ML20153F579
| ML20153F579 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/23/1998 |
| From: | William Reckley Office of Nuclear Reactor Regulation |
| To: | Entergy Operations |
| Shared Package | |
| ML20153F582 | List: |
| References | |
| DPR-51-A-193, NPF-06-A-193 NUDOCS 9809290169 | |
| Download: ML20153F579 (42) | |
Text
_
VaCity g>
t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20666-0001
'+9.....,o ENTERGY OPERATIONS. INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO.1 j
AMENDMENT TO FACILIW OPERATING LICENSE Amendment No.193 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the lic( nsee) dated October 2,1996, as supplemented by letter dated June 18,1997, 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 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 license 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.
9809290169 980923 PDR ADOCK 05000313 P
2.
Accordingly, the license is amended by changes to the Technical Specifications e' 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 (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.193, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
j 3.
The license amendment is effective as of its date of issuance and shall be implemented 4
within 60 days of the date ofissuance. The implementation shall include the relocation of the appropriate provisions to the Offsite Dose Celculation Manual and Process Control Program as described in the licensee's application dated October 2,1996, as supplemented by letter dated June 18,1997, and the staff's sahty evaluation dated September 23,1998.
)
FOR THE NUCLEAR REGULATORY COMMISSION William Reckley, Project Manager l
Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications a
i Date of Issuance: September 23,1998 9
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____.-___._._..___.___-_m ATTACHMENT TO LICENSE AMENDMENT NO.193 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain verticallines indicating the area of change.
REMOVE PAGES INSERT PAGES i,11, lia, iv i,11, lia, iv Sa 6
6 53d through 531 66v through 66z 66v,66w 66aa through 66ff 110cc through 110 zz 110cc,110dd 110aaa,110bbb 111a 126 126 127,127a 127,127a 129 129 141 141 141a,141b 146a,146b 146a 148 148
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TABLE OF CONTENTS SECTION
- TITM, PAGE 1.
DEFINITIONS 1
1.1 ~
RATED POWER 1
1.2 REACTOR OPERATING CONDITION 1
1.3 OPERABLE 2
1.4 PROTECTION INSTRUMENTATION LOGIC 2
1.5-INSTRUMENTATION SURVEILLANCE 3
1.6 POWER DISTRIBUTION 4
1.7 REACTOR BUILDING 5
1.8 FIRE SUPPRESSION WATER SYSTEM 5
1.9 STAGGERED TEST BASIS 5
1.10 DOSE EQUIVALENT I-131 6
1.11 LIQUID RADWASTE TREATMENT SYSTEM 6
1.12 PURGE-PURGING 6
1.13 MEMBER (S) OF THE PUBLIC 6
1.14 EXCLUSION AREA 6
1.15 UNRESTRICTED AREA 6
1.16 CORE OPERATING LIMITS REPORT 6
2.
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7
2.1 SAFETY LIMITS REACTOR CORE 10 7
2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 11 3.
LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 Operational Components 16 3.1.2 Pressurization, Heatup and Cooldown Limitations 16 3.1.3 Minimum Conditions for Criticality 21 3.1.4 Reactor Coolant System Activity 23 3.1.5 Chemistry 25 3.1.6 Leakage 27 3.1.7 Moderator Temperature Coefficient of Reactivity 30 3.1.8 Low Power Physics Testing Restrictions 31 3.1.9 Control Rod Operation 32 3.2 PAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDIN COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 36 3.4 STEAM AND POWER CONVERSION SYSTEM 40 3.5 INSTRUMENTATION SYSTEMS 42 3.5.1 Operational Safety Instrumentation 42 3.5.2 Control Rod Group and Power Distribution Limite 46 3.5.3 Safety Features Actuation System Setpoints 49 3.5.4 Incore Instrumentation
$1 3.6 REACTOR BUILDING 54 3.7 AUXILIARY ELECTRICAL SYSTEMS 56 3.8 FUEL LOADING AND REIVELING 58 3.9 CONTROL ROOM EMERGENCY AIR CONDITIONING AND ISOI.ATION SYSTEM 60 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY-COOLING POND 66a 3.12
-MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c
' Amendment No. u,M,He,193 1
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SECTION TITLE PAGE l
'3.14 HYDROGEN RECOMBINERS 66e 3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g 3.16L 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-FIRE BARRIERS 66q i
3.22 REACTOR BUILDING PURGE ' FILTRATION SYSTEM 66r.
h 3.23 REACTOR BUILDING PURGE VALVES 66t 3.24 EXPLOSIVE GAS MIXTURE 66u 3.25-.
RADIO 7.CTIVE EFFLUENTS 66v 3.25.1 Radioactive Liquid Holdup Tanks 66v 3.25.2 Radioactive Gas Storage Tanks-66w 4.'
SURVEILLANCE REQUIREMENTS 67 4.1 OPERATIONAL SAFETY ITEMS 67 4.2-REACTOR COOLANT SYSTEM SURVEILLAFCE 76 4
4.3 TESTING FOLLOWING OPENING OF SYSTEM 78 4.4 REACTOR BUILDING 79 4.4.1
' Reactor Building Leakage Tests
- 79 5
4.4.2 Structural Integrity 85 t
4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR 1
BUILDING COOLING SYSTEM PERIODIC TESTING 92
~. 4. 5.1 Emergency Core-cooling Systems 92 14.5.2 Reactor Building Coolina Systems 95 4
L 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 Program Verification 104 4.8-EMERGENCY FEEDWATER PUMP TESTING 105
.4.9 REACTIVITY ANOMALIES 106 4.10 CONTROL ROOM EMERGENCY AIR CONDITIONING AND ISOLATION SYSTEM SURVEILLANCE-107 I
4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN RECOMBINERS SURVEILLANCE 109b l
l4.13 EMERGENCY COOLING' POND 110a j
'.4.14.
RADIDACT7.VE MATERIALS SOURCES SURVEl'LLANCE 110b 4.'15 AUGMENTi"3 INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 110c I
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. Amendment No. mom,M,M, Mow,Mo -
LA M, M, M, M, Ma, C+,
193 -
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SECTION.
