ML20006C616
| ML20006C616 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/31/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006C604 | List: |
| References | |
| NUDOCS 9002080292 | |
| Download: ML20006C616 (5) | |
Text
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E'+[ noti %j UNITED STATES -
NUCLEAR REGULATORY COMMISSION o
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_0MAHA PUBLIC POWER DISTRICT' DOCKET NO. 50-285' FORT CALHOUN STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE
- Amendment No.124 License No. DPR c 1..
The _ Nuclear Regulatory Conrission (the Connission) has found that:
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The application for'amendrent by the Jmaha Public Power District L
(thelicensee)datedDecember1,1989,complieswiththe L
standards and requirements of the Atomic Energy.Act cf 1954, as L
.ar.jended (the Act), and the Comissior.'s rules and regulations set
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y forth in 10 CFR Chapter I; i
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The facility will operate in conformity with the application, as.
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amended,Lthe provisions of the Act, and the rules and regulations of the Connission;-
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There. is reasonable. assuranc.e:
(i)thattheactivitiesauthorized 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 license 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 ir, accordance with 10 CFR Part 51
'of the Commission's-regulations and all applicable requirements have been satisfied.
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'Accordingly, Facility Operating License No. DPR-40 is amended by changes-to the Technical Specifications as indicated in the attachnent to this =
license amendment, and paragraph 3.B. of Facility Operating License No.
0 DPR-40 is hereby amended to read as follows:
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Technical Specifications i
.The Technical Specifications contained in Appendix A, as revised through Amendrent No.124
, are here!)y incorporated in'the license. The licensee shall operate the facility in accordance with the' Technical Specifications.
3.
The license amendment is effective as of its date of. issuance.
F FOR THE NUCLEAR REGULATORY COMMISSION l
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Frederick J. He don, Director l'
Project Directorate IV L
Division of Reactor Projects - III, i
IV, V and Special Pro,ects j
Office of Nuclear Reactor Regulation L
Attachment:
1 Changes to the-Technical 1.
Specifications s
- Date of Issuance: January 31, 1990 i
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1 ATTACHMENT _T,0,!.lEENSE, AMEppf.ENLpl.,13, S
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FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix."A" Technical Specifications as indicated below. The revised pages are: identified by amendment number and contain vertical lines indicating
.the. area of change.
Remove Pages Insert Pages 3-18 3-18 3-19 3-19
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i TABLE 3-4 y
1 MINIMUM FREQUENCIES FOR SAMPLING TESTS-
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Type of Measurement Sample and Analysis and Analysis Frequency 1.
Reactor-Coolant (a) Power Operation (1) Gross Radioactivity 1 per 3 days (Operating Mode 1)
(Gamma emitters) l' (2) Isotopic Analysis for (i)
I per 14 days DOSE EQUIVALENT I-131 (ii) per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (1) whenever the radio-activity exceeds 1.0 Ci/gm DOSE EQUIVALENT I-131.
(iii) 1 sample between 2-8 hours following.
a thermal power change exceeding 15%-
of the rated thermal power change exceeding ~15% of the rated thermal power within a 1-hour period.
(3)~ E Determination 1 per'6 months (2)
(4) Dissolved oxygen 1 per 3~ days and chloride (b) Hot Standby (1) Gross Radioactivity 1 per 3 days (Operating Mode 2)
(Gamma emitters)
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Hot' Shutdown (2)
Isotopic Analysis for.
(i) 1 per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (1)
(Operating Mode 3)-
DOSE EQUIVALENT I-131 whenever the radio-(.
activity exceeds 1.0 Ci/gm DOSEL.
EQUIVALENT I-131.
(ii) 1 sample between 2-8 hours following a thermal power change exceeding 15% of the rated thermal power within a 1-hour period.
(3) Dissolved oxygen 1 per 3 days and chloride v
Amendment No. 28, 67, 1E4 3-18 4
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MINIMUM FREQUENCIES FOR SAMPLING TESTS j
Type of Measurement Sample and Analysis and Analysis Frequency 1.
Reactor Coolant (Continued)
(c) Cold Shutdown (1) Chloride 1 per 3 days I
(Operating Mode 4)
(d) Refueling (1) Chloride 1 per 3 days (3) l Shutdown (Operating Mode 5)
(2) Boron Concentration 1 per 3 days (3) 2.
SIRW Tank Boron Concentration 1 per 31 days
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Concentrated Boric Boron Concentration 1 per 31 days o
Acid Tanks 4.
SI Tanks Boron Concentration 1 per 31 days.
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Spent Fuel Pool Boron Concentration 1 per 31 days.
(1) Until the radioactivity of the reactor coolant is restored to 51 pCi/gm DOSE EQUIVALENT I-131.
. (2) LSample to be taken after a minimum of 2 EFPD and 20 days of power operation-have elapsed since reactor was suberitical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer, a
(3) Boron and chloride sampling / analyses are not required when the core'has been off-loaded.
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k Amendment No. 28, 67, 86,124 3-19
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