ML20151U092
| ML20151U092 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/28/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151U097 | List: |
| References | |
| NUDOCS 8808180398 | |
| Download: ML20151U092 (8) | |
Text
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OfTROITEDISONCOMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.24 Licensa No. NPF-43 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated March 28, 1988, complies with the standards and requirements of the Atosite Energy Ac2 of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Cnapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules ar.ri regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment 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 amendment will not be inimical te +.he comon defense and security or to the health and safety of tna public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all appliubh requirements have been satisfied.
2.
.tecordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attactment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmen' cal Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.24, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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Thic license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION A~
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Martin J. Virgilio, Director Project Directorate 111-1 Division of Reactor Projects - III, IV, y
& Special Projects
Attachment:
Changes to the Technical 5pecifications Date of Issuance:
July 28, 1988 L
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e ATTACP. MENT TO LICENSE AMENDMENT NO. 24 FA';ILITY OPERATING LICENSE NO. NPF-a.3 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 docustent completeness.
REMOVE
_ INSERT 3/4 3-71 3/4 3-71 3/4 3-73 3/4 3-73 3/4 3-76 3/4 3-76 3/4 3-80 3/4 3-80 6-20 G-20 e
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INSTRUMENTATION f
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION I
3.3.7.11 The radioactive liquid offluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of Specification 3. u.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CH).
APPLICABILITY: At all times.
ACTION:
With a radioactive liquid effluent monitoring instrumentation channel a.
alarm / trip setpoint less conservative than required by the above specification, immediately suspend the releanc of radioactive liquid effluents monitored by the affected channel, or declare the channel i
i inoptrable, or change the setpoint so it is acceptably conservative.
l b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.
Restore the inoperable instrument. tion to OPERABLE status within 30 days and, if unsuccesstol, t.
lain why this inoperability was not corrected in a timely manner in the next Semiannual Radioactive Effluent Release Report.
1 lhe provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHE CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1.
?ERMI - UNIT 2 3/4 3-71 Amen h nt No. 24
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TABLE 3.3.7.11-1 (Continued)
_ TABLE NOTATIONS l
ACTION 110 -
With the number cf channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified individuals independently verify the release rate calculations tid discharge line valving; Otherwise, suspend release of radioactive affluents via this pathway.
ACTION 111 -
With the number of channels OPERABLE loss than required by the flinimum Channels OPERABLE requirement, efflusnt re' eases via this pathway may continue provided that grab samples are collected and analyzed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10 7 microcurie /m1, for Cs-137.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTICN 112 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least on:e per 4 hoeri during actual releases.
Pump perform-ance curves generated ta place may be used to est' mate flow.
Otherwise, suspend release of radioactive effluents via this pathway.
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FERMI - UNIT 2 3/4 3-73 Amendment No. 24 i
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6 TABLE 4.3.7.11-1 (Continued)
TABLE NOTATIONS 1
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alare/ trip setpoint.
2.
Circuit failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the fellowing conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failurt.
4.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using National Burea of Standards traceable sources.
These standards shall permit calibrating the system over the range of energy and measurement expected during normal operation and anticipated operational occurrences.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or 1
are National Bureau of Standards traceable shall be used.
(4) CHANNEL' CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on 1
dnys on which continuous, periodic, or batch releases are made.
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(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alars annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alara setpoint.
2.
Circuit failure.
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3.
Instrument indicates a downscale failure.
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FERMI - UMIT 2 1/4 3-75
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TABLE 3.3.7.12-1 (Continued)
A E
RADI0 ACTIVE GASEOUS EFFLUENT NONITORING INSTRUN g
INSTRUNENT MININUM CHANNELS Z
OPERABLE RADWRSTE RUILDING VENTILATION MONITORING _
APPLICA8ILITY 6.
ACTION SYSTEM Noble Gas Activity Monitor a.
1 b.
Iodine Sampler 121 1
Particulate Sampler 122 c.
1 d.
Sampler Flow Rate Monitor 122 1
7.
ONSITE STORAGE BUILDING VENTILATION 123
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EXHAUST RADIATION MONITOR Y
Noble Gas Activity Monitor a.
1 b.
Iodine Samoler 121 1
Particulate Sampler 122 c.
1 d.
Sampler Flow Rate Monitor 122 1
123 t
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ADMINISTRATIVE CONTROLS 3NNUALRADIOLOGICALENVIRONMENTALOPERATINGREPORT(Continued) the report, the report'shall be subeitted noting and explaining the reasons for the missing results.
If possible, the missing data shall be submitted as soon as possible in a Applementary report.
The reports shall also include the following:
a summary description of the radiological environmental monitoring program at least two legible maps
- cover-ing all sampling locations keyed to a table gIving distances and directions from the centerline of one reactor; the results of ifcensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations free the sampling schedule of Table 3.12.1-1 discussion of all analyses in which the LLD required by Table 4.12.1-1 was; not achievable.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT **
6.9.1.8 Routine Sealannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality.
The Semiannual Rattioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Seetannual Radioactive Effluent Release Report to h cubeltted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may wind direction, atmosphe;Ic stability, and precipitation (if m
,the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.***
radiation doses due to the radioactive liquid and gaseous affluents re from the unit or station during the previous calendac year.
T:its same report shall also include an assessment of the radiation doses from radioactive liquid
- 0ne map shall cover stations near the SITE SOUNDARY; a second shall include the more distant stations.
- A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station; however, for unMs with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
- In lieu of subetssion with the first half year Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
FERMI - UNIT 2 6-19 Amendment No. 11
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