TITLE PAGE
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4.16 SHOCK SUPPRESSORS (SNUBBERS) 110e 4.17-FUEL HANDLING AREA VENTILATION SYSTEM SURVEILIANCE 110h 4.18 STEAM GENERATOR TUBING SURVEILLANCE
.1103 4.19 Deleted 4.20 Deleted 4.21 Deleted 4.22 Deleted i
4.23 Deleted 4.24 Deleted 4.25
' REACTOR BUILDING PURGE FILTMTION SYSTEM 110x 4.26 REACTOR BUILDING PURGE VALVES 110 4.27 DECAY' HEAT REMOVAL 110aa 4.28 EXPLOSIVE GAS MIXTURE' 110bb 4.29 RADI0 ACTIVE EFFLUENTS 110cc 4.29.1 Radioactive Liquid Noldup Tanks 110cc 4.29.2 Radioactive Gas Storage Tanks 110dd 5.
DESIGN FEATURES 111 5.1 SITE 111 l
5.2-REACTOR BUILDING 112 5.3
. REACTOR 114 5.4-NEW AND SPENT FUEL STORAGE. FACILITIES 116 6.
ADMINISTRATIVE CONTROLS 117 i
6.1 RESPONSIBILITY 117 6.2 ORGANIZATION
'117 l
6.3 FACILITY STAFF QUALIFICATIONS 117 6.4 TRAINING 117 6.5 Deleted 6.6 REPORTABLE OCCURRENCE ACTION 126 l
6.7 SAFETY LIMIT' VIOLATION 126
- 6.8 PROCEDURES AND PROGRAMS 127 6.9 RECORD RETENTION 128
- 6.10 RADIATION PROTECTION PROGRAM 129 6.11 HIGH RADIATION AREA 129
' 6.12 REPORTING - REQUIRDENTS 140 6.13 Deleted 147 l
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 148 l
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2 11a p,444,4G4,449, Amendment No.
___.___________..y._.,
0 9
LIST GF FIGURES Number Title Page 3.1.2-1 REACTOR C001 ANT SYSTEM HEATUP AND COOLDOWN LIMITATIONS 20a 3.1.2-2 REACTOR COOLANT SYSTEM NORMAL OPERATION-NEATUP l
LIMITATIONS 20b i
j 3.1.2-3 REACTOR C00IANT SYSTEM, NORMAL OPERATION COOLDONN l
LIMITATIONS 20c l
3.1.9-1 LIMITING PRESSURE VS. TEMPERATURE FOR CONTROL ROD DRIVE OPERATION WITH 100 STD CC/ LITER H O 33 2
[
3.2-1 BORIC ACID ADDITION TANK VOLUME AND CONCENTRATION VS. RCS AVERAGE TEMPERATURE 35a 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE INDICATION 53a 3.5.4.2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT INDICATION 53b i
3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 3.8.1 SPENT FUEL POOL ARRANGEMENT UNIT 1 59c 3.8.2 MAXIMUM BURNUP VS INITIAL ENRICHMENT FOR REGION 2 STORAGE 59d 3.24-1 HYDROGEN LIMITS FOR ANO-1 WASTE GAS SYSTEM 110be 4.4.2-1 NORMALIZED LIFTOFF FORCE - HOOP TENDONS 85b 4.4.2-2 NORMALIZED LIf70FF FORCE - DOME TENDONS BSc 4.4.2-3 NORMALIZED LIFTOFF FORCE - VERTICAL TENDONS 85d 4.19.1 UPPER TUBE SHEET VIEW OF SPECIAL GROUPS PER SPECIFICATION 4.18.3.a.3 110o2 5.4-1 ANO-1 FFSR LOADING PATTERN 116a l
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Amendment Fo. M,M,4G,M6,M4, iv aw,Me,444,193 l
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1.10 Dose Equivalent I-131 The Dose Equivalent I-131 shall be the concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose
.as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
1.11 Liquid Radwaste Treatment System A Liquid Radwaste Treatment System is a system designed and used for holdup, filtration, and/or demineralization of radioactive liquid effluents prior to their release to the evironment.
1.12 Purge - Purging Purge or Purging is the controlled process of discharging air or gas from a confinement to reduce the airborne radioactivity concentration in such a manner that replacement air or gas is required to purify the confinement.
1.13 Member (s) of the Public l
Member (s) of the Public shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
1.14 Exclusion Area l
The exclusion area is that area surrounding ANO within a minimum radius of.65 miles of the reactor buildings and controlled to the extent necessary by the licensee for purposes of protection of individuals from exposure to radiation and radioactive naterials.
1.15 Unrestricted Area l
An unrestricted area shall be any area beyond the exclusion area 2
boundary.
1.16 Core Operating Limits Report l
The CORE OPERATING LIMITS REPORT is the ANO-1 specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.12.3.
Plant operation within these operating limits is addressed in individual specifications.
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Amendment No. e, es, u s,193 6
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3.25 RADIOACTIVE ErrLUENTS 3.25.1 Radioactive Liquid Holdup Tanks i
Applicability: At all times.
~0biective:
To ensure that the limits of 10 CFR 20 are not exceeded.
Specifications:
l 3.25.1 A.
The quantity of radioactive material contained in each j
unprotected
- outside temporary radioactive liquid storage tank i
shall be limited to less than or equal to 10 curies, excluding j
F tritium and dissolved or entrained noble gases.
3 B.
With the quantity of radioactive natorial exceeding the above i
limit, immediately suspend all additions of radioactive material to the affected tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and describe the events leading to the condition in the next Radioactive Effluent Release Report pursuant to specification 6.12.2.6.
l C.
The provisions of specification 3.0.3 are not applicable.
Bases:
This specification is provided to ensure that in the event of an uncontrolled release of the contents of the tank
- the resulting concentrations would be less than the_ limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest. surface water supply in the unrestricted area.
- Tanks included in this specification are those outdoor temporary tanks that
- 1) are not surrounded by liners, dikes, or walls capable of holding the tank contents, and 2) do not have overflows and surrounding area drains connected to the liquid radwaste treatment systam.
Amendment No, M,4 H,4 6,193 66v
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3.25.2 Radioactive Gas Storage Tanks Applicability: At all times obiective:
To restrict the amount of activity in a radioactive gas holdup tank.
Specifications:
3.25.2 A.
The quantity of radioactivity contained in each gas storage tank shall be limited to 300,000 curies noble gases (Xe-133 equivalent).
B.
With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and describe the events leading to the condition in the next Radioactive Effluent Release Report pursuant to Specification 6.12.2.6.
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C.
The provisions of Specification 3.0.3 are not applicable.
Bases:
The value of 300,000 curies is a suitable fraction of the quantity of radioactive material which if released over a 2-hour period, would result in a total body exposure to a member of the public at the exclusion area boundary of 500 mrem.
This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.
