ML20138K706
| ML20138K706 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/07/1997 |
| From: | NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO. |
| To: | |
| Shared Package | |
| ML20138K690 | List: |
| References | |
| NUDOCS 9702190097 | |
| Download: ML20138K706 (14) | |
Text
-
Docket No. 50-245 B16136
)
4 l
i 1
I Millstone Nuclear Power Station, Unit No.1 l
Proposed Technical Specifications Revision Response Time Testing Marked-up Version of Current Technical Specifications l
February 1997 NO DO OR i
P l
August 28, 1995 g/g/,g 1.0 DEFINITIONS
)
i The succeeding frequently used terms are explicitly defined so that a
{
sniform interpretation of the Specifications may be achieved.
i A.
Deleted j
B.
core Alterattena i
i CORE ALTERATIONS shall be the movement of any fuel, sources.
reactivity control components, or other components affecting i.
reactivity within the reactor vessel with tis vessel head removed and fuel in the vessel. Movement of source range monitors, local
{
power range monitors, intermediate range monitors, traversing incore probes, or s replacement)pecial movable detectors (including undervassel l
is not considered a CORE ALTERATION.
j Suspension of CORE ALTERATIONS shall not preclur',e. completion of movement of a component to a safe position.
j
. C.
Hot Standhv i
l HOT STANDBY means operation with the reactor critical, system l
pressure less than 600 psig, and the main steam isolation valves closed.
D.
Immediate IMMEDIATE men.ns that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.
ggg/ c e E.
Inshument talibrahon Wdle IWA An IN UMENT CALIBRA DN means th adjustment an instrument signal tput so that
- correspond within acc table range, accuracy d response t'
, to a kno value(s)ll e; ompass the o the parameter which the trument moni rs. Calibr ion sha entire instr nt includin actuation, a rs or trip.
F.
trument Fune anal Test An UMENT FUNC ONAL TEST se s the injec on of a si sted signa into the inst unent primar ensor to ve fy the pro r instr tchannelregonse, alarm, nd/orinitia ng action.
G.
Instrument check An INSTRUMENT CHECK is qualitative determination of operability by observation of behavior during operation. This deterstnation shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
Millstone Unit 1
. 3-1 Amendment No. M, 86 mm
- _ y W
\\"
SkSen7
/
i l
l E.
Instrument er channel calibration An INSTRUMENT or CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the i
necessary range and accuracy to known values of the parameter that i
the channel monitors. The INSTRUMENT or CHANNEL CALIBRATION shall i
encompass those components, such as sensors, alarms, displays, and trip functions required to perform the specified safety I
function (s). Yhe INSTRUMENT or CHANNEL CALIBRATION shall include l-the INSTRUMENT or CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative j
assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The INSTRUMENT or l
CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.
F.
Instrument er channel Functional Test I
An INSTRUMENT or CHANNEL FUNCTIONAL TEST shall be the injection of a i
simulated or actua', signal into the channel as close to the sensor l
as.pra:.ticable to verify 0PERABILITY, including all components in the chtsal, such as alarms, interlocks, displays, and trip i
The INSTRUMENT or CHANNEL FUNCTIONAL TEST may be perfor functions, required to perform the specified safety function means l
of any series of sequential, overlapping, or total channel steps so that, the entire channel ir %sted.
i i
i 3
i 1
IyfVtb,eyry i
Juns 11, 1951 00.' Sueolemental Reload Licensina $'ubmittal 1
TheSUPPLEMENTAl.RELOADLICENSINGSUBMITTAL(SRLS),itssupplements e
and revisions, are unit and cycle specific document (s containing
)
the power distribution limits (MCPR, LNGR, and APLHGR for the current operating cycle. The limits in the SRLS, inc uding supple-ments and revisions, are only applicable during the reload / cycle number (s)giveninthetitle. These cycle specific limits shall be detemined for each reload cycle in accordance with Specification 6.g.l.g.
