ML20104B221
| ML20104B221 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/14/1985 |
| From: | John Miller, Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20104B224 | List: |
| References | |
| DPR-51-A-093, NPF-06-A-061 NUDOCS 8502010746 | |
| Download: ML20104B221 (20) | |
Text
___
49
%o UNITED STATES
/
'"h NUCLEAR REGULATORY COMMISSION h
.j WASHINGTON, 0. C. 20555 8
...../
ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company
~
(the licensee) dated October 31, 1980 as supplemented August 23, 1983 and July 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 Comission'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. DPR-51 is hereby amended to read as follows:
8502010746 850114 PDR ADOCK 05000313 P
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 93, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION vohn F. Stolz, Chief l
Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 14, 1985 L
l i
i
ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET N0. 50-313 Revise the Appendix A Technical Specifications as follows:
Remove Insert Page 11 11 fia iia v
v 66u 66u 110bb 110bb 110bc h
e d
SECTION TITLE PAGE 3.14 HYDROGEN PURGE SYSTEM 66e 3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g 3.16 SHOCK SUPPRESSORS (SNUBBERS) 661 3.17 FIRE SUPPRESSION WATER SYSTEM 66m 3.18 FIRE SUPPRESSION SPRINKLER SYSTEMS 66n 3.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON SYSTEMS 66o 3.20 FIRE HOSE STATIONS 66p 3.21 PENETRATION FIRE BARRIERS 66q 3.22 REACTOR BUILDING PURGE FILTRATION SYSTEM 66r 3.23 REACTOR BUILDING PURGE VALVES 66t 3.24 EXPLOSIVE GAS MIXTURE 66u 1
3.25 RADI0 ACTIVE EFFLUENTS 66v 3.25.1 Radioactive Liouid Effluents 66v 3.25.1.1 Concentration 66v 3.25.1.2 Dose 66w 3.25.1.3 Waste Treatment 66x 3.25.1.4 Liquid Holdup Tanks
, 66y 3.25.2 Radioactive Gaseous Effluents 66z 3.25.2.1 Dose Rate 661 3.25.2.2 Dose - Noble Gases 66aa 3.25.2.3 Dose - Iodine-131. Tritium, and Radionuclides in Particulate Form 66bb 3.25.2.4 Gaseous Radwaste Treatment 66cc 3.25.2.5 Gas Storage Tanks 66dd
_3.25.3 Total Dose 66ee 3.25.4 Solid Radioactive Waste 66ff 4.-
SURVEILLANCE STANDARDS 67 1
4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 76 4.3 TESTING FOLLOWING OPENING OF SYSTEM 78 4.4 REACTOR BUILDING 79_
4.4.1 Reactor Buildino Leakaoe Tests 79 4.4.2 Structural Integrity 85 4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR l
BUILDING COOLING SYSTEM PERIODIC TESTING 92 4.5.1 Emeroency Core Cooling Systems 92 4.5.2 Reactor Buildina Cooling Systems 95 4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100 4.7 REACTOR CONTROL ROD SYSTEM TESTS 102 4.7.1 Control Rod Drive System Functional Tests 102 4.7.2 Control Rod Prooram Verification 104 l
4.8 EMERGENCY FEEDWATER PUMP TESTING 105 4.9 REACTIVITY ANOMALIES l
4.10 106 CONTROL ROOM EMERGENCY AIR CONDITIONING AND i
ISOLATION SYSTEM SURVEILLANCE 4.11 107 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE l-4.12 HYDROGEN PURGE SYSTEM SURVEILLANCE 109 -
l 4.13 EMERGENCY COOLING POND 109b 4.14 110a a
RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE
'110b l
4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH j
ENERGY LINES OUTSIDE OF CONTAINMENT 110c l-if AmendmentNo.23,2A,Jg,3A,he 93 53 '55, 55, 84,
SECTION TITLE PAGE 4.16 Sil0CKSUPPRESSORS(SNUBBERS) 110e 4.11 FUEL HANDLING AREA VEN11LAIION SYSTEM SURVEILLANCE 110h 4.18 STEAM GENERATOR TUBING SURVEILLANCE 110j 4.19 FIRE DETECTION INSTRUMENTATION 110p 4.20 FIRE SUPPRESSION WATER SYSTEM 110q 4.21 SPRINKLER SYSTEMS 110t 4.22 CONTROL ROOM AND AUXILIARY CONTROL ROOM HAla:4 SYSTEMS 110u 4.23 FIRE HOSE STATIONS 110v 4.24 PENETRATION FIRE BARRIERS 110w a.;s REACTOR BUILDING PURGE FILTRATION SYSTEM 110x 4.26 REACTOR BUILDING PURGE VALVES 110z 4.27 DECAY HEAT REMOVAL 110aa 4.28 EXPLOSIVE GAS MIXTURE 110bb l
4.29 RADIOACTIVE EFFLUENTS 110cc 4.29.1 Radioactive Liouid Effluents 110cc 4.29.1.1 Concentration 110cc 4.29.1.2 Liquid Holdup Tanks 110gg 4.29.1.3 Liquid Radioactive Effluent Instrumentation 110hh 4.29.2 Radioactive Gaseous Effluents 110jj 4.29.2.1 Dose-Rate 110jj 4.29.2.2 Gas Storage Tanks 110mm 4.29.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation 110nn 4.29.3 Dose Calculations for Radioactive Effluents 110rr 4.29.4 Sol 10 Kadioactive Waste 11orra 4.30 RADIOLOGICAL ENVIRONMENTAL MONITORING 110ss 4.30.1 Radiological Environmental Monitoring Program Description 110ss 4.30.2 Land use census 110zz A.30.3 Interlaboratory Comparison Program 110bbb 5.