Amendment No. os,u s, m, 193 66w
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4.29 RADI0 ACTIVE EFFLUMTS 4.29.1 Radioactive Liquid Holdup Tanks Applicability: At all times Objective:
To ensure that the limits of 10 CFR 20 are not exceeded.
Specification:
4.29.1 The quantity of radioactive material contained in an outside temporary radioactive liquid storage tank shall be determined to be within the limit of Specificatiota 3.25.1 by analyzing a representative sample of tFs contents of the tank at least once per 7 days when radioactive unterials are being added to the tank.
Bases:
This specification is provided to ensure that in the event of an uncontrolled release of the contents of the tank the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest poteble water supply and the nearest surface water supply in the unrestricted 4
area.
4 i
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t Amendment No. 44, 193
.110cc
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4.29.2 Radioactive Gas Storage Tanks Applicability: At all times ob4ective To ensure meeting the requirements of Specification 3.25.2.
Specification:
4.29.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limits of Specification 3.25.2 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank and the reactor coolant activity exceeds the limits of Specification 3.1.4.1.b.
l Bases:
This specification is provided so that the requirements of Specification 3.25.2 are met.
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r Amendment No. 44,193 11 odd i
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6.6 REPORTABLE EVENT ACTION 1
6.6.1 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
6.6.2 The following actions shall be taken for REPORTABLE EVENTS:
a.
A report shall be submitted to the Commission pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and j
l b.
Each REPORTABLE EVENT shall be reviewed by the PSC, and the results of this review shall be submitted to the SRC and the Vice President, Operations ANO.
6.7 SAFETY LIMIT VIOLATION 1
6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least hot shutdown within one hour.
b.
The Nuclear Regulatory Commission shall be notified pursuant to 10 CFR 50.72 and a repert submitted pursuant to the requirements of 10 CFR 50.36 and Specification 6.6.
6.8 PROCEDURES AND PROGRAMS l
6.8.1 Written procedures shall be established, implenented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
(Deleted) e.
(Deleted) j l
f.
Fire Protection Program Implementation.
g.
New and spent fuel.*?,orage.
h.
offsite Dose Calculation Manual and Process Control Program implementation at the site.
1.
Post accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and the containment atmosphere).
Amendment No. H,M,M,M,M,47, 126 M, M, M, Me, M4, MS, MG.193
1 4
6.8.2 Esch prec: dura of 6.8.1 cbsva, cnd chtnges in intent thoroto, chall be rovicwed end cpprov:d ce 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 alterad.
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, inplemented, and unincained:
A program shall be established to implement the leakage rate testing of the reactor building as required by 10 CFR 50.54 (o) and 10 CFR 50,
)
Appendix J, Option B, as modified by approved exemptions. This l
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 calcultaed reactor building internal pressure for the design basis loss of coolant accident, Pa, is 54 psig.
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 performed in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and s 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.
6.8.5 The Radioactive Effluent Controls Program shall be established, i
implemented, and maintained:
a.
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 lindts are exceeded. The program shall include the following elements:
1)
Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; Amendment No. M,M,M, M,M,M, 127 M, H, M, M9, M4, M9 M4,M9, M&,M9,M&. I93
_.m 2)
Limitations en tha canc:ntretiano of radicactiva matorici rolonsad in liquid offlu:nts to UNRESTRICTED AREAS i
conforming to 10 CFR Part 20, Appendix B, Table 2, Column 2; 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with j
the methodology and parameters in the ODCM; 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive unterials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I; 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calandar year in accordance with the anthodology and parameters in the ODCM at least every 31 days;
)
k 6)
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 i~
releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the 4
annual dose or dose commitment, conforming to 10 CFR 50, 4
Appendix I; 4
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' i
10 CFR 20, Appendix B, -Table 2, Column 1; 8)
Limitations on the annual and quarterly air doses resulting 1
from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; i
i 9)
Limitations on the annual and quarte:1y doses to a MEMBER OF i
THE PUBLIC from iodine-131, iodine-133, tritium, and all
)
radionuclides in particulate form with half lives > 8 days j.
in gaseous effluents released from each unit to areas beyond the site boundary, conforming'to 10 CFR 50, Appendix I; and i
- 10) - 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.
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Amendment No.193 127a l
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h.
Records of in-service inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities required by Section i
17 of the Quality Assurance Manual for operations.
j j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant i
to 10CTR50.59.
]
k.
Records of meetings of the PSC and the SRC.
1.
Records of reviews performed for ch,suges made to the Offsite Dose Calculation Manuni and Process cnntrol Program.
m.
Records of the service lives of the seals of all hydraulic anubbers applicable to Specificetion L 16 including the date at which the servico 11fe commeners and associated installation and naire mano.. rncords, n.
Records of analyr.n:s
- n. m p d. t.e d L.y sir L..li mi i
N cal Environmental MonIi;nrinr1 t'roge.m 6.10 RADIATION PROTECTj0a M<oG H Aci.
Procedures for personnel radistion p m.u.ilun J.. t t h p up.u.3d.:on sin Lunt with the requiremersts of loCFR Pa ce ?0 a n d Y i l.
b2.ipp rov e d, usiniainert and adhered to for all operations 1.n.n ! > i m o v w ii, H e me.. w r. n.
6.11 HIGH RADIAT10N,.t<r,A 6.11.1 In lieu of the "t.onuul d-.,
.o
.!.ou l.; o # 1 setd t. d by paragraph 20.203(c) (2) o f 106"0 0, e b
> ?
m' at on Aw N-dwin>d in 20.202 (b) (3) of 10CTR20) in whi..h tb=
io< n
.,, o f.
.4 1 i..
i.- 1000 mrem /hr or less shall be barrirwtad w.i c..n.picuoi.'./ pn i.M n i high radiation area and shall be c....it.olt s v i s i r.,
- h.
~.4nca of a radiation work permit. Any indiv. dual..< 9to..p o f i nd i.s 'tdu.O s :. cnd t ted to encer such areas shall be pr.orid-d ui e'.
w.w pani +1 by on.
n.
.nn re
. n:
of the followings a.
A radiation monitorio.; devi.
.J.t. b
.o,oio.
osty : od i..ites che radiation dose rate in the u.* a b.
A radiation montLucing d.v,...o.. Lith on i
..o.e d y t a t o.p a t m the radiation dose rate in the me m !. Lu ni, aban a pre-sat integrated dose is racol.ved.
Enh. i n N ;a n h unas with this monitoring device way be mad.: a tte the
'm
,at o 1.: vel in the area has been established and pur.monal have been made knowledgeable of them.
i c.
