ML20114D112
| ML20114D112 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/18/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114D115 | List: |
| References | |
| NUDOCS 9209040157 | |
| Download: ML20114D112 (14) | |
Text
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?'.#)%i NUCLEAR REGULATORY COMMISSION F
UNITED STATES 3
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WASHINGTON D C. 20%$
NORTHERN STATES POWER COMPANY i
DOCKET NQ. 50-?63 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENS.E Amendment No. 83 License No. DPR-22 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amend.nent by Nor ern States Power Company (the licensee) dated February 14, 1992, 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 amendn.ent can be conducted withcut endangering the health and safety 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 an't 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 becn satisficd.
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 Operating License No. DPR-22 is hereby amended to read as follows:
4 WO@h C PDR P
4 lechnical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 83, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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e Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 18, 1992 l
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ATTACHMENT TO LICENSE AMENDMENT NO 83 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 psges.
The revised pages are identified by amendment number and contain marginal lines indicating tiie area of change.
REMOVE INSEPT 29 29 30 30 32 32 33 33 34 34 36 36 37 37 49 49 62 62 63a 63a 66 66 2
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1 TABLE 3.1.1 - CONTINUED t
Modes in which func-Total No. of Min No. Operable Lion must be Oper-Instrument or Operating Instru-Limiting able or Operating **
Channels per ment Channels Per Required Trip Function-Trip Settings Refuel (3) Startup Run Trip System Trip System (1)
Conditions
- 10.-Main Steamline
$ 10% Valve Isolation Valve Closure Closure X(b)
X(b)
X 8
8 A or C
- 11. Turbine Control Valve Fast Closure (See Note 7)
X(d.f) 2 2
D
- 12. Turbine Stop.
s~10% Valve Valve Closure Closure X(d) 4 4
D
?!OTES1 1.
There :: hall be two operable or tripped trip systems for each function. A channel may be placed in en 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.
i k
2.
For an IRM channel to be cons,idered operable, its detector shall be fully inserted.
3.
In the-refueling mode with the reactor subcritical and reactor water temperature less than 212'F, only the following trip functions need to be operable: (a) Mode Switch in Shutdown, (b) Manual Scrarn, (c) liigh Flux IRM, 3
(d)' Scrain Discharra Volume High Level.
7 1
i 4
Not required to be operable when primary containment integrity is not required.
S.
To be considered operable, an APRM must have at least 2 LPRM inputs per level and at least a total of 14 LPPJi i
inputs, except th.it channels 1, 2, 5, and 6 may lose all LPRM inputs from the companion APRM. Cabinet plus one additional LPRM input and still be considered operable.
29 3.1/4;1 kmimnt tb. 50, H, 81, 83,
L Table 3.1.1 - Continued 6.
Seven inches on the water level instrumentation is 10*6" above the top of the active fuel at rated powe.
7.
Trips upon loss of oil pressure to the acceleration relay.
8.
Limited trip setting refers to' the volume of water in the discharge volume raceiver tank and does not include the volume in the lines to the level switches.
9.
High reactor _ pressure is not required to be operable when the reactor vessel head is unbolted.
- Reautred Conditions when minimum conditions for operation are not satisfied.
A.
All operable control' rods fully inserted within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
B.
Power on IRM range or below and reactor in Startup, Refuel, or Shutdown mode.
C.
Reactor in Startup or Refuel mode and pressure below 600 psig.
D.
Reactor pover less than 45% (751.5 MWt.).
- Allowable Bvoass Conditions It is permissiblo to bypass:
The scran discharge volume High Water Level scram function in the refuel mode to allow reactor protection a.
system reset. A rod block shall be applied while the bypass is in effect.
b.
The Low condenser vacuum and MSIV closure scram functionin the Refuel and Startup modes if reactor 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% (751.5 MWt).
