setpoint and Allowable Value also contain additional marg n Specified for instrument accuracy and calibration capability.
t surveillance intervals and surveillance and maintenance ou age times have been determined in accordance with NEDC
" Bases for Control Rod Block Instrumentation," and GENE-770-06-1, Suppl.
i Changes to Surveillance Test Intervals and Allowed Out-Of-Serv ce
" as Times for Selected Instrumentation Technical Specifications, (letter to R.
D.
approved by the NRC and documented in the SER When a channel is Binz IV from C. E. Rossi dated July 21, 1992).
i d
placed in an inoperable status solely for performance of requ re entry into LCO and required ACTIONS may be provided the associated function maintains Control Rod surveillances, The scram discharge volume water level-high
- delayed, Block capability.is referenced to a scram discharge volume instrument setpoint feet 10 inches.
zero level at elevation 263 MONITORING INSTRUMENTATION 3/4.3,7 RADIATION MONITORING INSTRUMENTATION 3/4.3.7.1 The OPERABILITY of the radiation monitoring instrumentat ensures that: (1)
(2) the alarm or in the areas served by the individual channels; i
automatic action is initiated when the radiation level Tr psufficient inform (3)
Setpoint is exceeded; andon selected plant parameters to monit variables following an accident. General Design Criteria (GDC) 19, 41, Appendix A, Specified surveillance intervals and with 10 CFR 50, in i
surveillance and maintenance outage times have been determined 60, 61, 63 and 64.
accordance with GENE-770-06-1, Test Intervals and Allowed Out-Of-Service Times D. Binz IV from C.
E.
(letter to R.
and documented in the SER When a channel is placed in an
)
Rossi dated July 21, 1992).
inoperable status solely for performance of requiredentry i delayed, provided the associated function maintains Control Room surveillances, Ventilation initiation capability.
AMENDMENT NO.
NINE MILE POINT - UNIT 2 B3/4 3-4a
e INSTRUMENTATION
,, BASES TURBINE OVERSPEED PROTECTION SYSTEM (Continued)
Protection will protect the turbine from excessive overspeed.
from excessive turbine overspeed is required since excessive overspeed could generate potentially damaging missil or structures.
PLANT SYSTEMS ACTUATION INSTRUMENTATION 3/4.3.9 (1) to The plant systems actuation instrumentation is provided:
to ensure in the event of feedwater controller failure and (2) the proper operation of the service water system during norma and accident conditions.
" Bases for been determined in accordance with GENE-770-06-1, Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specification," as (letter to R. D.
approved by the NRC and documented in the SER Binz IV from C. E. Rossi dated July 21, 1992).
When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LCO and required ACTIONS may be provided the associated function maintains Feedwater
- delayed, System / Main Turbine Trip System actuation capability.
AMENDMENT NO.
NINE MILE POINT - UNIT 2 B3/4 3-8 4
r
~
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE PAGE BASES FOR SECTIONS 3.0/4.0 B3/4 0-1 3/4.0 APPLICABILITY REACTIVITY CONTROL SYSTEMS 3.4.1 B3/4 1-1 3/4.1.1 SHUTDOWN MARGIN B3/4 1-1 3/4.1.2 REACTIVITY ANOMALIES B3/4 1-2 3/4.1.3 CONTROL RODS.
1 B3/4 1-3 CONTROL ROD PROGRAM CONTROLS 3/4.1.4 B3/4 1-4 STANDBY LIQUID CONTROL SYSTEM 3/4 1.5 POWER DISTRIBUTION LIMITS 3/4.2 B3/4 2-1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.
3/4.2.1 B3/4 2-1 3/4.2.2 APRM SETPOINTS BASES TABLE B3.2.1-1 SIGNIFICANT INPUT PARAMETERS TO B3/4 2-3 THE LOSS-OF-COOLANT ACCIDENT ANALYSIS B3/4 2-4 MINIMUM CRITICAL POWER RATIO.........
3/4.2.3 B3/4 2-4 LINEAR HEAT GENERATION RATE 3/4.2.4 3/4.3 INSTRUMENTATION B3/4 3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4.3.1 B3/4 3-2 ISOLATION ACTUATION INSTRUMENTATION 3/4.3.2 EMERGENCY CORE COOLING SYSTEM ACTUATION B3/4 3-2a l 3/4.3.3 INSTRUMENTATION.
RECIRCULATION PUMP TRIP ACTUATION B3/4 3-3 i
3/4.3.4 INSTRUMENTATION REACTOR CORE ISOLATION COOLING SYSTEM B3/4 3-4 3/4.3.5 ACTUATION INSTRUMENTATION B3/4 3-4a l CONTROL ROD BLOCK INSTRUMENTATION 3/4.3.6 xvi AMENDMENT NO. 17 NINE MILE POINT - UNIT 2
,