An individual qualified in radiatiuns protection psocedures who
. re monitori ng %vice. This I
is equipped with a radiation dose individual shall be responsibin for providing positive control over the activities within the area and shall perform periodic 1
radiation surveillance at the frequency specified in the radiation work permit.
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~ Amendment No. M, M, H,
129 1C/2t!*C-C:t:, M, M, M MQ, M4,193 l
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The dose assignments to various duty functions may be estimates based on pocket dosimeter,.TLD, or film badge measurements, small exposures l
totaling less than 20% of the individual total dose need not be accounted i
for.
In the aggregate, at least 80% of the total whole body dose received j.
from external sources shall be assigned to specific major work functions.
j 6.12.2.3 Monthly operating Report Routine reports of operating statistics which includes (1) Average Daily Unit Power Level
, (2) operating Data Report i
(3) Unit Shutdowns and Power Reductions I
(4) Narrative Summary of Operating Experience shall be submitted on a monthly basis to the Director, office of Management and Program Analysis, U.S. Nuclear Regulatory Conadssion, Washington, D.C.
i 20555, with a copy to the appropriate Regional Office by the fifteenth of i
j each month following the calendar month covered by the report.
i 6.12.2.4 Annual Report 1
. All challenges to the pressurizer electromatic relief valve (ERV) and t
nronsurizar safety valves shall be reported annually.
1 i.
m 12.2.5 Annual Radiological Environmental Operating Report
- l 1
The Avnual Radiological Environmental Operating Report covering the operation of l
Phe ontt during the previous calendar year shall'be submitted by May 15 of each faar-che report shall include summaries, interpretations, and analyses of i
tronos of the results of the zadiological environmental monitoring program for t.he reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose calculation Manual (ODCM), and in in cfR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.
.che Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental j
-tadiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and i
tabulated results of these analyses and measurements.
In the event that some individual results are not available for inclusion with the report, the report 4
j-shall be submitted noting and explaining the reasons for the missing results.
[
The missing data shall be submitted in a supplementary report as soon as possible.
6.17.2.6 Radioactive Effluent Releas'e Report **
.The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a.
The report shall include a i
summary of the quantities of radioactive liquid and gaseous effluents and solid l
waste released from the unit. The material provided shall be consistent with the
. objectives outlined in the ODCM and Process Control Program and in conformance with 10 CTR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.
i i
- A single submittal may be made for ANO.
The submittal should combine those 1
sections that are common to both units.
- A single submittal may be made for ANO.
The submittal should combine those sections that are conson to both units. The submittal shall specify the releases of radioactive material from each unit.
Amendment No. 4, 44, 44, 44 44 141 44, 44, 444, i93,
.. ~
6.12.5 Special Reports Special. reports shall be submitted to the Administrator of the appropriate Regional Office within the tine period specified for each report. These
. reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.
a.
Tendon Surveillance, Specification 4.4.2.2 b.
Inoperable containment Radiction Monitors, specification 3.5.1, j
Table 3.5.1-1.
c.
Deleted l
d.
Steam G6nerator Tubing Surveillance - Category C-3 Results, specification 4.18.
e.
Miscellaneous Radioactive Materials Source Leakage Tests, Specification 3.12.2.
f.
Deleted l
1 g.
Deleted l
h.
Inoperable Fire Detectica Instrumentation
'i.
Inoperable Fire Suppression Systems j.
Degraded Auxiliary Electrical Systems, Specification 3.7.2.H.
k.
Inoperable Reactor vessel Level Monitoring Systems, Table 3.5.1-1 1.
Inoperable Hot Leg Level Measurement Systens, Table 3.5.1-1 m.
Inoperable Main Steam Line Radiation Monitors, Specification 3.5.1, Table 3.5.1-1.
a 3
l a
Amendment No. 44, 444, 4 M, H e, 146a 444,193
6.14 OFFSITE DOSE CALCULATIO'l MANUAL (ODCM)
I The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm end trip setpoints, and in the conduct of the radiological environmental monitoring program.
The CDCM shall also contain the' radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive-Effluent Release Reports required by specifications 6.12.2.5 and j
6.12.2.6.
Licensee initiated changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained.
This documentation shall contains 4
1.
Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s), and 2.
A determination that the change (s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; 4
1 l
b.
Shall become effective after approval of the General Mane er, Plant s
Operations; and i
c.
Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent l
Release Report for the period of the report in which any change in the ODCM i.
Was made. Each change shall be identified by markings in the margin of the j
affected pages, clearly indicating the area of the page that was changed and shall also indicate the date (i.e., month and year) the change was implemented.
t I
t i
Amendment No. 44,193 148 m.4 u
pitrg UNITED STATES
{o j
NUCLEAR REGULATORY COMMISSION o
R WASHINGTON, D.C. 20066 4001 l
b,,,,*
4 ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.193 License No. NPF-6 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated j
October 2,1996, as supplemented by letter dated June 18,1997, 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 opcrate 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 Commissicn's regulations; D.
The issuance of this license 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.
l i
i I
, 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-6 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.193, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance and shall be implemented i
within 60 days of the date ofissuance. The implementation shallinclude the relocation of the appropiate provisions to the Offsite Dose Calculation Manual and Process Control Program as described in the licensee's application dated October 2,1996, as supplemented by letter dated June 18,1997, and the staff's safety evaluation dated September 23,1998.
FOR THE NUCLEAR REGULATORY COMMISSION n
l
'l William Reckley, Project Mang r Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: September 23,1998
ATTACHMENT TO LICENSE AMENDMENT NO 193 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-388 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain verticallines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
J REMOVE PAGES INSERT PAGES II, V, VI, X, XIV, XVil ll, V, VI, X, XIV, XVil 1-5 through 1-7 1-5 through 1-7 3-42 through 3-3-57 11-1 through 11-16 11-1 through 11-5 i2-1 through 12-9 B 3-3a through B 3-5 B 11-1 through B 11-5 B 11-1 B 12-1 5-3A 6-13,6-14 6-13,6-14 6-17 through 6-20 6-17 through 6-20 i
6-23 6-23 6-25 6-25 1
j
y DFFfNTTIONS liGIlQli f.AEE 1.0 DEFINITIONS Defined Terms................................................
1-1 Thermal Power................................................
1-1 Rated Thermal Power..........................................
1-1 Operational Mode - Mode......................................
1-1 Action.......................................................
1-1 Operable - Operability.......................................
