ML20198M362
| ML20198M362 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/23/1998 |
| From: | Lyon C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198M366 | List: |
| References | |
| NUDOCS 9901050319 | |
| Download: ML20198M362 (18) | |
Text
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k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30856-0001 49.....,o I
NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. DPR-22 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 5,1995, as supplemented October 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
)
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and cafety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility l
Operating License No. DPR-22 is hereby amended to read as follows:
l 9901050319 981223 i
PDR ADOCK 05000263 l
P PDR
.1
j.'
i.
.2 Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 103
, are hereby incorporated in the license. The licensee shall operate the -
facility in accordance with the Technicai Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation i
within 30 days.
I FOR THE NUCLEAR REGULATORY COMMISSION cgaL F.
i Carl F. Lyon, Project Manager l
Project Directorate lll-1 Division of Reactor Projects - Ill/lV Office of Nuclear Reactor Regulation l
i
Attachment:
Changes to the Technical Specifications i
i l
Date of Issuance: recember 23, 1998 l
l I
ATTACHMENT TO LICENSE AMENDMENT NO.103 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and i
contain vertical lines indicating the areas of change.
REMOVE INSERT 30 30 32 32 33 33 42 42 50 50 51 51 52 52 53 53 54 54 55 55 59 59 59a 1
60d 60d 61 61 62 62 l
no-w
-A
Table 3.1.1 - Continued 6.
Deleted.
7.
Trips upon loss of oil pressure to the acceleration relay.
8.
Limited trip setting refers to the volume of water in tho discharge volume receiver tank and does not include the volume in the lines to i
the level switches.
i 9.
High reactor pressure is not required to be operable when the reactor vessel head is unbolted.
l l
- Reauired Conditiu6s when minimum conditions for Osmaiicn are not saiid=d. fref. 3.1.B) l l
l t
A.
All operable cor. trol rods fully inserted.
i B.
Power on IRM range or below and reactor in Startup, Refuel, or Shutdown mode.
l C.
Reactor in Startup or Refuel mode and pressure below 600 psig.
D.
Reactor power less than 45% (738.75 MWt.).
- Allowable Bvoass Conditions 7
It is permissible to bypass:
a.
The scram discharge volume High Water Level scram function in the refuel mode to allow reactor protection system reset. A rod block shall be apphed while the bypass is in effect.
b.
The Low Condenser vacuum and MSIV closure scram function in the Refuel and Startup modes if teactor pressure is below 600 psig.
i c.
Deleted.
d.
The turbine stop valve closure and fast control valve closure scram functions when the reactor thermal power is s 45%
(798.75 MWt).
3.1/4.1 30 Amendment No. 44,50,63,83, Me, 103 i
~.. '
TABLE 4.1.1 L
SCRAM INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCulTS INSTRUMENTATION CHANNEL FUNCTIONAL TEEI MINIMUM FREQUENCY (4)
High Reactor Pressure Trip Channel and Alarm Quarterly
.j High Drywell Pressure Trip Channel and Alarm Quarterly 1
.. Quarterly l
t Low Reactor Water Level (2,5)
Trip Channel and Alarm High Water Level in Scram Discharge Volume Trip Channel and Alarm Quarterly 4
i Condenser Low Vac Trip Channel and Alarm
.Once each month
{
Main Steam Line Isolation Valve Closure Trip Channel and Alarm Quarterly -
[
Turbine Stop Valve Closure Trip Channel and Alarm Quarterly Manual Scram Trip Channel and Alarm Weekly f
Turbine ControlValve Fast Closure Trip Channel and Alarm Quarterly APRM/ Flow Reference (5)
Trip Output Relays Quarterly IRM (5)
Trip Channel and Alarm Note 3 Mode Switch in Shutdown Place mode switch in Every Operating Cycle l
f shutdown i
I l
i i
32 i
3.1/4.1 Amendment No. 40, 63,66, St. 68 103 i
f
9 TABLE 4.1.1 (Continued)
Note 1:
Deleted.
