ML20154R057
| ML20154R057 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/20/1998 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154R060 | List: |
| References | |
| DPR-51-A-193, NPF-06-A-193 NUDOCS 9810260165 | |
| Download: ML20154R057 (4) | |
Text
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6.8.2 E:ch prse:durs of 6.8.1 absys, cnd ch;ng:s in intant tharcts, ch211 b3 rsvicw:d and cpprovsd es rsquircd by ths QAMO prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Changes to procedures of 6.8.1 above may be made and implemented prior to obtaining the review and approval required in 6.8.2 above provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's license on Unit 1.
c.
The change is documented, reviewed and approved as required by the QAMo, within 14 days of implementation.
6.8.4 The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintair.ed:
A program shall be established to implement the leakage rat sisting of the reactor building as required by 10 CFR 50.54 (o) and.. OFR 50, Appendix J, option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based containment Leak-Test Program," dated September 1995.
The peak calculated reactor building internal pressure for the 9
design basis loss of coolant accident, Pa, is 54 psig.
i The maximum allowable reactor building leakage rate, La, shall be 0.20% of containment air weight per day at Pa.
Reactor building leakage rate acceptance criteria is 5 1.0 La.
During the first unit startup following each test per"ormed in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and 5 0.75 La for Type A tests.
The provisions of specification 4.0.2 do not apply to the test frequencies specified in the Reactor Building Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the Reactor Building Leakage Rate Testing Program.
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l Amendment No M,M,M,M,M,M, 127 M o M, M, MG, M4, MS, M4,MG, M6,4M, 185 9810260165 981020 PDR ADOCK 05000313 P
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6.8.5 Tho Radioactiva Efflurnt Cantrolo Prsgram chall bo estchlich d, implemented, cnd maintain d This program conforms with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
The program shall be contained-in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
a.
Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint detenmination in accordance with the methodology in the ODCM; b.
Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to 10 CFR 20, Appendix B, Table II, Column 2; c.
Monitoring, sampling, and analysis of radioactiva liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the CDCM; d.
Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I; e.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quartsr and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days; f.
Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; g.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; h.
Limitations on the annual and quarterly air Jones resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CrR.50, Appendix I; 1.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate fona with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and j.
Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
Amendment No. 193 127a I
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22 20 18-t 16 h,
14-Z 12-m O10 xo 8 --
REGION B (UNACCEPTABLE OPERATION) 6-(4,4) 4 2
REGION A (ACCEPTABLE OPERATION)
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I 0
0 10 20 30 40 50 60
. 70 80 90 100 i
HYDROGEN %
l HYDROGEN - OXYGEN LIMITS FOR ANO-2 WASTE GAS SYSTEM Figure 3.11-1 i
ARKANSAS - UNIT 2 3/4 11-5 Amendment No. 49,61,M,434.193 f
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8 ADMINISTRATIVE CONTROL 6.8.3 ' Changes to procedures of 6.8.1 above may be made and implemented prior to obtaining-the review and approval required in 6.8.2 above provided:
.a.
The intent of the original procedure is r.ot altered.
b.
The change is approved by two members of the plant management staff, at least one of wham holds a Senior Reactor operator's
-License on Unit 2.
l c.
The change is documented, reviewed and approved as required by j
the QAMO, within 14 days of implementation.
1 L
6.8.4 The following program shall be established, implemented, and
(
maintained:
l a.
Radioactive Effluent Controls Program This program conforms with 10 CFR 50.36a for the control of radioactive j
effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from L
radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be take whenever the program limits i
are exceeded. -The program shall include tae following elements:
l 1)
Limitations on the functional capability of radioactive liquid and gj i
gaseous monitoring instrumentation including surveillance tests and l:
setpoint determination in accordance with the methodology in the ODCM; l.
J l:
2)
Limitations on the concentrations of radioactive material released in liquid offluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2; 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; 4)
Limitations on the annual and quarterly doses or dose commitment to a HEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I; l
l 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current I
calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days; 6)
Limitations on the functional capability and use of the liquid and l-gaseous effluent tr.atment systems to ensure that appropriate portions j
of these systems aie used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the i
l guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, i
Column 1; i-4 ARKANSAS - UNIT 2 6-14 Amendment No. 6,W,44,M,44,48,444, 444,444,449,193
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