1-1 Reportable Occurrence........................................
1-1 l
Containment Integrity........................................
1-2 Channel Calibration..........................................
1-2 Channel Check................................................
1-2 l
Channel Functional Test.....................................'.
1-3 Core Alteration..............................................
1-3 Shutdown Margin..............................................
1-3 Identified Leakage...........................................
1-3 l
Unidentified Leakage.........................................
1-4 4
Prassure Boundary Leakage....................................
1-4 Azimuthal Power T11t-Tq......................................
1-4 l
Dose Equivalent 1-131........................................
1-4 1
t-Average Disintegration Energy..............................
1-4
~
Staggered Test Basis.........................................
1-4 Frequency Notation...........................................
1-4 Axial Shape Indtx.............................................
1-5 Reactor Trip system Response Time............................
1-5 Engineered safety Feature Response Time......................
1-5 Physics Tests................................................
1-5 Software.....................................................
1-5 1
i Pl ana r Rad i al Peaki ng Feetor-Fxy.............................
1-5 ARKANSA8 - UNIT 2 1
Amendment No. 25, 71,157
$23i' $!
x
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILIANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE...............................
3/4 2-1 3/4.2.2 RADIAL PEAKING FACTORS.........................
3/4 2-2 3/4.2.3 AZIMUTHAL POWER TILT...........................
3/4 2-3 3/4.2.4 DNBR MARGIN....................................
3/4 2-5 3/4.2.5 RCS FLOW RATE..................................
3/4 2-7 1
3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE...........
3/4 2-8 3/4.2.7 AXIAL SHAPE INDEX..............................
3/4 2-9 3/4.2.8 PRESSURIZER PRESSURE...........................
3/4 2-10 3/4.3 INSTRUMENTATIO_N 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION.............
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................
3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Mcnitoring Instrumentation............
3/4 3-24 I
Remote Shutdown Instrumentation................
3/4 3-36 Post-Accident Instrumentation..................
3/4 3-39
.I 4
i Amendment No. g 40,4 M,443,494, ARKANSAS - UNIT 2 V
y DEFfNfT10N1 SECIION PKaE 1.0 DEFINITIONS Defined Terms................................................
1-1 Thermal Power................................................
1-1 Rated Thurnal Power..........................................
1-1 Operational Mode - Mode......................................
1-1 Action.......................................................
11 Operable - Operability.......................................
1-1 Reportable Occurrence........................................
1-1 l
Containment Integrity........................................
1-2 Channel Calibration..........................................
1-2 Channel Check................................................
1-2 l
Channel Functional Test.....................................'.
1-3 Core Alteration..............................................
1-3 Shutdown Margin..............................................
1-3 Identified Leakage...........................................
1-3 l
Unidentified Leakage.........................................
1-4 Pressure Boundary Leakage....................................
1-4 Azimuthal Power T11t-Tg......................................
1-4 l
Dose Equivalent I-131........................................
1-4 t-Average Disintegration Energy..............................
1-4 Staggered Test Lasis.........................................
1-4 Frequency Wotat1on...........................................
1-4 Ax i al s ha pe I nde x............................................
1-5 Reactor Trip System Response Time............................
1-5 Engineered Safety Feature Response Time......................
1-5 Physics Tests................................................
1-5 Software.....................................................
1-5 Planar Radial Peaking Factor-Fxy.............................
1-S ARKANSAS - UNIT 2 I
Amendment No. 4, H,167 APR 1. ' '!m..
v 4
INDEX DEFINITIONS i
PAGE SECTION 1-5 Liquid Radwaste Treatment System............................
1-5 Member (s) of the Public.....................................
1-5 l
Purge - Purging..................
1-6 l
Exclusion Ares..............................................
1-6 l
Unrestricted Area...........................................
1-6 l
Core operating Limits Report................................
l 1
ARKANSAS - UNIT 2 II Amendment No. 49,4n 193
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILIANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE...............................
3/4 2-1 3/4.2.2 RADIAL PEAKING FACT 0RS.........................
3/4 2-2 3/4.2.3 AZIMUTHAL POWER TILT...........................
3/4 2-3 3/4.2.4 DNBR MARGIN....................................
3/4 2-5 3/4.2.5 RCS FLOW RATE..................................
3/4 2-7 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE...........
3/4 2-8 3/4.2.7 AXIAL SHAPE INDEX..............................
3/4 2-9 3/4.2.0 PRESSURIZER PRESSURE...........................
3/4 2-10 i
1
-3/4.3 INSTRUMENTATION j
3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION.............
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................
3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...........
3/4 3-24 Remote Shutdown Instrumentation................
3/4 3-36 Post-Accident Instrumentation..................
3/4 3-39
.I Amendment No. g60,M7,444,4M, ARKANSAS - UNIT 2 V
l l
i 2
INDEX l
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i
SECTION PAGE 3/4.8.2 ONSITE' POWER DISTRIBUTION SYSTEMS A. C.. Distribution - 0perating........................ 3/4 8-6 A. C. Distribution - Shutdown......................... 3/4 8-7 D. C. Di stribution - Operating........................ 3/4 8-8 D. C. Distri bution - Shutdown......................... 3/4 8-10 Containment Penetration Conductor Overcurrent
- . ~
Protecti ve Devices.................................. 3/4 8-11
)
3/4.9 REFUELING OPERATIONS 1
3/4.9.1 BORON CONCENTRATION...................................
3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................'. 3/4 9-2 3
3/4.9.3 DECAY TIME AND SPENT FUEL ST0 RAGE..................... 3/4 9-3 3/4.9.4 CONTAINMENT 8UILDING PENETRATIONS.....................
3/4 9-4 3/4.9.5 COMMUNICATIONS........................................
3/4 9-6 j
3/4.9.6 REFUELING MACHINE OPERA 81LITY.........................,. 3/4 9-7
}
3/4.9.7 CRANE TRAVEL - SPENT FUEL POOL BUILDING............... 3/4 9-8" i
I 3/4.9.8 SHUTDOWN COOLING AND CDOLANT CIRCULATION..............
3/4 9-9 3/4.9.9 WATER LEVEL - REACTOR VESSEL.......................... 3/4 9-10 e
!~
3/4.9.10 SPENT FUEL POOL WATER LEVEL........................... 3/4 9-11 3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM................. 3/4 9-12 3/4.9.12 FUEL ST0 RAGE.......................................... 3/4 9-14 1
3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN....................................... 3/4 10-1 i
3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION
}
L I MI TS.............................................. 3/ 4 10- 2 3/4.10.3 REACTOR C00LANT L00PS.................................