~
l i
PP. Avernoe Planar Linear Heat Generation Rate lAPLHGR) i The AVERAGE PLANAR LINEAR 3T GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the j
fuel rods in the specified bundle at the specified height, divided l
by the number of fuel rods in the fuel bundle at that height.
j QQ. Linear Heat Generation Rate (LHGR)
The LINEAR HEAT GENERATION RATE (LHGR) shall be applicable to a specific rod at a specific height and is equal to the heat genera-i l
tion rate per unit length for the specific rod at that specific height.
j RR. Limitina Control Rod Pattern 7
A LIMTjNG CONTROL R00 PATTERN is a control rod configuration which d
resuii.i in the core being an a themal hydraulic limit, i.e.,
operating on a limiting value for APLHGR, LHGR, or MCPR.
[
l j
k i
0 ld j
$5. Reactor Protection System (RPS) Loaic Response Time The RPS LOGIC RESPONSE TIME hall be that time interval from the j
opening of the sensor contact up to and including the de-energization of the scram pilot valve solenoids.
[
i
(
)
I Millstone Unit 1 1-8 AmendmentNo.)(.54 i
i
Iy Q' y
i OCT 31 BB6 l
LIMITING CONDITION FOR OPERATION 3.1 REACTOR PROTECTION SYSTEM l
Applicabilit'y:
~
}
... Applies to.the instrumentation and associated. devices which initiate a reactor i
scram and provide automatic isolation of the Reactor Protection Systes. buses j
40s their power supplies.
l dbjective:
f To assure the operability of the Reactor Protection System.
Specification:
l A.
The setpoints, minimum number of trip systems, and minimum number of f
instrument channels that must be operable for each position of the reactor mode switch shall be as given in Table 3.1.1.
8.
Lewr.ee Tin t.
NOT U S 8D, i
j
- Tim i.in fre;. in'tf etter Of : y :5::::1 tM p S th: d; ;r.;rgi::ti;n :f a
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th; ;c.
spienoiE. Ge, ;h:11 ::t :need 50 en1':::: d:. L i
C.
Reactor Protection System Fower Monitorina
{
Two kPS electric power monitoring channels for each inservice RPS MG set, j
or alternate power supply, shall be operable at all times except as follows:
)
1.
With one RPS electric power monitoring channel for an inservice i
RPS MG set or alternate power supply inoperable, restore the inoperable 1
channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RP5 MG set or alternate power supply from service.
2.
With both RPS electric power monitoring channels for an inservice RPS MG set or alternate power supply inoperable, restore at least one to CPERABLE status within 30 minutes or remove the associated RPS MG set or alternate power supply from service.
SURVEILLANCE REQUIREMENT 4.1 REACTOR PROTECTION SYSTEM 4
Applicability:
Applies to the surveillance of the instrumentation and associated devices which initiate reactor scram and provide automatic isolation of reactor protection system buses from their power supplies.
(
Millstone Unit 1 3/4 1-1
WYO aew r W
i OCT si 1SB6 '
i EURVE!LLANCE REQUIREMENT (Continued)
)
4.1 REACTOR PROTECTION SYSTEM Ohlective:
I To specify the type and frequency of surveillance to be applied to the i
reacter protection instrumentatten.
i
$secifiestion:
A A.
Instrumentation syst s 41 he functionally teste calibrated as indicated in Tables 1.
and 4.1.2. respectively.
gg i
B.
Daily during reactor power operation, the maximum fraction of limiting power density shall be checked and the APRM ceras and red block settings given by the equations in specifications 2.1.2A and 2.1.28 shall be i
j determined to be valid.
C.
The RPS electri:a1 protection assemblies shall be determined operable as follows:
1.
At least once per 6 months by perfomance of a CHANNEL FUNCTIONAL j
TEST, and 2.
At least once per 18 months by demonstrating the OPERABILITY of ever-voltage, under-voltage and under-frequency protective
)
instrumentation by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping i
logic and output circuit breakers, and verifying the following l
setpoints:
a.
Over-voltage 5 (132)VAC, i
b.
Under-voltage 3 (108)VAC, c.
Under-frequency 3 (57)Hz, and i
d:
Time-delay 5 (4.0) seconds.
D.
When the roastor made evitch is in RfipfL pr SHUT 00 Wit and fuel is in the g~
reactor vessel, no trip functions are required to be operable provided j
that all control rods are fully inserted, and either electrically or i
hydraulically disarmed. Thereafter, daily serve 111ance shall be performed to verify that all control rods remain valved out er electrically disamed.
j Verify the RPS LOGIL,
RESPONSE TIME for ea'ch' trip function listed blosis withTiiTim'its at I
least once every 0PERATING CYCLE.
