ML19210D135
| ML19210D135 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/07/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210D136 | List: |
| References | |
| NUDOCS 7911200573 | |
| Download: ML19210D135 (9) | |
Text
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313_
ARKANSAS NUCLEAR ONE - UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE kendment No. 44 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the 1.icensee) dated March 28, 1977, 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 Cpapter I; The facility will operate in confonnity with the application, B.
the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance (1) that the activities authorized C.
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; The issuance of this amendment will not be inimical to the comon D.
defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.
51 of the Comission's regulations and all applicable requirements have been satisfied.
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. Accordingly, the' license is amended by changes to the Technical 2.
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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.44, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of its 3.
issuance.
FOR THE NUCLEAR REGULATORY COMMISSION S. I Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 7, 1979 4
13/3
ATTACHMENT TO LICENJE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Revise Appendix A Technical Specifications as follows:
Remove Pages Insert Pages i & 11 i & ii 66r & 66s 110x & 110y Changes on the revised pages are identified by marginal lines.
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TABLE OF CONTENTS SECTION TITLE PAGE 1.
DEFINITIONS 1
1.1 RATED POWER 1
1.2 REACTOR OPERATING CONDITIONS 1
1.3 OPERABLE 2
1.4 PROTECTION INSTRUMENTATION LOGIC 2
1.5 INSTRUMENTATION SURVEILLANCE 3
1.6 QUADRANT POWER TILT 4
1.7 REACTOR BUILDING 4
1.8 FIRE SUPPRESSION WATER SYSTEM 5
'2.
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7
2.1 SAFETY LIMITS, REACTOR CORE 7
2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRU-MENTATION 11 3.
LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 Operational Components 16 3.1.2 Pressurization, Heatuo and Cooldown Limitations 18 3.1.3 Minimum conditions for Criticality 21 3.1.4 Reactor Coolant System Activity 22 3.1.5 Chemistry 25
.3.1.6 Leakaae 27 3.1.7 Moderator Temoerature Coefficient of Reactivity 30 3.1.8 Low Power Physics Testino Restrictions 31 3.1.9 Control Rod Operation
'32 3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING 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 Grouo and Power Distribution Limits 46 3.5.3 Safety Features Actuation System Setpoints 49 3.5.4 In-Core Instrumentation 51 3.5.5 Fire Detection Instrumentation 53d 3.6 REACTOR BUILDING 54 3.7 AUXILIARY ELECTRICAL SYSTEM 56 3.8 FUEL LOADING AND REFUE(ING 58 3.9 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM 60 3.10 SECONDAP.Y SYSTEM ACTIVITY 66 3.11 EMERGENCY C0OLING POND 66a 3.12 MISCELLANE0US RADI0 ACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c 3.14 HYDROGEN PURGE SYSTEM 66e 3.lb FUEL HANDLING AREA VENTILATION SYSTEM 66g 3.16 SHOCK SUPPRESSORS (SNUBBERS) 66i 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
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}j6 66p 3.21 PENETRATION FIRE BARRIERS 66q 3.22 REACTOR BUILOING PURGE FILTRATION SYSTEM 66r l
SECTION TITLE PAGE 4.
SURVEILLANCE REQUIREMENTS 67 4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 76 4.3 RLACTOR COOLANT SYSTEM INTEGRITY FOLLOWING ENTRY 78 4.4 REACTOR BUILDING 79 4.4.1 Reactor Building Leakace Test 79 4.4.2 Structural Integrity 85 4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 92
'4.5.1 Emeroency Core Cooling System 92 4.5.2 Reactor Building Cooling System 95 4.6 AUXILIARY ELECTRICAL SYSTEM TESTf 100 4.7 REACTOR CONTROL ROD SYSTEM TESTS 102 4.7.1 Control Rod Drive System Functional Tests 102 4.7.2 Control Rod'Proaram Verification 104 4.8 EMERGENCY FEEDWATER PUMP TESTING 105 4.9 REACTIVITY ANOMALIES 106 4.10 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM SURVEILLANCE 107 4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN PURGE SYSTEM SURVEILLANCE 109b 4.13 EMERGENCY C0OLING POND 110a 4.14 RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT llOc 4.16 SHOCK SUPPRESSORS (SNUBBERS) 110e 4.16.1 Hydraulic Shock Suporessors 110e 4.17 FUEL HANDLING AREA VENTILATION 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 HALON SYSTEMS 110u
.4.23 FIRE HOSE STATIONS 110v 4.24 PENETRATION FIRE BARRIERS 110w 4.25 REACTOR BUILDING PURGE FILTRATION SYSTEM 110x l
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 LIMIT VIOLATION 126 6.8 PROCEDURES 127 6.9 RECORD RETENTION 128 6.10 RADIATION PROTECTION PROGRAM 129 6.11 DELETED 129 6.12 REPORTING REQUIREMENTS 140
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AmendmentNo.//,/[,[f,//,44 ii
3.22 Reactor Building Purge Filtration System Applicability This specification applies to the operability of the reactor building purge filtration system.