Note 2:
A sensor check shall be performed on low reactor water level once per day.
l Note 3:
Perform functional test prior to every startup, and demonstrate that the IRM and APRM channels overlap at least 1/2 decade prior to every normal shutdown.
t Note 4:
Functional tests are not required when the systems are not required to be operable or are tripped, if tests are missed, they shall be performed prior to retuming the systems to an operable status.
i Note 5:
A functional test of this instrument means the injection of a simulated signal into the instrument (not primary sensor) to verify the proper instrument channel response, alarm, and/or initiating action.
P l
33 3.1/4.1 Amendment No. 63, St.43, 103
l
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Bases 4.1:
The instrumentation in this section will be functionally tested and calibrated at regularly scheduled intervals. Spec:fic surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P, " Technical Specification improvement Analysis for BWR Reactor Protection System," as approved by the NRC and documented in the SER dated July 15,1987 (letter to T A Pickens from A Thadani).
Calibration frequency of the instrument channelis divided into two groups as defined on Table 4.1.2.
Experience with passive type instruments indicates that a yearly calibration is adequate. Where possible, however, quarterly i
calibration is performed. For those devices which employ amplifiers etc., drift sWretivns call for drift to be less than 0 5%/ month; l l
i.e., in the period of a month a drift of 0.5% would occur and thus provide for adequate margin. For the APRM system, drift of electronic apparatus is not the only consideration in determining a calibration frequency. Change in power distribution and loss of chamber sensitivty dictate a calibration every three days. Calibration on this frequency assures plant operation at or below thermal limits.
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i 42 4.1 BASES NEXT PAGE IS 45 Amendment No. 63,84, $00a i
103 6
Table 3.2.1 (Continued)
~
Min. No. of Operable or Operating instru-Total No. of Instrument ment Channels Required Function Trip Settings Channels Per Trip System Per Trip System (1,2)
Conditions b.
High Drywell Pressure (5) s2 psig 2
2 D
- l 3.
Reactor Cleanuo System (Grouo 3) a.
Low Reactor Water Level 27' (annulus) 2 2
E b.
High Drywell Pressure s 2 psig 2
2 E
4.
HPCI Steam Lines (Group 4) g a.
HPCI High Steam Flow s150,000 lb/hr 2(4) 2 F
with s60 second time delay b.
HPCI High Steam Flow s300,000 lb/hr 2(4) 2 F
c.
HPCI Steam Line Area High s 200*F 16(4) 16 F
Temp.
S.
RCIC Steam Lines (Group 5)
[
a.
RCIC High Steam Flow s 45,000 lb/hr with 2(4) 2 G
l 5
2 see time delay b.
RCIC Steam Line Area s 200*F 16(4) 16 G
6.
Shutdown Coolina Sug>ly Isolation a.
Reactor Pressure Interlock s75 psig 2(4) 2 C
at the reactor steam dome
)
3.2/42 50 Amendment No. 24,22,37,102 103
_m..
y-Table 3.2.1 (Continued)
NOTES:
(1)
There shall be two operable or tripped trip systems for each function. A channel (a shared channel is considered one channel) may l-be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.
(2)
Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated as follows:
6 (a) With one required instrument channel inoperable in one or more trip functions, place the inoperable channel (s) or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (b) With more than one instrument channel inoperable for one or more trip functions, immediately satisfy the requirements by
[
placing appropnate channels or systems in the tripped condition, or i
(c) Place the plant under the specified required conditions using normal operating procedures.
i.
l (3)
Low pressure in main steam line only need to be available in the RUN position.
(4)
All instrument channeis are shared by both trip systems.
(5)
May be bypassed when necessary only by closing the manual containment isolation valves dtring purging for containment inerting
}
or de-inerting. Venfication of the bypass condition shall be noted in the control room log. Also, need not be opemble when primary containment integrity is not required.
t i
Required conditions when minimum conditions for operation are not satisfied.
l A.
Group 1 isolation valves closed.
B.
Reactor Power on IRM range or below and reactor in startup, refuel, or shutdown mode.
C.
Isolation Valves closed for: Shutdown Cooling System, and Reactor Head Cooling Line.
D.
Comply with Condition C. above.
[
E.