3.1/4.1 30 krnhnt tb.11, F0, 63, 83
TABLE 4.1.1 SCRAM INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREOUENCIES FOR SAFETY INSTRUMENTATION AND CONTROL CIRCUITS 4
INSTRUMENTATION CHANNEL FUNCTIONAL TFSI MINIMUM FREOUENCY (4) i m
liigh Reactor Pressure Trip Channel and Alarm Quarterly High Drywell Pressure Trip channel and Alarm Quarterly Low Reactor Water Level (2, 5)
Trip Channel and Alaru Quarterly High Water Level in Scram Discharge Volume Trip Channel and Alarm Quarterly Condenser Low Vac Trip Channel and Alarm Once each month Hain Steam Line Isolation valve Trip Channel and Alarm Quarterly Clo ure Turbine Stop Valve Closure Trip Channel and Alarm Quarterly Manual Scram Trip Channel and Alarm Veekly Turbine Control Valve Fast Closure Trip Channel and Alarc Quarterly.
i APRM/ Flow Reference (5)
Trip Output Relays Quarterly IRM (5)
Trip Channel and Alarm Note 3 I
J Mode Switch in Shutdown Plve raode switch in Each refueling outage shutdown 3.1/4.1 32 kmtv.t tb. 10, 63, 66, 81, 83 -
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i table 4.1.1 (Contirn2ed) i Note'l:
Deleted.
Note-2;
'A -sensor check shall be performed on low reactor water level once per day and on hig) i steam line radiation once per shift.
Note 3:
Perform functional test-prior to every startup, and demenstrate that i.he IRM and APRM channels. overlap at least 1/2 decade prior to every normal. shutdown.
Note 4:
Functional. tests are ter required when the. systems are not' required to be operable or i
are tripped.' If tests are missed, they shall be ' performed prior to returning the rystems..to an operable status.
i l.
Note 5:
'A functional rest of this' instrument means the injection of a simulated signal into the
' instrument (not primary sensor) to' verify the proper instnunent channel response, alarm, I
atxt/or. Initiating 'sction.
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i 3.1/4.1-33 kmimot fb. 63,81,83 l
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TABLE 4.1.2 SCRAM INSTRUMENT CALIBRATION MINIMUM CALI38p. TION FREOUENCIES FOR REACTOR PRorECTION INSTRUMENT CHANNELS INSTRUMENT Ci g gi, CROUP CALIBRATION MET 110D 111NIMUM FREOUENCY (2)
APRM B
Heat Bals.nce Once every 3 days (4) 1RM B
Heat Balance See Note I liigh Reactor Pressure A
Pressure Standard Every ? months liigh Drywell Pressure A
Pressure Standard Every 3 months Low Reactor Water B
Pressure Standard Every Operating Cycle -
Transmitter Every 3 months - Trip Unit High Water Level in Scram Discharge A or B Water Level Every 3 months Condenser Low Vacuun A
Vacuum Standard Every 3 months Main Steamline Isolation Valve Closure A
Observation Every Operating Cycle k
Turbine Control Valve Fast Closure A
Pressure Standard Every 3 months Turbine.Stop Valve Closure A
Observation Every Operating Cycle i
Recirculation Flow Meters &
Pressure Standard Every 3 months Flow Instrumentailon Notes:
1.
Perform calibration test during every starttip and normal shotdown, 2.
~ Calibration tests are nat required when the systems are net required to be operable or are tripped.
If tests are missed, they shall be performed prior to returning the systems to an operable status.
3.
(Deleted).
l 4.
This calibration is performed by taking a heat balance and adjusting the APRM to agree
.iith the heat balance. Alarms and trips will be verified and calibrated if necessary during functional testing.
- CROUPS:
A.
Passive type devices.
B.
Vacuum tube or semiconduct.or devices and detectors that drift or lose sensitivity.
3.1/4.1 34 kmimnt rc. 3,11, M, #, 83
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Bases Continued:
3.1 Threa APRM instrument channels are provided for each protection trip system. APRM's #1 and #3 operate contsets in one subchannel, and APRM's #2 and #3 operate concacts in the other subchannel.
APRM's #4, #5, and #6 are arranged similarly in the other protection trip system.
Each protection trip system has one more APRM than is necessary to meet the minimur number required. This silows the bypassing of one APRM per protection trip system. Additional IRM channels have also been provided l
to allow for bypassin5 of one such channel in each trip system.
~
The bases for the scram settings for the IRM, APRM, high reactor pressure, reactor low water 1cvel, turbine control valve fast closere, and turbine stop valve closure are discussed in Specifications 2.3 and 2.4 Instrumentetion.(pressure switches) in the drywell are provided to detect a loss of coolant eccident and initiate the emergency coce cooling equipoent. This instrumentation is a backup to the water level ~ instrumentation which is ditcussed in Specification 3.2.
The centrol rod drive scram system is designed so that all of the water which is discharged from tl.e reactor by the scram can be acecmmodated in the discharge piping.