3/4 10-3 j
i i
ARKANSAS - UNIT 2 Amendment No. 29, 60 II t
em w
,.,e y
. _. _ - _ ~ _..
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.10.4 CENTER CEA MISALIGNMENT.................................
3/4 10-4 3/4.10.5 MINIMUM TDiPERATURE FOR CRITICALITY.....................
3/4 10-5 3/4.11 RADIOACTIVE EFTLUENTS 3
3/4 11-1 l
3/4.11.1 LIQUID HOLDUP TANKS...................
3/4 11-2 l
3/4.11.2 GAS STORAGE TANKS......................................
3/4.11.3 EXPLOSIVE GAS MIXTURE..................................
3/4 11-3 I
i l
ARKANSAS - UNIT 2 X
Amendment No. 40.193
-l
, ~ -
~., - -
. - - ~... -. ~ _ _... - - - -. - - -.. _. -.. =. - - - - - _..
I l
INDEX RASES l
SECTION PAGE l
3/4 9.5 COMMUNICATIONS....................................... B 3/4 9-2 i
3/4.9.6 '
REFUELING MACHINE OPERABILITY........................ B 3/4 9-2 i
3/4.9.7-CRANE TEAVEL - SPENT IVEL STORAGE BUILDING........... B 3/4 9-2 3/4.9.8 COOLANT CIRCUIATION.................................. B 3/4 9-2 3/4.9.9 and 3/4.9.10 WATER LEVEL - REACTOR VESSEL AND STORAGF POOL WATER LEVEL............................. B 3/4 9-3 3/4.9.11 FUEL HANDLING AREA VENTIIATION SYSTEM................ B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..................................;... B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMI TS............................................... 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 RADICACTIVE EFFLUENTS-3/4 11.1 LIQUID HOLDUP TANKS.................................. B 3/4 11 l 3/4 11.2 GAS STORAGE TANKS.................................... B 3/4 11-1 l
3/4 11.3 EX P LO5 IVE GAS MIXTURE................................ B 3 / 4 11-1 l
ARKANSAS - UNIT 2 XIV Amendment No. 44,44,193
,.w e.
e--,
,-m
~
=. - - -
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 REPORTABLE EVENT ACTION.....................................
6-12 6. *1 SAFETY LIMIT VIOLATION......................................
6-13 6.8 PROCEDURES AND PROGRAMS.....................................
6-13 l
6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS........................................
6-14a l
6.9.2 SPECIAL REPORTS........................................
6-16 6.9.3 RADIOACTIVE EFFLUENT RELEASE REPORT....................
6-18 l
6.9.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT. [...
6-20 l
6.9.5 CORE OPERATING LIMITS REPORT...........................
6-21 6.10 RECORD RETENTION...........................................
6-22 i
6.11 RADIATION PROTECTION PROGRAM...............................
6-23 6.12 Deleted....................................................
6-23 l
6.13 HIGH RADIATION AREA........................................
6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM1.....................
6-25 6.15 CONTAINMENT LEAKAGE RATE TESTING PR0 GRAM...................
6-26 4
ARKANSAS - UNIT 2 XVII Amendment No.
40, M, H,M4, f 76,
DEFINITIONS AXIAL SHAPE INDEX
?.22 The AXIAL SHAPE INDEX shall be the power generated in the lower. half of the core less the power generated in the upper half of the core divided by the sum of these powers.
REACTOR TRIP SYSTFM RESPONSE TIME 1.23 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.
Y.NGINEERED SAFETY FEATURE RESPONSE TIME 1.24 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e.,
the valves travel to their required positions, pung discharge l
pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.
J PHYSICS TESTS l
i 1.25 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commissior.
l SOFTWARE 1.26 The digital computer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation and procedures.
PLANAR RADIAL PEAXING FACTOR Ixy 1.27 The PLANAR RADIAL PEAXING FACTOR is the ratio of the peak to plane average power density of the individual fuel rods in a given horizontal plane, excluding the effects of azimuthal tilt.
LIQUID RADWASTE TREATMENT SYSTEM 1.28 A LIQUID RADWASTE TREATMENT SYSTEM is a system designed and installed to reduce radioactive liquid effluents from the unit. This is accomplished by providing for holdup, filtration, and/or domineralization of radioactive liquid effluents prior to their release to the environment.
MEMBER (S) OF THE PUBLIC l
1.29 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility,.its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
PURGE-PURGING 1.30 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to reduce airborne radioactive concentrations in such a manner that replacement air or gas is required to purify the confinement.
Amendment No. g49,4M ARXANSAS - UNIT 2 1-5
l DEFINITIONS EXCLUSION AREA 1.31 The EXCLUSION AREA is that area surrounding ANO within a minimum radius of
.65 miles of the reactor buildings and controlled to the extent necessary by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.
UNRESTRICTED AREA 1.32 An UNRESTRICTED 7JTJL shall be any area at or beyond the exclusion area boundary.
CORE OPERATING LIMITS REPORT 4
1.33 The CORE OPERATING LIMITS REPORT is the ANO-2 specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9.5 Plant operation within these operating limits is addressed in individual specifications.
4 Amendment No. g449,444 ARKANSAS - UNIT 2 1-6 l
.. -.., - ~.....
. -.. ~.... -. -.... -... -..... -. -..... -..
t j.
i I'
1~
4 i
a i
I J
j-0%
t l'
e i
1 9
THIS PAGE INTENTIONALLY LErr SLANK l
ARKANSAS - UNIT 2 1-7 Amendment No. 40 +44,M4 19$
4-r
TABLE 1.1 OPERATIONAL MODES REACTIVITY 1 RATED AVERAGE COOLANT MODE CONDITION. X,ff THERMAL POWER
- _ TEMPERATURE 1.
POWER OPERATION 1 0.99
> 55 t 300'F 2.
STARTUP 0
1 99
< 5%
> 300'F 3.
HOT STANDBY
< 0.99 0
1 300*F 4.
HOT SHUTDOWN
< 0.99 0
300*F> T
> 200'F avg 5.
COLD SHUTDOWN
< 0.99 0
200*F' 6.
REFUELING **
0 1
95 0
1 140'F l
l l
l Excluding decar heat.