DESIGN FEATURES 111 5.1 SITE 111 5.2 REACTOR BUILDING ~
112 5.3 REACTOR 114
' 5. 4 NEW AND SPENT FUEL STORAGE FACILITIES 116 6.
ADMINISTRATIVE CONTROLS 117 6.1 RESPONSIBILITY 117 6.2 ORGANIZATION 117 6.3 FACILITY STAFF QUALIFICATIONS 117 6.4 TRAINING 117 6.5 REVIEW AND AUDIT 117 6.6 REPORTABLE OCCURRENCE ACTION 126 6.7 SAFETY LIMIi (IOLATION 126 6.8 PROCEDURES 127 6.9 RECORD RETENTION 128 6.10 RADIATION PROTECTION PROG' TAM 129 6.11 HIGH RADIATION AREA 129 6.12 REPORTING REQUIREMENTS 140 6.13 ENVIRONMENTAL QUALIFICATION 147 6.14 0FFSITE DOSE CALCULATIGN MANUAL (ODCM) 148 ita Amendment No. 8W. 93
l l
3.5.2-2E DELETED 3.5.2-2F DELETED 3.5.2-2G DELETED 3.5.2-2H DELETED 3.5.2-3 OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION FROM 0 EFPD TO EOC - ANO-1 48e 3.5.2-3B DELETED 3.5.2-3C DELETED 3.5.2-3D DELETED 3.5.2-4 LOCA LIMITED MAXIMUM ALLOWABLE LINEAR HEAT RATE 48f 3.5.2-4A APSR POSITION LIMITS FOR OPERATION FROM 0 EFPD TO APSR WITHDRAWAL - ANO-1 48g 3.5.2-4B APSR POSITION LIMITS FOR OPERATION AFTER APSR WITHDRAWAL ANO-1 48h 3.5.2-4C DELETED 3.5.2-4D DELETED 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE INDICATION 53a 3.5.4-2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT INDICATION 53b 3.5.4-3_
INCORE INSTRUMENTATION SPECIFICATION 53c 3.24-1 HYDR 0 GEN LIMITS FOR ANO-1 WASTE GAS SYSTEM 110bc l
4.4.2-1 NORMALIZED LIFTOFF FORCE - HOOP TENDONS 85b 4.4.2-2 NORMALIZED LIFTOFF FORCE - DOME TENDONS 85c 4.4.2-3 NORMALIZED LIFTOFF FORCE - VERTICAL TENDONS 85d y
Amendment No. 52, 86. SfidI'
___y--
3.24 EXPLOSIVE GAS MIXTURE Applicability Applies to the Waste Gas System hydrogen / oxygen analyzers Objective To prevent accumulation of explosive mixtures in the waste gas system.
Specification 3.24.1 The concentration of hydrogen / oxygen shall be limited in the waste gas decay tanks to Region "A" of Figure 3.24-1.
3.24.2 When the hydrogen / oxygen concentration in any of the decay tanks enters Region "B" of Figure 3.24-1, corrective action shall be taken to return the concentration values to Region "A" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.24.3 The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
Bases These hydrogen / oxygen limits provide reasonable assurance that no hydrogen / oxygen explosion could occur to allow rupture of the waste gas decay tanks. The hydrogen and oxygen limits are based on information in NUREG/CR-2726 " Light Water Reactor Hydrogen Manual".