1.
APRN: Flow Stased High Flux 2.
High Reactor Pressurc 3.
High Orywell Pressure 4.
Reactor Low Water Lev 61 5.
Main Stena Line Isolatich Valve Closure 6.
Turbine Control Valve Fast closure i
Turbine stop Valve Millstone Unit 1 3/4 1-2
b l'.
u/4/94 4,1 REACTOR PROTECTION SYSTEM 007 31 1986 i
SASES l'
Group (C) devices are active only during a given portion of the operational cycle. For example, the IRM is active during startup and inactive durine i
full-power operation. Thus, the only test that is meaningful is the one j
perfomed just prior to shutdown or startup; 1.e., the tests that are perfomed just prior to use of the instrument. While included in Group (C),
l the Condenser Low Vacuum trip is treated differently. This is because j
the condenser low vacuum trip sensor can only be tested during shutdown.
i The primary function of this trip is to protect the turbine and condenser, l
although it is connected into the reactor protection system; thus testing j
the sensor at each refueling outage is adequate.
Calibration frequency of the instrument channels is 1Hvided into two groups.
l These are as follows:
a.
Passive type indicating devices that can be compared with like units
~
i on a continuous basis.
b.
Vacuum tube or semiconductor devices and detectors that drift or i
lose sensitivity.
i l
Experience with passive type instruments in generating stations and substations indicates that the specified calibrations are adequate.
For i
i those d' ices which employ amplifiers, etc., drift specifications call for i
drift tc, be less than 0.4%/ month; i.e., in the period of a month a drift i
h of 0.4% would occur thus providing for adequate margin.
For the APRM i-system, drift of electronic apparatus.is not the only consideration in l
determining a calibration frequency.
Change in power distribution and loss of chamber sensitivity dictate a calibration every seven days.
j j
Calibration on this freque,ncy assures plant operation at or below thermal M*
rZNSERT I
B.
The peak heat flux shall be checked once per day to determine if the APRM scram requires adjustment. This will normally be done by checking i
the LPRM readings. Only a small number of control rods are moved daily, i
thus the peaking factors are not expected to change significantly and a l
daily check of the peak heat flux is adequate.
%w l
IThe RPS LOGIC RESPONSE TIME surveillance ensures that the logic response time is less than or equal to the value assumed in the safety analyses. The logic response time is measured from the opening of the sensor contact up to and including the opening of the trip actuator contacts (de-energization of the SCRAM pilot valve solenoids). The RPS LOGIC RESPONSE TIME acceptance criterion is 50 millise'conds. RPS LOGIC RESP 0EE TIME tests are conducted jf at least every OPERATING CYCLE. This frequency is consistent with the j
Millstone refueling cycle and is based upon plant operating experience, ji which shows that random failures of instrumentation components causing 1
serious response time degradation, but not channel failure, are extre:aely j.
unlikely.
Millstone Unit 1 B 3/4 1-9 i
4 i
Docket No. 50-241 B16136 1
i l
e i
Millstone Nuclear Power Station, Unit No.1 Proposed Technical Specifications Revision l
Response Time Testing Retyped Technical Specifications February 1997 L-
.l. 0 DEFINITIONS l
.The succeeding frequently used tares are explicitly defined so that i
a uniform interpretation of the Specifications may be achieved.
I a
A.
Deleted J
B.
CORE ALTERATIONS shall be the movement of any fuel, sources, reactivity control components, or other components affecting j
reactivity within the reactor vessel with the vessel head removed 4
and fuel in the vessel. Movement of source range monitors, local i
m r range monitors, intermediate range monitors, traversing incore l
probes, or special movable detectors (including undervessel j
replacement) is not considered a CORE ALTERATION.
4 l
Suspension of CORE ALTERATIONS shall not preclude completion of 1
movement of a component to a safe position.
C.
Hot Standby H0T STAND 8Y means operation with the reactor critical, system pressure less than 600 psig, and the main steam isolation valves closed.
D.
Immediate IfMEDIATE means that the required action will be initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.