Isolation Valves closed for: Reactor Cleanup System.
l F.
HPCI steam line isolated. (See specification 3.5 for additional requirements.)
l G.
RCIC steam line isolated.
i s
i 3.2/4.2 51 l
Amendment No. 84,90, 103
. m m
m
i Table 3.2.2 r
instrumentatKm That initiates Fmergency Core Cooling Systems Minimum No'. of Minimum No. of Oper-Operable or Total No. of Instru-able or Opere'ing Operating Trip ment Channels Per Instrument Channels Required Function Trip Setting Systems (3) (6)
Trip System Per Trip System (3) (6)
Conditions
- l A.
Core Sorav and LPCI i
1.
Pump Start j
- a. Low Low Reactor 2 6'6" s 6'10' 2
4(M) 4
' A.
Water Level and
- b. i. Reactor Low 2450 psig 2
2(4) 2 A.
Pressure Permissive or ii. Reactor Low 20 1 min 2
1 1
B.
Pressure Permissive Bypass 'Umer
- c. High Drywell s2 psig 2
4(4) 4 A.
Pressure (1) l I
2.
Low Reactor Pressure 2450 psig I
2 2(4) 2 A.
(Valve Permissive) 2 2(2)
~2 A.
3.
Loss of Auxiliary Power L
i 3.2/4.2 52 Amendment No. 62,43, 103
.c t
Table 3.2.2 -
Instrumentation That Initiates Emergency Core Cooling Systems Minimum No. of Minimum No. of Oper-Operable or Total No. of Instru-able or Operating
[
Operating Trio ment Channels Per Instrument Channels Required Function Trip Setting Systems (3) (6)
Trip System Per Trip System (3) (6)
Conditions
- l B.
HPCI System t
1.
High Drywell Pressure s2 psig 1
4 4
A.
(1) t i
2.
Low-Low Reactor Water 2 6'6" s 6'10" 1
4 4
A.
[
Level C.
Aviviietic Deoressurization 1.
Low-Low Reactor Water a 6' 6" s 6' 10" 2
2 2
B.
[
Level and 2,
Auto Blowdown Timer s 120 sin.viids 2
1 1
B.
and i
3.
Low Pressure Core 260 psig 2
12(4) 12(4)
B.
- t Cooling Pumps s150 psig Discharge Pressure interlock I
+
t 4
t i
3.2/4.2 53
' Amendment No. 62,93,102, 103 I
i m
Table 3.2.2 - (Continued) l Instrumentation That initiates Emergency Core Cooling Systems Minimum No. of Min. No. of Oper-.
Operable or Total No. of Instru-able or Operating Operating Trip ment Channels Per Instrument Channels Required Function Trip Setting Systems (3) (6)
Trip System Per Trip System (3) (6)
Conditions
- l r
D.
Diesel Generalrx 1.
Degraded or Loss of Voltage Essential Bus (5) 2.
Low Low Reactor Water 2 6'6' s 6'10" 2
4(4) 4 C.
Level l
3.
High Drywell Press s2 psig 2
4(4) 4 C.
t NOTES; 1.
High drywell pressure may be bypacsed when necessary only by closing the manual containment isolation valves during purging for containment inerting or de-inerting. Verificat;cn of the bypass condition shall be noted in the control room log. Also need not be operable when primary containment integrity is not required.
2.
One instrument channel is a circuit breaker contact and the other is an undervoltage relay.
3.2/4.2 54 Amendment No. 3.-93, 103
Table 3.2.2 - Continued Notes:
3.
Upon discovery that minimum requirements for the number of operable or operating trip systems, or instrument channels are not satisfied action shall be initi 3ted as follows:
(a) With one required instrument channel inoperabia per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or (b) With more than one instnament channel per trip system inoperable, immediately satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (c) Place the plant under the specified required conditions using normal operating procedures.
4.
All instrument channels are shared by both trip systems.
5.
See table 3.2.6.
6.
A channel (a shared channel is considered one channel) may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.
Required conditions when minimum conditions for operation are not satisfied.
A.
Comply with Specification 3.5.A.
B.
