ML20043F102
| ML20043F102 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/05/1990 |
| From: | Pierson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043F103 | List: |
| References | |
| NUDOCS 9006140165 | |
| Download: ML20043F102 (8) | |
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- UNITED STATES NUCLEAR REGULATORY COMMISSION i
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WASHINGTON, D C. 20666
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-@RTHERNSTATESPOWERCOMPANY DOCKET NO. 50-263-110NTICELLO NUCLEAR GENERATING PLANT AMENDMENT T0-FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-22 l
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company.
(the licensee) dated March 28, 1990, complies with the standards and
,.E requirements of the Atomic Energy Act of 1954, as amended (the Act).-
and the Comission8s rules and regulations set forth in 10 CFR 1
p Chapter I; L
.B.
- The facility will operate in conformity with the application, the provisions of the.Act, and the rules and regulations of the Comission; w
D C.
There'isreasonableassurance'(i)thattheactivitiesauthorized by this amenament can be conducted without endangering the health and safety of the-public, and (ii) that such activities will be conducted in compliance with the Comission's regulations;
~D..
The issuance of this amer.dment will not-be inimical to the comon
< 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.
-r 2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicateri in the attachment to this license amendment, and gara-graph 2.C.2 of Facility' Operating License No. DPR-22 is hereby amended to read as follows:
9006140165 900603 DR ADOCK 05000263 PDC a[
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4 Technical Specifications-The>Technica1' Specifications contained in Appendix A, as' revised' through Amendment No. 74, 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 the date-of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-(-
u Robert C. Pierson, Acting. Director.
Project Directorate III-1 Division of Reactor Projects - III,:
IV, V & Special Projects Office of Nuclear Reactor Regulation Attachmenti
, Changes to the Technical 1 Specifications Date of Issuance: June 5, 1990.
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'c't ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. OPR-22 9
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 contain marginal lines indicating the area of change..
REMOVE INSERT 59 59 62 62 68 68-198-1 198-1 198y 198y
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Tcblo 3.2.4 Instrumentaticn Thdt Initiatos Rasctor Building V;ntliction Ics1ction'
. And Standby Gas Treatment System Initiation v
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... z; Min. No. of Operable j;
Total: No. of Instru-or' Operating:Instrumentz l.
ment Channels Per Trip Channels Per Trip Required l
Function Trip Settings System System-(Notes 1, 2)
- Conditions * -
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- 1. ' lev Reactor Vater
>10'6"~above 2-2 A. or B; Level (Not'e 3) the top :of ' the.
. active fuel.
2.
liigh Drywell Pres-
$2 psig 2
2 A. or B.
sure ~(Note 3) o i
3.
R? actor' Building.
$100 mR/hr 1
'.1 (Note 4)
- A. or B..
Plenum Radiation Monitors 4
Refueling Floor
$100 mR/hr 1
1 (Note 4)'
A. or B.
Radiation Monitors i
Notes:
(1) There shall be two operable or tripped trip systems for each function with two instrument channels per trip
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system and there shall be one operable 'or tripped trip system for each function with one instrument channel
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per trip system.
i (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:
i (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-
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(4) One of the two monitors may be bypassed for maintenance and/or testing.
- 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 gonditions where secondary containment is not required.
t 3.2/4.2 59 4.
Amendment No. M,74 K:
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Table 4.2.1-- Continued Minimum Test and Calibration' Frequency For Core Cooling
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Rod Block and Isolation Instrumentation
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" Instrument Channel Test'(3)
Calibration (3)
SensorCheck(3)[
3.
Steam Line Low Pressure Once/ month Once/3 months None
- 4.
-Steam Line High Radiation Once/wcek.(Note 5) Note 6' Once/ shift
- CONTATNNENT TSOIATION (CROUPS 2 & 3) 1.
Reactor-Low Water Level (Note 10)
- 2.
Drywell' High Pressure (Note :10)
IIPCI (CROUP 4) ISOIATION
'1.