66u Amendment No. ES, 93
4.28 EXPLOSIVE GAS MIXTURE Applicability Applies to the Waste Gas System hydrogen / oxygen analyzers.
Objective To prevent accumulation of explosive mixtures in the waste gas system.
Specification 4.28.1 The concentration of hydrogen / oxygen in the waste gas system shall be monitored continuously by either the primary or redundant waste gas analyzer during waste gas compressing operations to the waste gas decay tanks.
analyzer in 4.28.2 During waste gas system operation, with no H /02 2
service, without delay suspend all additions of waste gas to the decay tanks or take grab samples for analysis every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations, daily during other operations. The analysis of these samples shall be completed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of taking the sample.
Bases This specification is to assure that the hydrogen / oxygen concentration will be kept within the limits in Figure 3.24-1 and therefore not enter the flammable region concentrations in the waste gas decay tanks.
Grab samples are to be taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations when both hydrogen / oxygen analyzers are out of service. These samples are to be analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to assure that the hydrogen / oxygen concentration is within the limits in Figure 3.24-1.
During other Waste Gas compressor operations, the hydrogen / oxygen concentration is not as subject to change, therefore grab samples are to be taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
110bb Amendment No. EB, 93
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Il0be-Amendment flo. 93 i
M UNITED STATES y
h NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 Y*
t ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated October 31, 1980 as supplemented August 23, 1983 and July 11, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 j
conducted in compliance with the Comission's regulations; i
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 Comission's regulations and all applicable requirements p
have been satisfied.
e I
i
(
s 9
- c., w y
^ 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 i
No. NPF-6 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license j
conditions.
3.
This license amendment is effective as of the date of its issuance.
i
)
FOR THE NUCLEAR REGULATORY COMMIS~iION
]
M
+
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical l
Specifications Date of Issuance:
January 14, 1985 l
I e
9
ATTACHMENT TO LICENSE AN.'NDMENT NO. 61 FACILITY OPERATING LICENSE N0. NPF-6 DOCKET NO. E0-368 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Pages Insert Pages XIV XIV 3/4 11-14a 3/4 11-14b 3/4 11-14c B 3/4 11-4 B 3/4 11-4 B 3/4 11-5 l
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INDEX BASES SECTION PAGE 3/4.9.5 COMMUNICATIONS.........................................
B 3/4 9-2 3/4.9.6 REFUELING MACHINE OPERABILITY.......................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............. B 3/4 9-2 3/4.9.8 COOLANT CIRCULATION.................................... B 3/4 9-2 3/4.9.9 andi3/4.9.10 WATER LEVEL - REACTOR VESSEL AND STORAGE P0OL WATER LEVEL............................. B 3/4 9-3 3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM.................. B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 S HUTDOWN MARG I N........................................ B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS............................................... B 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS.................................. B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT................................ B 3/4 10-1 3/4.10.5 MINIMUM TEMPERATURE FOR CRITICALITY.................... B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS....................................... B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS...................................... B 3/4 11 -2 t
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3/4.11.3 TOTAL D0SE............................................. B 3/4 11-4 3/4.11.4 SOLID RADI0 ACTIVE WASTE................................ B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4 :12, L MONITORING PR0 GRAM..................................... B 3/4 12-1 3/4.12.2 " LAND USE CENSUS........................................ B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARIS0N PR0 GRAM..................... B 3/4 12-1 ARKANSAS - UNIT 2 XIV Amendment No.pyy, 61
INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area............................................
5-1 Low Popul a ti o n Zone.......................................
5-1 i
l 5.2 CONTAINMENT Co n fi g u ra ti o n.............................................
5-1 l
Design Pressure and Temperature...........................
5-4 l
l 5.3 REACTOR CORE Fuel Assemblies...........................................
5-4 Control Element Assemblies................................
5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature...........................
5-4 Vo1ume....................................................
5-5 l
5.5 METEOROLOGICAL TOWER L0 CATION.............................
5-5 I
l 5.6 FUEL' STORAGE C ri ti cal i ty-S pent Fue1....................................
5-5 Cri ti cal i ty-New Fue1...................................... 5 Drainage..................................................
5-5 Capacity..................................................
5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS......................
5-5 ARKANSAS - UNIT 2 XV Amendment No.60 I
RADI0 ACTIVE EFFLUENTS EXPL0SIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.7 The concentration of the vdrogen/ oxygen shall be limited in the waste gas storage tanks to Region "A" of Figure 3.11.1.
APPLICABILITY: At all times.
ACTION:
a.