Objective To assure that the reactor building purge filtration syste= will perform within acceptable levels of efficiency and reliability.
Specification 3.22.1 The reactor building purge filtration system shall be operable whenever ' irradiated fuel handling operations are in progress in the reactor building and shall have the following perform-ance capabilities:
The results of the in-place cold DOP and halogenated hydro-a.
carbon tests at design flows (+ 10%) on HEPA filters and charcoal adsorber banks shall show > 99% DOP removal and
> 99% halogenated hydrocarbon removal.
b.
The results of laboratory carbon sample analysis shall show
> 90% radioactive methyl iodide removal at a velocity within
[ 20% of system design, 0.05 to 0.15 mg/m3 inlet methyl iodide concentration, > 70% R. H. and > 125F.
Fans shall be shown to operate within ; 10% design flow.
c.
d.
The pressure drop across the combined HEPA filters and char-coal adsorber banks shall be less than 6 inches of water at system design flow rate (1 10%).
Air distribution shall be uniform within + 20% across HEPA e.
filters and charcoal adsorbers when tested initially and after any maintenance or testing that could affect the air distribution within the reactor building purge filtration system.
3.22.2 If the requirements of Specification 3.22 1 cannot be met, either:
a.
Irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be completed); or, b.
Isolate the reactor building purge system.
Base s The reactor building purge filtration system is designed to filter the reactor building atmosphere during normal operations for ease of person-nel entry into the reactor building.
This specification is intended to require the system operable during fuel handling operations, if the system
} 373
)ib Amendment No. 44 66r
is to be. used, to limit the release of activity should a fuel handling accident occur. The system consists of one circuit containing a supply and an exhaust fan and a filter train.
The filter train consists of a pre-filter, a HEPA filter and a charcoal adsorber in series.
High efficiency particulate air (HEPA). filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the potential release of radioiodine to the environment.
The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers anc a HEPA efficiency of a least 99 percent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive methyl iodide re= oval efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10CFR100 guidelines for the accidents analyzed.
Operation of the fans significantly different from the design flow will change the recoval efficiency of the HEPA filters and charcoal adsorbers.
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P Amendment No.44 66 5
4.25 Reactor Buildino Purge Filtration System Applicability Applies to the surveillance of the reactor building purge filtration system.
Objective To ' verify an acceptable level of efficiency and operability of the reactor building purge filtration system.
Specification
- 4. 25.1 The pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow rate (+10%) within 720 system operating hours prior to initial irradiated Tuel handling operations.
4.25.2 Initially 'and after any maintenance or testing that could affect the air distribution within the reactor building purge system, air distribution shall be demonstrated to be uniform within
- 20% across HEPA filters and charcoal adsorbers.
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- 4. 2E 3a.
The tests and sample analysis of Specification 3. 22.1.a,b, 6 c.
shall be performed within 720 system operating hours prior to initial irradiated fuel handling operations in the reactor building, and prior to irradiated fuel handling in the reactor build-ing following significant painting, fire or chemical release in any ventilation :one communicating with the system, b.
Cold DOP testing shall also be performed prior to irradiated fuel handling in the reactor building after each ecmplete or partial replacement of a HEPA filter bank or after any structural maintenance on the system housing.
c.
Halogenated hydrocarbon testing shall also be performed prior to irradiated fuel handling in the reactor building after each complete or partial replacement of a charcoal adsorber bank or after any structural maintenance on the system housing.
Bases Since the reactor building purge filtration system may be in operation when the reactor is operating, its operability must be verified before handling of irradiated fuel.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indi-cate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per refueling period to show system performance capability.
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Amendment No. 44 110 x
The frequency of tests.and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perfom as evaluated.
The charcoal adsorber efficiency test procedures should allow for obtaining at least two samples.
Each sample ghould be at least two inches in diameter and a length equal to the thickness of the bed. Tests of the charcoal adsorbers with halogenated hydrocarbon refrigerant and of the HEPA filter bank with DOP aerosol shall be perfomed in accordance with ANSI N510 (1975) "Standani for Testing of Nuclear Air Cleaning Systems." Any HEPA filters found defective shall be replaced with filters qualified according to Regulatory Position C.3.d. of Regulatory Guide 1.52.
Radioactive methyl iodide removal efficiency tests shall be perfomed in accordance with RUT Standard M16-IT.
If laboratory test results are unacceptable, all charcoal adsor-bents in the system shall be replaced with charcoal adsorbents qualified according to Regulatory Guide 1.52.
13/3 12, Amendment No. 44 110y