Reactor vessel head unbolted or removed and fuel in the vessel.
i l
l l
t ARKANSAS - UNIT 2 1-8 Amendment No.60 4
__m 3/4.11 RAD 20 ACTIVE ErrLUENTS 3/4.11.1 LIQUID HOLDUP TANKS
- LIMITING CONDITION roR OPERATION 2.11.1 The quantity of radioactive material contained in each unprotected outside temporary radioactive liquid storage tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolvad or entrained noble gases.
APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material exceeding the above limit, immediately suspend all additions of radioactive material to the affected tank and within 48 nours reduce the tank contents to within the limit and describe the events leading to the condition in the next Radioactive Effluents Release Report pursuant to Specification 6.9.3.
b.
The provisions of specification 3.0.3 are not applicable.
i SURVEILLANCE REQUIREMENTS 4.11.1 The quantity of radioactive material contained in each unprotected outside temporary radioactive liquid storage tank shall be determined to be within the above lindt by analyzing a representative sample of the contents of the tank at least once per 7 days when radioactive materials are being added to the tank.
- Tanks included in this specification are those outdoor temporary tanks that
- 1) are not surrounded by liners, dikes, or walla capable of holding the tank contents, and 2) do not have overflows and surrounding area drains connected to the liquid radwaste treatment system.
l ARKANSAS - UNIT 2 3/4 11-1 Amendment No. 40,M4,46,193 l '
--7---
y wr y
e
RADIOACTIVE EFFLUENTS 3/4.11.2 GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2 The quartity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 300,000 curies noble gases (considered as Xe-133).
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any gas storage tank a.
exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and describe the events leading to the condition in the next Radioactive Effluent Release Report pursuant to specification 6.9.3.
~
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2 The quantity of radioactive material contained in each gas stotage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank and the reactor coolant activity exceeds the limits of Specification 3.4.8.
ARKANSAS - UNIT 2 3/4 11-2 Amendment No. 40,H4,193
_.._.____._.m.-_.
RADIOACTIVE EFFLUENTS 3/4.11.3 EXPLOSIVE GAS MIXTURE l
LIMITING CONDITION FOR OPERATION 3.11.3 The concentration of the hydrogen / 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 />.
b.
The provisions of Specification 3.0.3 are not applicable.
,SURVEILIANCE REQUIREMENTS 4.11.3 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 11-3 Amendment No. 4,G,H4,193
~_
TABLE 3.11-3 EXPLOSIVE GAS MONITORING INSTRUMENTATION Minimum channels Instrument Operable Applicability Action 1.
Waste Gas Holdup System Explosive Gas Monitoring Sustem-1 a.
Hydrogen monitor 1
1 b.
Oxygen monit'.;
1
- During waste gas compressing operation (treatment for primary system off gases.)
ACTION 1 -
With both channels inoperable, operation may ceintinue provideC grab samples are taken 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 samplea 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.
f j
N SAS - UNIT 2 3/4 11 4 Amendment No. M,M,M,M4,193
E 20 18 16-14-t Z 12 m
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8-REGION B (UNACCEPTABLE OPERATION) 6 (4,4) 4 2
REGION A (ACCEPTABLE OPERATION)
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O 10 20 30 40 50 60 70 80 90 100 HYDROGEN %
HYDROGEN - OXYGEN LIMITS FOR ANO-2 WASTE GAS SYSTEM Figare 3.11-1 i
ARKANSAS - UNIT 2 3/4 11-5 Amendment No. 60,64, M,4M,193 l
RADI0 ACTIVE KFTLUENTS LIOUID HOLDUP TANKS
- LTMTTTNG CON'DTTTON TOR OPTW ATTON 3.11.1.4 The quantity of radioactive asterial contained in each unprotected outside temporary radioactive liquid starage tank shall bs limited to less than or equal to 10 curies, exclutant; tritius and dissolved or entrained noble gaser.
APPLICABILITY: At all times.
ACTION:
a.-
With the quantity of radioactive saterial exceeding the above limit, immediately suspend all additions of radioactive satorial to the affected tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions of Specification 3.0.3 are not applicable.
l SURVIILLANCE REOUTREMENTS 4 4L.I.6 Th..pantity of esdioactive material contained in each oupcotactad outside temporary radioactive liquid storage tank shall be datermined to be within the above limit by analyzing a representative
<teple of the contenta of the tank at least once per 7 days when radioactive matarisis are being added to the tank.
- Tanks included in this specification are those outdoor temporary tanks that do not have 1) liners, dikes or walls capable of holding the tank 4
contents, or 2) tank overflows and surrounding area drains connected to the LIQUID RADWASTI TREATNENT SYSTEM.
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4 ARKANSAS - UNIT 2 3/4 11-6 Amendment No. #f, 134 MnY t
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3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that, in the event of an uncontrolled release of the contents of the tanks, the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage 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 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.
L.11.3 EXPLOSIVE GAS MIXTURE It is expected that the hydrogen / oxygen concentration will be kept within the limits and therefore not enter the flammable or detonable region concentrations within the waste gas storage tanks.
]
These levels provide reasonable assurance that no hydrogen / oxygen explosion j
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 Water Reactor Hydrogen Manual."
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 3.11-1.
During other Waste Gas compressor operations, the hydrogen / oxygen concentration is not es 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 />.
l ARKANSAS - UNIT 2 B 3/4 11-1 Amendment No. 64,193
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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety Limit is i
violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
b.
The Vice President, operations ANO and the SRC shall be notified
{
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
The Nuclear Regulatory Commission shall be notified pursuant to 10CFR50.72 and a report submitted pursuant to the requirements of 10CFR50.36 and Specification 6.6.
1 6.8 PROCEDURES AND ILOCRAMS l
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
-c.-
Surveillance and test activities of safety related (quipment.
d.
(Deleted) e.
(Deleted) f.
Fire Protection Program implementation.
g.
Modification ox Core Protection Calculator (CPC) Addressable constants. These procedures should include provisions to assure that sufficient margin is maintained in CPC Type I addressable constants to avoid excessive operator interaction with the CPCs during reactor operation.
NOTE:
Modifications to the CPC software (including changes of algorithms and fuel cycle specific data) shall be performed in accordance sith the most recent version af "CPC Protection Algorithm Software Change Procedure,"
CEN-39 (Al-P that has been deterndned to be applicable to the facility. Additions or deletions to CPC addressable constants or changes to addressable constant software lindt values shall not be implemented without prior NRC approval, h.
New and spent fuel storage.
i.
j.
Post accident sampling (includes sampling of reactor coolant, rcdioactive iodines and particulates in plant gaseous effluent, and the containment atmosphere).
