ML20215L559
| ML20215L559 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 10/23/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20215L562 | List: |
| References | |
| DPR-57-A-130, NPF-05-A-065, TAC 60728, TAC 60729 NUDOCS 8610290105 | |
| Download: ML20215L559 (9) | |
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UNITED STATES
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 130 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated January 27, 1986, as supplemented July 10, 1986, 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 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 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 changes to the Technical Specifications as indicateo in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 134 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY C 1 SSION f
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 23, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO.130 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 3.15-11 3.15-11 4
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RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TJble Natrtions a.
Lower Limit of Detection is defined in table notation (a) of Table 4.16.1-1, Specification 4.16.1.
b.
For certain radionuclices with Jow-gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure redionuclides in concentrations near the Lower Limit of Detection. Under these circumstances, the Lower Lipit of Detection may be increased inversely proportional to thc magnitude of the gamma yield (i.e., 1 x 10-4/I, where I = photon abundance expressed as a decimal fraction), but in no case shall the Lower Limit of Detection, as calculated in this manner for a specific radionuclide, be greater than 10 percent of the Maximum Permissible Concentration value specified in 10 CRF 20, Appendix B, Table II (column 1).
c.
Sampling and analyses for principal gamma emitters shall l
also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have increased more than a factor of 3.
d.
Sampling shall be performed weekly, and analyses chall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing (or af ter removal from sampler). Sampling shall also be performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15-percent RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding Lower Limits of Detection may be increased by a factor of 10.
The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor Reading have increased more than a f actor of 3.
e.
The ratio of the sample flowrate to the sampled stream flowrate shall be know for the time period covered by each dose or dose rate calculation made in accordance with Specification 3.15.2.1, 3.15.2.2, and 3.15.2.3.
f.
The principal gamma emitters for which the Lower Limit of Detection specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135. and Xe-138 for gaseous emissions; and Mn-5 4, Fe-59, co-5 8, co-60, zn-6 5, Mo-9 9, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported. Other measurable and identifiable peaks, together with the above nuclides, shall also be identified and reported. Nuclides below Hatch - UNIT 1 3.15-11 Amendment No. 110, 130
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
j WASHINGTON. D. C. 20555 o,
g GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated January 27, 1986, as supplemented July 10,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the CommTssion's rules and regulations set f. orth in 10 CFR 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 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 changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
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' (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY C ISSION 4
W Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing Attachmert:
Changes to the Technical Specifications Date of Issuance: October 23, 1986
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-s ATTACHMENT TO LICENSE AMENDMENT fl0 65 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised'page is identified by Amendment number and contains vertical lines indicating the area of change.
Remove Insert 3/4 11-11 3/4 11-11 I
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TABLE 4.11.2-1 (SHEET 2 OF 3) k,**
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM T blo Netttion1 a.
Lower Limit of Detection is defined in table notation (a) of Tablo 4.16.1-1 of Unit 1, Specification 4.16.1.
b.
For certain radionuclides with low-gamma yield or low T energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the Lower Limit of Detection. Under these circumstances, the Lower Limit of Detection may be increased inversely proportional to the magnitude of the gamma yield (i.e.,1 x 10-4/I, where I = photon abundance expressed as a decimal fraction), but in no case shall the Lower Limit of Detection, as calculated in this manner for a specific radionuclide, be greater than 10 percent of the Maximum Permissible Concentration value specified in 10 CRF 20, Appendix B, Table II (column 1).
c.
Sampling and analyses for principal gamma emitters shall l
0 also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED T5ERMAL POWER within a 1-hour period if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have increased more than a factor of 3.
d.
Sampling shall be performed weekly, and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing (or af ter removal from sampler). Sampling shall clso be performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15-percent RATED THERMAL FOWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses completed within 48 hotra of changing. When samoles collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding Lower Limits of Detection may be increased by a tactor of 10.
The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor Reading have increased more than a factor of 3.
e.
The ratio of the sample flowrate to the sampled stream flowrate shall be know for the time period covered by each dose or dose rate calculation made in accordance with specification 3.11.2.1, 3.11.2.2, and 3.11.2.3.
f.
The principal gamma emitters for which the Lower Limit of Detection specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135. and Xe-138 for geseous emissions; and Mn-5 4, Fe-59, Co-5 8, Co-6 0, 2n-6 5, Mo 09, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissir,s.
This list does not mean that only these nuclides are to be detected and reported. Other measurable and identifiable peaks, together with the above nuclides, shall also be identified and reported. Nuclides below Hatch - UNIT 2 3/4 11-11 Amendment No. 48, 65 7s
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TA3LI 4.11.2-1 (SW 3 OF 3 )
RADICAC"IVEGASEOUSWASTESAMPLINGANDANALYSISPROGRA.k Table Notatiens (Continued) i only these nuclides are to be detected and reported.
Other measurable and identifiable peaks, together with the above nuclides, shall also be identified 2nd reported.
Nuclides below the Lower Limit of Detection for the analyses should not be reported as being present at the Lower Limit of Detection level for that nuclide.
When unusual circumstances result in Lower Limit (s) of Detection. higher than required, the reasons i
shall be documented in the semi-annual effluent release report.
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- Amendment No. 48 00000 Ct1 dLttlf Q [5-9-b5
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