Reactor pressure s150 psig.
C.
Comply with Specification 3.9.B.
3.2/4.2 55 Amendment No. 3,93, 103
Table 3.2.4 Instrumentation That Initiates Reactor Building Ventilation Isolation And Standby Gas Treatment System initiation Min. No. of Operable Total No. of Instru-or Operating instrument.
~
ment Channels Per Channels Per Trip Required Function Trip Settings Trip System System Conditions
- 1.
Low Low Reactor Water 2:6*-6*, s 6'-10" 2
2 (Notes 1,3,5,6)
A. or B.-
l Level 2.
High Drywell Pressure s2 psig 2
2 (Notes 1,3,5,6)
A. or B.
3.
Reactor Building Plenum s100 mR/hr 1
1 (Notes 1,2,4)
A. or B.
Radiation Monitors 4.
Refueling Floor Radiation s100 mR/hr 1
1 (Notes 1,2,4)
A. or B.
Monitors Notes-(1)
There shall be two operable or tripped trip systems for each function with two instrument channels per trip system and there shall be one operable or tripped trip system for each function with one instrument channel per trip system.
(2)
Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated to:
(a) Satisfy the requirements by placing appropriate channels or systems in the tripped condition, or (b) Place the plant under the specified required conditions using normal operating procedures.
(3)
Need not be operable when primary containment integrity is not required.
(4)
One of the two monitors may be bypassed for maintenance and/or testing.
3.2/4.2 59 Amendment No.40,74,% 103
Notes: (cont'd)
(S)
Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated as follows:
(a) With one required instrument channel inoperable peer trip function, place the inoperable channel or trip sptem in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or I
(b) With more than one instrument channel trip system inoperable, immediately satisfy the requirements by placing appropnate channels or systems in the tripped condition, or
~
j (c) Place the plant under the specified required conditions using normel operating procedures.
i (6)
A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other OPERABLE channel in the same trip system is monitoring that parameter.
j Required Conditions when minimum conditions for operation are not satisfied.
A.
The reactor building ventilation system isolated and the standby gas treatment system operating.
B.
Establish conditions where secondary containment is not required.
s 3.2/4.2 59a Amendment No.103 4
Table 3.2.8 Other instrumentation Minimum No. of Minimum No. of Operable or Oper-Total No. of instru.
Operable or Operating ating ment Channels Per Instrument Channels Required Function Trip Setting Trip System (1) (2)
Trip System Per Trip System (1) (2)
Conditions
- l A.
RCIC Initiation 1.
Low-Low Reactor Level 2 6'6" & s 6'10" 1
4 4
B l,
above top of active fuel l
B.
HPCl/RCIC Turbine Shutdown a.
High Reactor Level s 14' 6" above 1
2 2
A top of active fuel C.
HPCl/RCIC Turbine Suction Transfer a.
Condensate Storage 22' 0" above tank 1
2 2
C Tank Low Level bottom NOTE:
1.
Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied, action shall be initiated as follows:
a.
With one required instrument channel inoperable per trip function, place the inoperable channel or trip system in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or b.
With more than one instrument channel per trip system inoperable, immediately satisfy the requirements by placing the appropriate channels or systems in the tripped condition, or c.
Place the plant under the specified required condition using normal operating procedures.
^
2.
A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition provided that at least one other operable channel in the same trip system is monitoring that parameter.
Roquired conditions when minimum conditions for operation are not satisfied:
A.
Comply with Specification 3.5.A.
l B.
Comply with Specification 3.5.D.
C.
Align HPCI and RCIC suction to the suppression pool. Restore channel; 'o operable status within 30 days or place the plant in Required Condition A for HPCI, or B for RCIC.
l 3.2/4.2 60d Amendment No. 37,98, 103
O,,
t
. Table 4.2.1 i
Minimum Test and Calibration Frequency for Core Cooling, l
Rod Block and Isolation Instrumentation instrument Channel fest (3) -
Calibration (3)
Sensor Check (3) t ECCS INSTRUMENTATION i
1.
Reactor Low-Low Water Level Once/3 months (Note 5)
Every Operating Cycle -Transmdter l
Once/3 months -Trip Unit Once/ Shift 2.