Steam Line High Flow.
Once/ month Once/3 months.
None 2.
Steam Line High Temperature Once/ month Once/3 months None RCIC (CROUP 5) ISOIATION 1.
Steam Line High Flow Once/ month Once/3 months None 2.
Steam Line High Temperature
-Once/ month Once/3 months None REACTOR BUTI. DING VENTTIATION 1.
Radiation Monitors (Plenum)
_Once/ month Once/3 months Once/ day 2.
Radiation Nonitors (Refueling Floor)
Once/ month Once/3 months Note 4 4
RECIRCUIATION PUNP TRIP AND ALTERNATE ROD INJECTION I
1.
Reactor High Pressure
-Once/ month (Note 5) Once/ Operating Cycle-Once/ Day l
s 3
Transmitter Once/3 Nonths-Trip Unit 2.
Reactor Low imw Water level Once/ month-(Note.5) Once/ Operating Cycle-Once/ shift-Transmitter-Once/3 Nonths-Trip Unit SHUTDOWN COOLING SUPPLY ISOIATION 4
1.
Reactor Pressure Interlock Once/ month Once/3 Nonths None 3.2/4.2 62
- Amendment No. 72,$p.45,$3,$9,74-r-
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. Bases Continu-dr
~3.2. The RBH bypass time delay -is set low enough. to assure minimum rod movement while upscale trips are bypassed.
The IRM rod block function provides local as well as gross core protection. The' scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level. Analysis of the worst case accident results in rod block action before MCPR approaches the Safety Limit (T.S.2.1.A).
A downscale indication of an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough.
In either case the instrument will not respond to changes in control rod" motion and thus control rod motion is prevented. The downscale red blocks assure that there will be proper overlre between the neutron monitoring systems' and thus, that adequate coverage is provided-j for all ranges of reactor operation. The downscale trips are set at 3/125 of full scale.
For effective emergency core cooling for the small pipe break the HPCI or Automatic Pressure Relief 1
system must function since for these breaks, reactor pressure does not decrease rapidly enough to allow either core spray or LPCI to operate in time.
The arrangement of the tripping contacts is such as to provide this' function when necessary and minimize spurious operation. The trip settings given in the specification are adequate to assure the above criteria is met.
Reference Section 6.2.4 and 6.'!.6 FSAR. The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e.,
only one instrument channel out of service.
Four radiation monitors (two reactor building vent plenum and two refueling floor) are provided which initiate isolation of the reactor building and operation of the standby gas treatment system following a
- l, refueling accident. The monitors measure radioactivity in the reactor building ventilation exhaust and on the refueling floor. One upscale trip signal or two downscale/ inoperable trip signals, from a pair of monitors performing the same function,-will cause the desired action. Trip settings of 100 'mR/hr for the reactor building vent plenum monitors and the refueling floor. monitors are based upon. initiating normal ventilation isolation and standby gas treatment system cperation so that none of the activity released during the refueling accident leaves the reactor. building via the normal ventilation stack but that all l
the activity is processed by the standby gas treatment system.
l The recirculation pump trip description and performance analysis is discussed in Topical Report NEDO-25016, September 1976, ' Evaluation of Anticipated Transients Uithout Scram for the Monticello Nuclear Generating Plant".
(See September 15, 1976' letter from Mr L 0 Mayer, NSP, to Mr D L Ziemann, USNRC.) The pump trip is provided to minimize reactor pressure in the highly unlikely event of a plant transiene coincident with the failure of all control rods to scram. The rapid flow reduction q
3.2 BASES 68 Amendment No. U,(p 59,74 I
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TABLE 3.8.2
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~ RADI0 ACTIVE GASEOUS EF1117ENT MONITORING INSTRUNENTATION (Page 2 of 2)
..m Minimum Channels
. Instrument l Operable Applicability Action if Minimum Channels not Operable' lc Reactor Building Vent (includes Turbine Building
'6 Radwaste Building. releases) l Wide Range Noble Gas Activity 1
At all times Releases via this pathway may continue for up
- Monitors **
to 30 days provided grab samples are taken and-analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
1 Iodine Sampler Cartridge 1
At all times Releases via the pathway may continue for up to 30 days'provided within 8~ hours samples are continuously
-collected with auxiliary sampling equipment as required by Table 4.8.4.