1 E.
Instr-:t or Channel Calibration An INSTRUMENT or CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it res>onds within the necessary range and accuracy to known values of tse parameter that the channel monitors. The INSTRUMENT or CHANNEL CALIBRATION shall encompass those components, such as sensors, alarms, displays, and trip functions, required to perform the spacified safety function (s). The INSTRUMENT or CHANNEL CALIBRATION shall include the INSTRUNENT or CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The INSTRUMENT or CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.
F.
Instr-nt or Channel Functional Test An INSTRUMENT or CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILIT's, including all components in the channel, such as alarms, interlocks, displays, and trip Ni11 stone Unit 1 1-1 Amendment No. pp, pp, one
.1. 0 DEFINITIONS (continued)
F.
Instrument or Channel Fonctional Test (cont'd) functions, required to perform the specified safety function (s).
The INSTRUMENT or CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
G.
Instrument Check An INSTRUMENT CHECK is qualitative determination of operability by observation of behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
Millstone Unit 1 1-la Amendment No. 77, pp, 0248 J
4 4
4 l
- 00. Supplemental Reload Licensino Submittal The SUPPLEMENTAL RELOAD LICENSING SUBMITTAL (SRLS), its supplements and revisions, are unit and cycle specific document (s) containing l
. the power distribution limits (MCPR, LHGR, and APLHGR) for the current o prating cycle.
The limits in the SRLS, including supple-l monts and revisions, are only applicable during the reload / cycle number (s) given in the title.
These cycle specific limits shall be detemined for each reload cycle in accordance with Specification 6.g.l.9.
j PP. Averaae Planar Linear Heat Generation Rate (APLHGR)
The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be j
applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the l
fuel rods in the specified bundle at the.specified height, divided by the number of fuel rods in the fuel bundle at that height.
l QQ.
Linear Heat Generation Rate (LHGR)
)
The LINEAR HEAT GENERATION RATE (LHGR) shall be applicable to a specific rod at a specific height and is equal to the heat genera-tion rate per unit length for the specific rod at that specific height.
j RR.
Limitina Control Rod Pattern A LIMITING CONTROL R00 PATTERN is a control rod configuration which results in the core being on a thermal hydraulic limit, i.e.,
operating on a limiting value for APLHGR, LHGR, or MCPR.
l SS. Reactor Protection System (RPS) Loaic Response Time i
The RPS LOGIC RESPONSE TIME shall be that time interval from the l
opening of the sensor contact up to and including the i
de-energization of the scram pilot valve solenoids.
Nilistone Unit 1 1-8 Amendment No. U M,
aue i
-. - ~, - -
8j*,
L 1
LIMITING CONDITION FOR OPERATION i
1 l"
3.1 REACTOR PROTECTION SYSTEN Annlicability Applies to the instrumentation and associated devices which initiate a reactor scram and provide automatic isolation of the Reactor Protection System buses j
from their power supplies.
l Ob.iective:
To assure the operability of the Reactor Protection System.
Specification:
A.
The setpoints, minimum number of trip systems, and minimum number of instrument channels that must be operable for each position of the reactor mode switch shall be as given in Table 3.1.1.
B.
NOT USED.
l C.
Reactor Protection System Power Monitorina Two'RPS electric power monitoring channels for each inservice RPS MG set, or alternate power supply, shall be operable at all times except as follows:
1.
With one RPS electric power monitoring channel for an inservice RPS NG set or alternate power supply inoperable, restore the inoperable
- ianiel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove tiie associated US % set or alternate power supply from service.
2.
With both RPS electric power monitoring channels for an inservice RPS NG set or alternate power supply inoperable, restore at least one to OPERABLE status within 30 minutes or remove the associated RPS MG set or alternate power supply from service.
SURVEILLANCE REQUIREMENT 4.1 REACTOR PROTECTION SYSTEM Acolicability:
A plies to the survaillance of the instrumentation and associated devices wiich initiate reactor scram and provide automatic isolation of reactor protection system buses from their power supplies.
N111 stone Unit 1 3/4 1-1 Amendment No.
0260
SURVEILLANCE REQU3REMENTS (Continued) 4.1 REACTOR PROTECTION SYSTEM Obiective:
To specify the type and frequency of surveillance to be applied to the reactor protection instrumentation.