6.8.2 Each procedure of 6.8.1 above, and changes in intent thereto, shall be reviewed and approved as required by the QAMO prior to implementation and reviewed periodically as set forth in administrative procedures.
i ARKANSAS - UNIT 2 6-13 Amendment No M,M,43,M,44,43,
'gM,44, G4,44, M4, MG, MG, MG, MG
ADMINI97 RAT 2VE 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 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 Licerse on Unit 2.
j c.
The change is documented, reviewed and approved as required by the QAMO, within 14 days of implementation.
6.8.4 The following program shall be established, implemented, and maintained:
a.
Radioactive Effluent Controls Program 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:
1)
Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforndng to 10 CFR Part 20, Appendix B, Table 2, Column 2; 3)
Monitoring, sampling, and analysis of radioactive liquid and gas eous effluents in accordance with 10 CFR 20.1I02 and with the met;.odology and parameters in the ODCM; 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive naterials in liquid effluents released from each unit to UNRESTRICTED AREAS, conforming to 10 CFR 50, Appendix I; 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the CDCM at least every 31 days; 6)
Limitations on the functient?. capability and use of the liquid and gaseous effluent treatmer.t systems to ensure that appropriate portions of these systens are used to reduce releases of radioact$vity 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, Appendir 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 2, Column 1; ARKANSAS - UNIT 2 6-14 Amendment No.4, M, ~4, M, M,48, W, Me,444,MG e E
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ADMINISTRATIVE CONTROL 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous affluents released from each unit to areas beyond the site boundary, conforming to 10 CTR 50, Appendix I; and 10)
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.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Administrator of the Regional Office unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been nanufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and rpecifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion r*
the startup test program, (2) 90 days following resumption or commenceu me, of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power opiration), aapplementary reports shall be submitted at 13ast every three months until all three events have been completed.
ARKANSAS - UNIT 2 6-14a Amendment No.6,M,M,M,M,H,M4, kM,4Ma %Q,193 j
i l
ADMINISTRATIVE CONTROLS h.
Deleted l
l 1.
Inoperable Containment Radiation Monitors, l'
Specification 3.3.3.1.
j.
Steam Generator Tubing Surveillance -- Category C-3 Re:Jults, Sp_cification 4.4.5.5.
k.
Maintenance of Spent ruel Pool Structural Integrity, Specification 3.7.12.-
1.
Deleted l
m.
Deleted l
n.
Irioperable Reactor Vessel Level Monitoring System (RVLMS),
Specification 3.3.3.6, Table 3.3-10 Item 14.
o.
Inoperable Main Steam Line Radiation Monitors, Specification 3.3.3.1, l
Table 3.3-6.
ARKANSAS - UNIT 2 6-17 Amendment No. 40,64,M,
+sa,++6,464,193
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ADMINjSTRATIVE CONTROLS RADIOACTIVE ErrLUENT RELEASE REPORT
- l 6.9.3 The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid wasto released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.l.
- A single submittal may be made for ANO.
The submittal should combine those sections that are common to both units. The submittal shall specify the releases of radioactive material from each unit.
l ARKANSAS - UNIT 2 6-18 Amendment No. 40,94,u4,HA 193
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I' ARMAN8A8 - UNIT 2 6-19 Amendmerit No. 40,444,193
n.
ADMINISTRATIVE CONTROL ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.4 The Annual. Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shal be submitted by May 15 of each year. The report shall include summarier, intstepretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the cbjectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendi:: I, Sections IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The misming data shall be submitted in a supplementary report as soon as pna.=fble.
aingle submittal may be made for ANO.
The submittal should combine those
.rutit,nr that are common to both units.
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l ARKANSAS - UNIT 2 6-20 Amendment No. 40,G4,m 193 l
~
. ~ -. -.
ADMINISTRAT.IVE CONTROL f.
Reestds of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff, h.
Records of in-service f.nspections performed pursuant to these Technical Specificatiens.
1.
Records of Quality Assurance activities required by the QA Manual.
j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10C(R50. 59.
k.
Records of meetings of the PSC and the SRC.
1.
Records of changes to the Core Protection Calculator System (CPCS) SOFTWARE. Changes to the CPCS SOFTWARE shall be made in accordance with methods approved by the NRC.
Thes e1.' records shall include the following:
1.
Purpose of change.
2.
Detailed description of changes including algorithms, changes to the assembly listings, checksums and disk identification numberw.
3.
Summary of validation test results.
m.
Records of reviews performed for changes unde to the Offsite Dose Calculation Manual and Process Control Program.
n.
Records of the service lives of the seals of all hydraulic anubbers required by Specification 3.7.8, including the date at whien the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 (DELETED)
ARKANSAS - UNIT 2 6-23 Amendment No. H,40,e,M,H 4,193
ADMINISTRATIVE CONTROL i
6.12.2 (DELETED) l 4.13 NIGH RADIATION AREA 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CTR 20, each high radiation area (as defined in 20.202(b)(3) of 10 CFR 20) in which the intensity of radiation is 1000 mrom/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring the issuance of a radiation work permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more cf the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alares when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made 4
knowledgeable of them.
4 c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control nyer the activities within the arta and shall perform periodic radiation surveillance at the frequency specified in the radiation work permit.
6.13.2 The requirements of 6.13.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 ares /hr.
In addition, locked doors shall be provided to prevent unauthorised entry into such areas and access to these areas shall be maintained under the administrative control of the shift gepervisor on duty and/or the designated radittion protectnen sanager.
1 ARKANSAS-UNIT 2 6-24 Cidit 46164 Ott656t Rf, 1999 Amendment No. 11, 19, 69, 90, 90, 116
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ADMINISTRATIVE CONTROL 4
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM)
The CDCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the 4
calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.
The CDCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Radioactive Effluent Release and Annual Radiological Environmental operating Reports required by Specifications 6.9.3 and 6.9.4.
Licensee initiated changes to the ODCM:
Shall be documented and records of reviews performed shall be retained.
a.
This documentation shall contain:
1.
Sufficient information to support the change (s) together with the appropriate analyses or evaluations justifying the change (s),
t 2.
A determir. tion that the change (s) maintain the levels of radioactit effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; b.
Shall become effective after approval of the General Manager, Plant operations; and c.
Shall be submitted to the NRC in the form of a complete, legible copy of the entire CDCM as a part af or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM i
was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed and shall also indicate the date (i.e., month and year) the change was implemented.
1
)
ARKANSAS - UNIT 2 6-25 Amendment No. 40,193