ML19312C505
| ML19312C505 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/30/1978 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C503 | List: |
| References | |
| NUDOCS 7912160066 | |
| Download: ML19312C505 (13) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
WASHINGTON. D. C. 20555
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DUKE POWER COMPANY DOCKET N0. o0-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-38 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment by Duke Power Company (the licensee) dated October 31, 1977 and December 2, 1977, comply 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; 8.
The faci.lity will operate in conformity with the application, the provisions of the Act, and the rules and 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 Commission's regulations; D.
The issuance of this amendment 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 wit' 11 CFR Part 51 of the Commission's regulations and all applicabie requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-38 is hereby amended to read as follows:
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"3.B Technical Specifications
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The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, are l
hereby in.orporated in the license.
The licensee shall j
operate the facility in accordance with-the Technical Specifications."
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This license amendment is effective April 1,1978.
4 FOR THE NUCLEAR REGULATORY COMMISSION l
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A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Rea' tors
Attachment:
Changes to the Technical Specifications Date of Issuance:
Januany 3 0 1975 I'
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UNITED STATES p'
NUCLEAR REGULATORY COMMISSION
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DUKE POWER COMPANY 00CbTNO.50-247 OCONEE NUCLEAR STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-47 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendnent by Duke Power Company (the licensee) dated October 31, 1977 and December 2, 1977, comply 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and 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 Commission's regulations; D.
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 satisfied.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-47 is hereby amended to read as follcws:
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"3.8 Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.55, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."
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This license amendment is effective April 1,1978.
FOR THE NUCLEAR REGULATORY COMMISSION D
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i A. Schwencer, Chief Operating Reactors Branch #1 i
Division of Operating Reactors i
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Attachment:
Changes to the Technical Specifications 4
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Date of Issuance:
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UNITED STATES NUCLEAR REGULATORY COMMisslON WASHINGTON. D. C. 20555 o
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e OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. DPR-55 1.
The Nuclear Regulatory Conmission (the Cornission) has found that:
A.
The. applications for amendment by Duke Powar Company (the licensee) dated October 31, 1977 and December 2,197?, comply with the standards and requirements of the Atomic Cr.argy 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:
C.
There is reasonable assurance (i) that the activities authorized by this arendrent 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 regulatior.s; D.
The issuance of this amendment will nct be inimical tc tne conrcon defense and security or to tne Sealth and safetj of the public; and E.
The issuance of this amendr.ent is ir acccedance >:ith 10 CFR : art 51 of ne Comnission's reculaticns and all asolicatie rec. e er.ts o
have been satisfied.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility License No. DPR-55 is hereby amended to read as follows:
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. "3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications."
3.
This license amendment is effective April 1,1978.
FOR THE NU LEAR REGULATORY COMMISSION
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lb'siLOWf 2 A. Schwencer, Chief Operating Reactors Branch #1 Division o.f Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
J N A'Y 3834
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0. 55 TO DPR-38 AMENDMENT NO. 55 TO DPR-47 AMENDMENT NO. 52 TO DPR DOCKET NOS. 50-269, 50-270 AND 50-287 Remove the following pages and insert revised identically numbered pages:
6.6-1 6.6-2 6.6-3 6.6-4 6.6-5 Delete the following pages:
6.7-1 6.7-2 6.7-3 6.7-4 6.7-5 6.7-6 s8
Section DTS.
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6.3 ACTIO:: TO 3E TAKE:4 I!: IllE INE"T A SAFETY LI'11T IS EXCEDO 6.3-1 6.4 STATIO!! 0?L'.ATI:;G PROCED'J:'ES 6.4-1 6.5 ST/.TIO:; OPEPJTI::3 RECORDS 6.S-1 6.6 STATIO.' REPCnT!!:0 REQ"IP.CIL:::S 6.6-1 6.6.1 Routine Renorts 6.6-1 6.6.2 h n-kou_ tine Rconr:s
- 6. 6-6 6.6.3 Soccial Penorts 6.6-9 s
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Arnendment Nos 55, 55 & 52
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6.6 STATION REPOR'.
G REQUIREMENTS 6.6.
Routine Reports In additien to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Office of Inspection and Enforcement, Region II unless otherwise noted.
6.6.1.1 Startup Report A summary report of unit startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the facility license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have signi-ficantly altered the nuclear, thermal or hydraulic performance of the unit.
Startup reports shall be submitted (1) within 90 days following completion of the startup test program, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) nine months following initial criticality, whichever occurs first.
If a startup report does not cover all three events, i.e.,
initial criticality, completion of the startup test program and resumption or commencement of commercial power operation, supplementary reports shall be submitted at least every three months until all three events are completed.
6.6.1.2 Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, D.C.,
- 20555, with a copy to the appropriate Regional Office, to be submitted by the fifteenth of each month following the calendar month covered by the report.
6.6.1.3 Personnel Exposure and Monitoring Report A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mre and their associated man rem exposure according to work and job functions,pfyr e.g.,
reactor operationa and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling.