Specification:
A.
Instrumentation systems shall be functionally tested and calibrated as indicated in Tables 4.1.1 and 4.1.2, respectively. Verify the RPS LOGIC RESPONSE TIME for each trip function listed below is within limits at least once every OPERATING CYCLE.
i 1.
APRM: Flow Biased High Flux 2.
High Reactor Pressure 3.
High Drywell Pressure 4.
Reactor Low Water Level l
5.
Main Steam Line Isolation Valve Closure 6.
Turbine Control Valve Fast Closure l
7.
Turbine Stop Valve i
B.
Daily during reactor power operation, the maximum fraction of limiting i
power density shall be checked and the APRM scram and rod block settings given by the equations in Specifications 2.1.2A and 2.1.2B shall be determined to be valid.
4 l
C.
The RPS electrical protection assemblies shall be determined operable as follows:
1.
At least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST, and 2.
At least once per 18 months by demonstrating the OPERABILITY of over-voltage, under-voltage and under-frequency protective instrumentation by performance of a CHANNEL CALIBRATION including simulated automatic actuation of the protective relays, tripping logic and output circuit breakers, and verifying the following setpoints:
a.
Over-voltage 1 (132)VAC, b.
Under-voltage 2,(108)VAC, c.
Under-frequency > (57)Hz, and d.
Time-delay 1 (4.I) seconds.
D.
When the reactor mode switch is in REFUEL or SHUTDOWN and fuel is in the reactor vessel, no trip functions are required to be operable provided that all control rods are fully inserted, and either electrically or hydraulically disarmed. Thereafter, daily surveillance shall be performed to verify that all control' rods remain valved out or electrically disarmed.
i Millstone Unit 1 3/4 1-2 Amendment No.
i
]
j.
i l
4.1 AEACTOR PROTECTION SYSTEM i
l BASES Group (C) devices are active only during a given portion of the operational l
cycle.
For example, the IRM is active during startup and inactive during j
full-power operation. Thus, the only test that is meaningful is the one performed just prior to shutdown or startup; i.e., the tests that are performed just prior to use of the instrument. While included in Group (C),
j the Condenser Low Vacuum trip is treated differently. This is because the condenser low vacuum trip sensor clin only be tested during shutdown.
j The primary function of this trip is to protect the turbine and condenser, although it is connected into the reactor protection system; thus testing the sensor at each refueling outage is adequate.
Calibration frequency of the instrument channels is divided into two groups.
l These are as follows:
a.
Passive type indicating devices that can be compared with like units l
on a continuous basis.
b.
Vacuum tube or semiconductor devices and detes. tors that drift or
[
lose sensitivity.
J l
j Experience with passive type instruments in generating stations and substations indicates that the specified calibrations are adequate.
For i
i those devices which employ amplifiers, etc., drift specifications call for i
drift to be less than 0.4%/ month; i.e., in the period of a month a drift
{
of 0.4% would occur thus providing for adequate margin.
For the APRM i
system, drift of electronic apparatus is not the only consideration in determining a calibration frequency. Change in power distribution and loss of chamber sensitivity dictate a calibration every seven days.
Calibration on this frequency assures plant operation at or below thermal l
limits.
The RPS LOGIC RESPONSE TIME surveillance ensures that the logic response i
time is less than or equal to the value assumed in the safety analyses. The logic response time is measured from the opening of the sensor contact up to i
and including the opening of the trip actuator contacts (de-energization of i
l the SCRAM pilot valve solenoids). The RPS LOGIC RESPONSE TIME acceptance criterion is 50 millisecor.ds. RPS LOGIC RESPONSE TIME tests are conducted at least every OPERATING CYCLE. This frequency is consistent with the Millstone refueling cycle and is based upon plant operating experience, which shows that random failures of instrumentation components causing i
serious response time degradation, but not channel failure, are extremely unlikely.
B.
The peak heat flux shall be checked once per day to determine if the APRM scram requires adjustment. This will normally be done by checking the LPRM readings. Only a small number of control rods are moved daily, thus the peaking factors are not expected to change significantly and a daily check of the peak heat flux is adequate.
Millstone Unit 1 B 3/4 1-9 Amendment No.
0251 b