ML20245D577
| ML20245D577 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 08/19/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151X494 | List: |
| References | |
| NUDOCS 8808250381 | |
| Download: ML20245D577 (7) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION
<t WASHINGTON.D.C 206S5 DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVL INCORPORATED DOCKET NO._ 5_0_ _3_4_1 f_ERMI_2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No NPF-43 1.
The Nuclear Regulatory Conn.ission (the Ccir.ission) has found that:
A.
The application fer avendnent by the Detrait Edison Cortpany (the licensee)datedNovember 30, 1987, corrplies with the standards and requirements of the Aton.ic Energy Act cf 1954, as arrended (the Act),
and the Cuntnission's rules and regulations set forth in 10 CFR Chapter I; D.
The facility will operate in ccnfomity with the application, the provisions of the Act, and the rules and regulations of the Contrissf or.;
C.
There is reasonable assurance (1) that the activities authorized by this anendirent can be condectu' without tr.dangering the health and safety of the public, ar.c (ii) that such activities will be conducted in compliar.ce with the Conrnission's regulations; D.
The issuance of this arrendnent will nct be iniinical to the correron defense and security or to the hielth and safety of toe public; and E.
The issuance pf this arnend: rent is in accordance with 10 CFR Part 51 of the Con 4nissior'$ <egulations and all applicable requireinents we beer, satisfied.
2.
Accordingly, tne license is ainended by changes to the Technical Specifica-tions as indicated in the attachment to this license arrendirent and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follews:
Technical Specifications at:d Envimnrental Protection Plan The Technical Specifications contained in Appendix A, as revised through Anendrtent No.28. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. DECO shall operate the Tecility in accordance with the Technical Specifications and the Ens 'ronrnental Protection Plan.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COINISSION Marti J. Vi io, D rector Projec Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 19, 1988 I
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, ATTACHMENT TO LICENSE AMENDMENT NO.28 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.-
REMOVE INSERT 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 B 3/4 3-4 8 3/4 3-4 l
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TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION MINIMUM APPLICABLE g
REQUIRED NUMBER CHANNELS OPERATIONAL q
INSTRUMENT OF CHANNELS OPERABLE CONDITIONS ACTION
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1.
Reactor Vessel Pressure 2
1 1, 2 80 2.
Reactor Vessel Water Level, Fuel Zone 2
1 1, 2 80 3.
Suppression Chamber Water Level 2
1 1, 2 80 4.
Suppression Chamber Water Temperature 2
1 1, 2 80 5.
Suppression Chamber Air Temperature 2
1 1, 2 80 6.
Suppression Chamber Press::re 2
1 1, 2 60 y
7.
Drywell Pressure, Wide Range 2
1 1, 2 80 8.
Drywell Air Temperature 2
1 1, 2 80 l
9.
Drywell Oxygen Concentration ***
2 1
1, 2 80
- 10. Drywell Hydrogen Concentration 2
1 1, 2 80 11.
Safety / Relief Valve Position Indicators 1*/ valve 1*/ valve 1, 2 80 12.
Containment High Range Radiation Monitor 2
2 1,2,3 81 g
- 13. Standby Gas Treatment System Radiation Monitors **
2 2
1,2,3 81 l
14.
Neutron Flux 2
1 1, 2 80 5
15.
Drywell Sump Level 2
1 1, 2 80 16.
Primary Containment Isolation Valve Position 1/ valve 1/ valve 1, 2, 3 80 u
- Pressure switch
- High (accident) range noble gas monitors (One channel per flow path) l
- See Special Test Exception 3.10.5
TABLE 3.3.7.5-1 (Continued)
ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 -
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Ch6nnels OPERt.BLE requirements of Table 3.3.7.5-1, restore the inoperable channeis ) to s
OPERABLE status within 4B hours or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 81 -
With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, initiate the preplanned alternate method of monitoritg the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
1) either restore the inoperable channel (s) to OPERABLE status within 7 days of the event, or 2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
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FERMI - UNIT 2 3/4 3-62 Amendment No. 28
INSTRUMENTATION BASES 3/4.3.4 ATVS RECIRCULATION PUMP TRIP SYSTEM ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient.
The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NE00-10349, dated March 1971, NE00-24222, dated December 1979, and Appendix 158.8 cf the FSAR.
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the lifference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.
i Operation with a trip set less conservative than its Trip Setpoint but within itt, specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits.
The trip logic is arranged so that a trip in any one of the inputs will result in a control rod block.
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to tr less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual chanr.11s; (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, 64.
i FERMI - UNIT 2 8 3/4 3-3
INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3.4.3.7.2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that suf-ficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capa-bility is required to permit comparison of the measured response to that used in the design basis for the unit.
This instrumentation is consistent with the recom-mendations of Regulatory Guide 1.12, "Instrumentation for Earthquakes," April 1974.
3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data are available for estimating potential radia-tion doses to the public as a result of routine or accidental release of radio-active materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
This instrumentation is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February, 1972.
3/4.3.7.4 REMOTE SHUTOOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutoown monitoring instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the contiol room.
This capability is required in the event control room habitability is lost and is con;istent with General Design Criterion 19 of 10 CFP. Part 50, 3/4.3.7.5 ACCIDENT MONITORING IhSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.
This capability is con-sistent with the recommendaticns of Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assest Plant Conditions During and Following an Accident," December 1975 and NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980.
The multiple noble gas monitors installed on each division of the Standby Gas Treatment System provide the necessary monitoring capabilities to assure that the normal and extended monitoring ranges required by NUREG-0737 and Regulatory Guide 1.97 are met.
3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.
At these power levels, reactivity additions shall not be made without this flux level information available to the operator.
When the inter-mediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe systea with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.
The TIP system OPERABILITY is demonstrated by normalizing all probes (i.e.,
detectors) prior to performing an LPRM calibration function.
Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may no~t be required to be OPERABLE.
The OPERABILITY of individual detectors to be used for monitoring is demonstrrted by comparing the detector (s) output with data obtained durin0 the previous LPRM calibration.
FERMI - UNIT 2 B 3/4 3-4 Amendment No. 28
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