The dose atsignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
6.6.1.4 Reporting of Radioactive Effluent Releases Data shall be reported to the Commission semi-annually in a form similar to that shown in Table 6.6-1 and shall include the following:
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(1) Gaseous Releases (a) Total radioactivity (in curies) releases of noble and activation gases.
(b) Maximum noble gas release rate during any one-hour period.
(c) Total radioactivity (in curies) released, by nuclide, based on repres entative isotopic analyses performed.
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-This tabulation supplements the requirements of 120.407 of 10 CFR Part 20 6.6-1 m,
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(d) Percentage applicable limits released.
(2)
Iodine Releases (a)
Total I-131, I-133, I-135 radioactivity (in curies) released.
(b) Total radioactivity (in curies) released, by nuclide, based on representative isotopic analyses performed.
(c)
Percentage of limit.
(3) Particulate Releases (a) Gross radioactivity (8-y) released (in curies) excluding back-ground radioactivity.
(b) Gross alpha radioactivity released (in curies) excluding back-ground radioactivity.
(c) Total radioactivity released (in curies) of nuclides with half-lives greater than eight days.
(d)
Percentage of limit.
(4) Liquid Releases (a) Gross radioactivity (8-y) released (in curies) excluding tritium and average concentration released to the unrestricted area at the Keowee Hydro unit.
(b) The maximum concentration of gross radioactivity (8-y) released to the unrestricted area (averaged over the period of release).
(c) Total tritium and alpha radioactivity (in curies) released and average concentration released to the unrestricted area at the Keowee Hydro unit.
(d) Total dissolved gas radioactivity (in curies) and average con-centration released to the unrestricted area at the Keowte Hydro unit.
(e) Total volume (in liters) of Keowee Hydro liquid waste released.
(f) Total volume (in liters) of dilution water used prior to release frem the restricted area.
(g). Total radioactivity (in curies) released, by nuclide, based on representative isotopic analyses performed.
(h)
Percentage of limit for total activity released.
6.6-2 Amencrent Nos. 55, 55 & 52
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a (5) Solid Waste (a) The total amount of solid waste packaged (in cubic feet).
(b)
Estimated total radioactivity (in curies):
(c) Disposition including date and destinatica if shipped off site.
6.6.1.5.
Environmental Monitoring An Environmental Monitoring Report containing the following information shall be submitted prior to March 1 of each year.
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(a) For each medium sampled during the reporting period, the folicwing information shall be previded.
1.
Number of sampling locations.
2.
Total number of samples.
3.
Number of locations at which levels are found to be sig-nificantly greater than local backgrounds.
4.
Highest, lowest, and the average concentrations or levels of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.
(b) If levels of station-contributed radioactive materials in en-vironmental media indicate the likelihood of public intakes in excess of 3 percent of those that could result from continuous exposure to the concentration values listed in Appendix B, Table II, Part 20, estimates the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based shall be provided.
(These values are com-parable to the top of Range I, as defined in FRC Report No. 2.)
(c) If statistically significant variations in off-site environmental concentrations with time are observed and are attributed to station releases, correlation of these results with effluent releases shall be provided.
6.6-3
<4 Amendment Nos. 55, 55 & 52
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DELETE ENTIRE PAGE 6.6-4 Amendment Nos. 55, 55 & 52
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6.6.2 Non-Routine Reports 6.6.2.1 Reportable Occurrences a.
Prempt Notification with Written Followup The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery by telephene, and confirmed by telegraph, mailgram or facsimile no later than the first normal working day following the event to the DirecterI Office of Inspection and Enforcement, Region II, or his designate with a written followup report within two weeks to the Director, Office of Inspec-tion and Enforcement, Region II (copy to the Director, Office of Management Infor=ation and Program Control).
(1) Failure of the Reactor Protective System to trip, as required, when a monitored parameter reaches the setpoint specified as the limiting safety system setting in the Technical Specifications.
(2) Operation of the unit or affected systems when any parameter or operation aubject to a limiting cendition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specifications.
1 (3) Abnor=al degradation discovered in fuel cladding, reactor coolant pressure boundary or primary containment.
(a) Reactivity anomalies involving disagreement with predicted value of reactivity salance under steady-state conditions greater than or equal to 1% ak/k; a calculated reactivit:- balance indicating shutdown margin less conservative than specified in the technical specifications; short-term reactivity increases that correspend to a reactor period of less than 3 seconds, or if subcritical, an unplanned reactivit:.
inser: ion of more than 0.U' ik/k; or any unplanned criticality.
($) Failure or malfunction of one er more cceponents which prevents or could prevent, by itself, the fulfillment of the functional require-ments of syste=s required to cope with accidents analyzed in the Safety Analysis Report.
(6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, :he fulfillment of :he functional requirements Of systems required to cope with accidents analyzed in the Safety Analysis Report.
(7) Conditions arising from natural or man-made events tha:, as a direct result of the event, require uni: shutdown, operation of safety systems, or other protective mea sures required by Technical Specifi-cations.
(8) Errors discovered in the transien: or accident analyses or in the methods used f:r such analyses as described in :he Saf aty Analysis Report or in tne bases for the Technical Specifications tnat have or could have permitted reactor operation in a manner less conservative than assured in the analyses.
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