Drywell High Pressure Once/3 months Once/3 months None l
g 3.
Reactor Low Pressure (Pump Start)
Once/3 months Once/3 months None 1
4.
Reactor Low Pressure (Volve Once/3 months Once/3 months None Permissive) i' 5.
Undervoltage Emergency Bus Refueling Outage Refueling Outage None 6.
Low Presses Core Cooling Pumps Once/3 months Once/3 months None l
Dist.harge Pressure Interlock 7.
Loss of Auxiliary Power Refuelrg Outage Refueling Outage None l'
8.
Condensate Storage Tank Level Refuehng Outage Refueling Outage None 9.
Reactor High Water Level Once/3 months (Nots 5)
Every Operating Cyc!a -Transmitter l
Every 3 months - Trip Unit Once/ Ship.
BQD BLOCKS l
1.
APRM Downscale Once/3 months (Note 5)
Once/3 months None 2.
APRM Flow Variable Once/3 months (Note 5)
Once/3 months None I
i 3.
IRM Upscale Notes (2.5)
Note 2 Note 2 i
4.
IRM Downscale Notes (2,5)
Note 2 Note 2 -
l
{
5.
RBM Upscale Once/3 months (Note 5)
Once/3 months None 6.
RBM Downscale Once/3 months (Note 5)
Once/3 months None 7.
SRM Upscale Notes (2,5)
Note 2 Note 2 l
8.
SRM Detector Not-Full-In Position Notes (2,9)
Note 2
.None 9.
Scram Discharge Volume-High Level Once/3 months Refueling Outago None MAIN SEAM LINE fGROUP 1) ISOtATION 1.
Steam Tunnel High Temperature Refueling Outage Refueling Outage None 2.
Steam Une High Flow Once/3 months Once/3 Months Once/ Shift 3.2/4.2 61 t
Amendment No. 3,44,37,39,63,66,84-t 103 i
4 Table 4.2.1-Gontinued Minimum Test and Calibration Frequency for Core Cooling, Rod Block and Isolation Instrumentation l
Instrument Channel Test (3)
Galibration (3)
Sensor Check (3) 3.
Steam Line Low Pressure Once/3 months Once/3 months.
None 4.
Reactor Low Low Water Level Once/3 months (Note 5)
Every Operating Cycle-Transmitter Once/ shift Once/3 Months-Trip Unit CONTAINMENT ISOLATION fGROUPS 2 & a}
1.
Reactor Low Water Level (Note 10) 2.
Drywell High Pressure (Note 10) i 11PCI (GRGUP 4) ISOLATION 1.
Steam Uoo High Flow Once/3 months Orce/3 month's None i
2.
Steam Line High Temperature Once/3 months Once/3 months None s
RCIC (GROUP 5) ISOLATION 1.
Steam Line High Flow Oncs/3 months Once/3 months None 2.
Steam Line High Temperature Once/3 months Once/3 months None REACTOR BUILDING VENTILATION & STANDBY GAS TREATMENT 1.
Reactor Low Low Water Level Once/3 months (Note 5)
Every Operating Cycle - Transmitter Once/ shift Once/3 months - Trip Unit 2.
Drywell High Pressure (Note 10) 7 3.
Radiation Monitors (P!enum)
Once/3 months Once/3 months Once/ day 4.
Radiation Monitors (Refueling Floor)
Once/3 months Once/3 months Note 4 RECIRCULATION PUMP TRIP AND ALTERNATE ROD INJECTION 1.
Reactor High Pressure Once/3 months (Note 5)
Once/ Operating Cycie-Transmitter Once/ Day g
Once/3 Months-Trip Unit 2.
Reactor Low Low Water Level Once/3 months (Note 5)
Once/ Operating Cycle-Transmitter Once/ shift Once!3 Months-Trip Unit SHUTDOWN COOLING SUPPLY ISOLATION
[
1.
Reactor Pressure interlock Once/3 morths Once/3 Months None l
t 3.2/4 2 62 Amendment No. 74,84,83, 94, 103 i
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