Particulate Sampler Cartridge 1
At all times Releases via the pathway may continue for up to.30-days providad within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> samples are continuously
- collected with auxiliary jampling equipment as required by Table 4.8.4.
Duct Flow Monitors 1
At all times Releases via.this pathway may continue for up to 30 days provided the flow rate.is estimated at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Sample Flow Instruments 1
At all times Releases via this pathway may continue for up to 30 days.provided.the flow rate is l
t estimated at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
j Notes:
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- - Indicates number of channels required per operating recombiner train.
- Provides automatic termination of offgas treatment system releases.
- - Provides control room indication prior to exceeding 10CFR Part.20 release limits.
3.8/4.8 198-1 Amendment No. J5,(p,74
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3.8'and 4.8 Bases:-(continued)
Specification 3.8.B.4.c is provided to ensure that the concentration of potentially explosive gas mixtures contained in the compressed storage subsystem..is maintained below the fleemability limits of hydrogen and oxygen..
Automatic control features are-included in'the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits.. Maintaining the concentration of hydrogen below the flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the require-'
ments of General. Design Criterion 60 of Appendix A to 10 CFR Part 50.
Specification 3.8.B.4.e is provided to limit the radioactivity which can be stored in one decay tank. Restricting-the quantity of radioactivity contained in each gas storage tank provides assurance that in the event. of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the site A4 restricted area boundary will not exceed 20 mrem. A flow restrictor in the discharge line of the decay tanks' prevents a tank form being discharged'st an uncontrolled: rate.
In additicn, interlocks prevent the contents of a _
tank from being released with less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of holdup.
Specification 3.8.B.5 establishes a maximum activity at the steam Jet air ejector. Restricting the gross radio-activity rate of noble gases form the main condenser provides reasonable assurance that the total body exposure to' an individual at the restricted area. boundary will not exceed the limits of 10 CFR Part 20 in the event this effluent is inadvertently discharged directly to the envirorument with minimal treatment. 'This specification implements the requirements of General Design Criteria 60 and 64 of Appenc'.1x A to 10 CFR Part 50.
Specification 3.8.B.6 requires the~contairunent to be purged and vented through the standby gas treatment system-except during inerting and deinerting operations. This provides for lodine and particulate removal'from the contairument atmosphere. During outages when the' containment is opened.for snaintenance, the containment ventilation exhaust is directed to the monitored reactor building vent.
Use of the 2-inch flow path prevents damage to the standby gss treatment system in the event of a loss of coolant accident during purging'or venting. Use of the reactor building plenum and vent flow path for inerting and deinerting operations permits the control room i
operators to monitor the activity level of the resulting effluent by use of the Reactor Building Vent Vide
.4 Range Cas Monitors.
In the event that the reactor building release rate exceeds the Reactor Building Vent Wide Range Cas Monitor alarm settings, the monitors will alarm in the control room alerting the operators
- i to take actions to limit the release of gaseous radioactive effluents. The alarm settings for the reactor building vent wide range gas monitors are calculated in accordance with the NRC approved methods in the
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ODCN to ensure that alarms will alert control room operators prior to the limits of specification 3.8.B.1 being exceeded.
C.
Solid Radioactive Umste Specification 3.8.C.1 provides assurance that the solid radwaste system will *oe used whenever solid radwastes require processing and packaging prior to being shipped offsite. This specification implements the
- i requirements of 10 W R Part 50.36a and General. Design Criteria 60 of Appendix A to 10 CFR Part 50.
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3.8/4.8 BASES 198y Amendment No. M,Jp,AS,74 l
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