Part of this piping consists of cwo instrument volumes which accommodate in excess of 56 gallons of water asch and is the low point in the piping.
During normal operation the discharge volumes are empty; however, should they fill with water, the water discharge to the piping from the reactor could not be accommodated which would result in slow scram times or partial or no control rod insertion. To preclude this oc'currence, level switches have been provided in the instrument-volumes which alarm and scram the reactor when the volume. of water in either_ of-the discharge volume receiver tanks reaches 56 gallons. At this point there is sufficient volume in the piping to accommodate the scram without impairment of the scram times or amount.of insertion of the control rods.
This function shats the reactor'down while sufficient volume remains to accommodate the discharged water and precludes the situation in which a scram would be required but not be able to perform its function adequately.
Loss of condenser vacuum occurs when the condenser can no longer handle the heat input.
Loss of 3.1 BASES 36 timeviout tb. If, 83
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Bases Continued:
3.1 condenser vacuum initiates a closure of the turbine stop valves and turbine bp ass valves which eliminates the heat input to tne condenser. C1csure of the turbine stop and bypass valves causes a 1 pressure transient,: neutron flux rise, and an increase in surface heat flux. To pievent the clad, safety limit.from being exceeded if thic occurs,-a reactor scram occurc on turbine stop valve closure. - The turbine step valve closure scrum function alone is adequate to prevent the clad safety Reference FSAR limit from.being exceeded in the event of a turbine trip transient without bypass Section 14.5.1.2.2 and supplemental.information submitted February 13, 1973. The condenser low vacuua scren -is a back-up to. the stop valve closure ; scram and causes a scram before the stop valves ere. closed md thus the resulting transient is less severe. Scram occurs at 23* Hg vacuum, stop valve closure occurs at 20* Hg vacuum, and bypass closure at 7* Hg vacuum.
The main steamilne isolation valve elesure scram is set to scram when the isolation valves are slot closed from full open.
This scram anticipates'the pressure and flux transient, which would occur when.the valves close..By scramming at this setting the resultant transient is insignificant.
Reference Section 14.5.1.3.1 FSAR and 'rupplemental information submitted February 13, 1973.
A reactor mode switch is provided which actuates or. bypasses the various scram functions appropriate to.the particular plant operating statu.s.
Reference Section 7.7.1 FSAR.
The manual.scras function-is active in all modes, thus providing for a manual means of rapidly inserting' control. rods durin5 all modes of reactor. operation.
The IRM system provides protection against excessive power levels and short reactor periods in the 37
~3.1 BASES Audent Pb. 83,
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Table 3.2.1 Instrumentation That Initiates Primary Containment Isolation Functions Hin. No. of Operable Total No. of Instru-or Operating lustru-ment Channels Per ment Char.nels Per Trip Required Function Trio Settines Trio Systere System (1.2)
Conditions
- l.
Main Steam and Recirc En.gole Lines (Group I) n.
Iow Low Reactor 26'-6" s6'10" 2
2 A
Water level b.
liigh Flow in Main s1409 rated 8
8 A
Steam Line c.
Iligh temp. in Main s200*r 8
2 of 4 in each A
Steam Line Tunnel of 2 sets d.
Iow Pressure in Main 2825 psig 2
2 B
Steam Line (3) 2.
R11R System, lleed Cooling, Drywell, Sump, TIP (Group 2) a.
Low Reactor Water
' 10' 6" above the 2
2 C
Level top of the active fuel i
i 3.2/4 2 49 kmhnt tb 83,
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l Table 4.2.1 - Continued Minimum Test and Calibration Fregaency For Core Cc,oling Rod Block and Isolation Instrumentation 1
Instrument Channel Test (3)
Caitbration (3)
Sensor Check (3) 3.
Steam Line Low Pressure once/3 months Once/3 months None l.
J 4
Peactor Low Low Water Level Onec/3 months (Note 5) Every Operating Cycle -
Once/ shift Transmitter once/3 months - Trip Unit CONTAINMENT IS01ATION (CFOUPS 2 & 3)
- ^
1.
Reactor Low' Water Ixvt 1 '(Note 10) 2.
Drywell High Pressure (Note 10) 1:PCI (CROUP 4) IS0!ATION t
1.
Steam Line liigh Flow Once/ month Once/3 months None 2.
Steam Line fligh Temperature Once/ month once/3 months None 4
RCIC (CROUP 5) ISOLATION 1.