When the concentration of hydrogen / oxygen in the waste gas storage tanks enters Region "B" of Figure 3.11-1, corrective action shall be taken to return the concentration values to Region "A" within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
F-The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.7 The concentration.of hydrogen / oxygen in the waste gas holdup system shall be determined to be within the above limits, with the waste gas system in operation, by continuously monitoring with the hydrogen / oxygen monitors required OPERABLE by Table 3.11-3.
ARKANSAS' UNIT 2 3/4 11-14a Amendment No. 61
TABLE 3.11-3 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
Waste Gas Holdup System Explosive Gas Monitoring System a.
Hydrogen monitor (1)
(1) b.
Oxygen monitor (1)
(1)
- During waste gas compressing operation (treatment for primary system offgases.)
ACTION 1 - With both channels inoperable, operation may continue provided grab samples are taken and analyzed 1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations, and 2) daily during other operations.
The analysis of these samples shall be completed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of taking the sample.
ARKANSAS - UNIT 2 3/4 11-14b Amendment No.
61
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10 20 30 40 50 60 70 80 90 100 20 m
HYDROGEN %
FIGURE 3.11-1 HYDR 0 GEN - OXYGEN LIMITS FOR ANO-2 WASTE GAS SYSTEM
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - 10 DINE-131, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates.of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.111.,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radio-nuclide pathways to man in'the areas at or beyond the site boundary. The pathways that were examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 2) deposition of radio-nuclides onto green leafy vegetation with subsequent consumption by man,
- 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposi-tion on the ground with subsequent exposure of man.
3/4.11.2.4 and 5 GASE0US RADWASTE TREATMENT The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radio-active materials in. gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appropriate portions of the systems were*specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents. This specification applies to gaseous radwaste from Arkansas Nuclear One, Unit No. 2.
ARKANSAS - UNIT 2 8 3/4 11-3 Amendment No. 60
7 a
5i i, - -
a e
p RADI0 ACTIVE EFFLUENTS i
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BASES 3
3/4.11.2.6 GAS STORAGE TANKS fi E
M1 Restricting the quantity of radioactivity contained in each gas storage i
tank provides assurance that, in the event of an uncontrolled release of the
[
tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC 1
l at the nearest EXCLUSION AREA boundary will not exceed 0.5 rem. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.
3/4.11.2.7 EXPLOSIVE GAS MIXTURE It is expected that the hydrogen / oxygen concentration will be kept i
within the above limits and therefore not enter the flanrnable or detonable
?
[
region concentrations within the waste gas storage tanks.
dj 0
Q1 i
These levels provide reasonable assurance that no hydrogen / oxygen lj explosion could occur to allow rupture of the waste gas storage tanks. The
(
hydrogen and oxygen limits are based on information in NUREG/CR-2726, " Light
(
l Water Reactor Hydrogen Manual."
~
$1h Grab samples are to be taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations when both hydrogen / oxygen analyzers are out of service. These samples are to be analyzed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to assure that the hydrogen / oxygen concentra-i I
tion is within the limits in Figure 3.11-1.
During other Waste Gas Compressor l
operations, the hydrogen / oxygen concentration is not as subject to change, therefore grab samples are to be taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2
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3/4.11.3 TOTAL DOSE This specification is provided to meet the dose limitations of 40 CFR N
i Part 190 that have now been incorporated into 10 CFR Part 20 by 46 FR 18525.
Y L
The specification requires the preparation and submittal of a Special Report i
whenever the calculated doses from plant radioactive effluents exceed twice arr the design objective doses of Appendix I.
For sites containing up to four
'i j
reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE 2
i PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual 5
[
reactors remain within the reporting requirement level. The Special Report j
will describe a course of action that should result in the limitation of 5
g 2
the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 2
E limits.
For the purposes of the Special Report, it may be assumed that the
}
E dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle m
l sources is negligible, with the exception that dose contributions from other
=
nuclea.r fuel cycle facilities at the same site or within a radius of 8 km must te,oonsidered.
If the dose to any MEMBER OF THE PUBLIC is estimated g
r to exceed the requirements of 40 CFR Part 190, the Special Report with a l
request for a variance (provided the release conditions resulting in viola-3 tion of 40 CFR Part 190 have not already been corrected), in accordance d
l 44 ARKANSAS - UNIT 2 B 3/4 11-4 Amendment No. S 61 g
5 N
s E
RADI0 ACTIVE EFFLUENTS BASES (Continued) with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.11.1'and 3.11.2.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
3/4.11.4 SOLID RADI0 ACTIVE WASTE This specification implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR 50.
ARKANSAS - UNIT 2 B 3/4 11-5 Amendment No. 60, 61 l