ML20033A644
| ML20033A644 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/22/1981 |
| From: | Snyder B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033A306 | List: |
| References | |
| NUDOCS 8111250676 | |
| Download: ML20033A644 (5) | |
Text
1 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.17 License No. DPR-73 1.
Thu Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (the Licensee) dated August 20, 1981, 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 confomity with the Order for Modification of License dated July 20, 1979, the Order of February 11, 1980, the Modification of Orders dated August 11, 1980 and September 23, 1981, the Amendment of Orders dated November 14, 1980 and April 28,-1981, the application for amendment, the provisions of the Act, and the rules and regulations of the Conunission.
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 Commission's regulations; 0.
The issuance of this 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 in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been sa tisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, by changing para-graph 2.C.(2) to Facility Operating License No. DPR-73, to read as follows:
2.C.(2)
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.17, are hereby incorporated in the license.
The licensee shall operate the facility in accordance
[ % % 8 h o$oo C-Q with the Technical Specifications and all Comm subsequent to March 28, 1979.
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'(
, i 3.
This license amendment is effective as of the date of'its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
Bernard J. Snyder,' rogram Director Three Mile Island rogram Office Office of Nuclear Reactor Regulation Attachmment:
Revised Technical Specifications Date of Issuance: October' 22,1981
FACILITY OPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320 Replace the following pages'of Appendix "B" Technical Specifications with the enclosed pages as indicated. The revised pages contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to main-tain document completeness.
Pages 3.2-3 5 /
e
3.2-3 exceeds the reporting level given in Table 4, a written report shall'be submitted to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear React'or Regulation) within 30 days from the end of the quarter.
If it can be demonstrated that the level is not a result of plant effluents (e.g., by comparison with control station or preoperational data) a report need not be submitted, but shall be dis-cussed in the annual report. When more than one of the radionuclides in Table 4 are detected in the medium, the reporting level shall have been exceeded if:
concentration (1) concentration (2)
+
,, 3 i reporting level (1) reporting level (2)
If radionuclides other than those in Table 3.2-4 are detected and are due from plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR Part 50, Appendix I.
This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result, c.
Radiological Releases and Estimated Dose Report.
The following information shall be submitted to the Director of the Regional Office. This information shall be submitted on a calendar quarter basis (January-March, April-June, July -September, and October-December) and shall be submitted no later than 60 days following the end of each calendar quarter.
J (a)
Estimates of the amounts and types of radioactivity that were released to the environment during the quarter and during the calendar year.
This shall include estimates of the total activity of each nuclide and the time rate of release of each nuclide.
(b)
Estimates of populations and maximum individual doses which occurred l
during the calendar quarter and during the calendar year shall be l
provided. The estimates shall be based on actual hydrological and i
meteorological conditions which occurred during the releases.
Calcu-lational methods shall be those of U.S. NRC Regulatory Guides 1.109 (Revision 1, October 1977), 1.111 (Revision 1, July 1977), 1.112 (Revision 0-R, April 1976) and 1.113 (Revision 1, April 1977). These calculations shall be based on estimates of actual population distri-butions during the releases and shall take into consideration factors such as boating or fishing recreation.
Amendment No. 76, 17
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i 5-7 y
i station operation ~on the environment.
If hannful effects or evidence m
of irreversible damage are s'uggosted by the monitoring or special' programs, the licensee shall provide a more detailed analysis of the_.
data and a proposed course of action to alleviate.the problem.
The Annual Report shall also include.a sunnary of:
L
- 1) All ETS noncompliances and the corrective actions taken~ to remedy them.
- 2) Changes made to state and federal permits and certificates.
- 3) Changes made to the Environmental Program Description Document.
- 4) Changes-in station design which could involve an environmental-impact or' change the findings of the FSFES.
- 5) All nonroutine reports submitted per ETS Section 4.6.
E
- 6) Changes in ETS.
l B.
Data ' Reporting Formats I
Results of analysis of all nonradiological environmental data collected
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shall be summarized and tabulated on an annual basis.
In the event that some results are not available by May 1, the report shall be j
submitted noting and explaining the missir.g results. The missing data shall be submitted as soon as possible in a supplementary report.
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.C.
Quarterly Radiological Releases and' Estimated Dose Report.
A quarterly report shall be submitted to the Director of the Regional l
Office. This report shall be submitted no later than 60 days following.
~
the end of.each calendar quarter. The report shall ' include estimates of i
the amounts and types of radioactivity released each quarter including -
the time release rate and total activity of each nuclide. Also include estimates of populations and maximum individual doses which occurred during the quarter and during the calendar year shall be provided. The estimates shall be based on actual hydrological and meteorological con-j.
ditions which occurred during the releases. Calculational methods shall be those of U. S. NRC Regulatory Guides 1.109 (Revision 1, October 1977),
4 1.111 (Revision 1, July 1977),1.112 (Revision 0-R, April 1976) and 1.113 (Revision 1, April 1977). These calculations shall be based on estimates
}
of actual population distributions during the release and shall take into i
consideration factors such as boating or fishing recreation.
l 5.6.2 Nonroutine Reports l
A report shall be submitted in the event that a " Limiting Condition for j
Operation" (Section 2), if applicable, is exceeded, a report level as specified in Section 3, " Environmental Monitoring," is reached or if an 4
" Exceptional Occurrence" as specified in Section 4.6 occurs.
Reports shall be submitted under one of the report schedules described below.
Amendment No. M, 17 L
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