Steam Line liigh Flow once/ month Once/3 months None 2.
Steam Line liigh Temperature once/ month once/3 months None i
REACTOR BUILDING _ VENTILATION l
I 1.
Radiation Monitors (Plenum) once/ month once/3 months once/ day l
'2. Radiation Monitors (Refueling Floor)
Once/ month Once/3 months Note 4 4
RECIRCUIATION PUMP TRIP AND ALTERNATE ROD INJECTION 1^
1.
Reactor High Pressure Once/ month (Note 5)
Once/ Operating Cycle.
Once/ Day Transmitter Once/3 Months-Trip Unit 2.
Reactor Low Low Water Level Once/ month (Note 5)
Once/ Operating Oycle-Once/ shift Transmitter Once/3 Months-Trip Unit SHUTDOWN COOLING $U_PfLY ISO)ATION 1.
Reactor Pressure Interlo':k once/mor.th once/3 Months None i
62 3.2/4.2 Amhnt 10. 22, E, 43, 63, 66, 74, Ef, 83 t.
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t Table 4.2.1 - Continued Minimum Test and Ca11braticn Frequency for Core Cooling, Rod Block and Isolation Instrumentation NOTES:
(1)
(Deleted)
(2)
Calibrate prior to normal shutdown and start-up and thereafter check once per shift had test once per week until no longer required. Calibration of this instrument prior to normal shutdown taeans adjustment of channel trips so that they correspond, within acceptable range and accuracy, to a simulated signal injected into the i
instrument (not primary sensor).
In addition. IRM gain adjustment will be performed, as necessary, in the APRM/IRH overlap region.
(3)
Functional tests, calibrations and sensor checks are not required when the sy:.tm 5 are not required to be t
operable or are tripped.
If tests are missed, they shall be performed prior to returning the systems to an operable status.
(4)
"Jhenever tuel inandling is in process, a sensor check shall be perform d once per shift.
(5)
A functional test of this instCument means the injection of a sinzulated signal into the in-trument (not primary sensor) to vi ify the prcper instnament channel response alarm and/or initiating action.
(6)
(Deleted)
(7)
(Deleted)
(8)
Once/ shutdown if not tested during previous 3 mo 4 : period.
(9)
Testing of the SRM Not-Full-In rod block is not required if the SRM detectors are secured in the full-in position.
(10) Uses contacts from scram system. Tcsted and calibrated in accordance with Tables 4.1.1 and 4.1.2.
3.2/4.2 634 kmhnt tb. 30,63,83, i
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b Bases Continued.
3.2 instrumentation is provided winich causes a trip of Croup 1 isolation valves. The primary ftuction of the instrumentation is to detect a break in the main ste unline. thus only Choup 1 valves sre closed.
For the worst esse accident, main steamline break outside-the drywell, this trip setting of 140% of rated steam flow in conjunction with the flow limiters and main steamline valve closure, limit the mass inventory loss such that fuel is not uncovered, fuel clad temperatures remain less than.1000*F and release of radioactivity to the environs is well below 10 CFR 100 guidelines.
r Reference Sections 14.6.5 FSAR.
Temperature monitoring instrumentation is provided in the main steamline tunnel to detect leaks in this area. Trips are provided on this instrumentation and when exceeded cause c?osure of Group 1 isolation valves.
Its setting of 200* F is low enough to detect leakc of the order of 5 to 10 gpm; thus, it is capable of covering the entire spectrum of breaks.
For large breaks, it is a back-up to high steam flow instrumentation discussed above, and for smalt breaks with the resvitant small release of radioactivity, gives isolation before the guidelines of 10 CFR 100 are exceeded.
Pressure instrumentation is provided which tripe when main steamline pressure drops below 825 psig.
A' trip of this instrumentation results in closure of Group 1 isolation valves.
In the
" refuel" and "Startup" moc2 this trip function is bypassed. Tnis function is provided primarily to provide protection against a. pressure regulator ualfunction which would cause the control and/or bypass valves to open. With the trip set at 825 psig' inventory loss is limited so that fuel is not uncovered and peak clad temperatures are much less than 1500*F; thus, there are no fission products available for release other than those in.the reactor water. Reference Licente Amendment Request Dated December 1,1975 from L. O. Mayer (NSP) to R. S. Boyd (USNRC).
3.2 BASES 66 Amtmt fb. 83,
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