ML20003C940
| ML20003C940 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/10/1981 |
| From: | Clark R, Reid R Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20003C941 | List: |
| References | |
| DPR-51-A-053, NPF-06-A-021 NUDOCS 8103180853 | |
| Download: ML20003C940 (10) | |
Text
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UNITED STATES I#*g NUCLEAR REGULATORY COMMisslON g
WASHINGTON, D. C. 20065
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313_
ARKANSAS NUCLEAR ONE - UNIT NO. l g
AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 53 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The application for amendment by Arkansas Power and Light Company A.
(the licensee) dated October 20, 1980, 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; The facility will operate in confomity 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 l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; I
l 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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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachr,ent to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
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(2) Te_chnical Specifications lhe Technical Specifications contained in Appendices A and B, as revised through Amendment No. 53, are hereby incorporated in the license. The licensee shall operate the facility in accordance witle the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Mi
/
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 10, 1981 L
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1 ATTACHMENT TO LICENSE'AMENDriENT NO. 53 FACILITY OPERATING LICENSE NO. DPR-51 i
DOCKET NO. 50-313 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 area of change.
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Pages 11 129
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4 SECTION TITLE PAGE 4.
SURVEILLANCE REQUIREMENTS 67 4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 76 4.3 REACTOR COOLANT SYSTEM INTEGRITY FOLLOWING ENTRY 78 4.4 REACTOR BUILDING 79 4.4.1 Reactor Building Leakage 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 Emergency Core Cooling System 92 4.5.2 Reactor Building Cooling System 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 Program 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 COOLING POND 110a 4.14 RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 110c 4.16 SHOCK SUPPRESSORS (SNUBBERS) 11('.a 110e 4.16.1 Hydraulic Shock Suppressors 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 1.10q 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 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 R2 PORTABLE 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 HIGH RADIATION AREA 129 l
6.12 REPORTING REQUIREMENTS-140' Amendment No.
, 24, $$, 34, 11
, 53
h.
R: cords of in-carvics in:pacticna p2rformid purcu:nt to thtco Technical Specifications.
1.
Records of Quality Assurance activities required by Section 17 of the Quality Assurance Manual for Operations.
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Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PSC and the SRC.
1.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.
6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved saintained and adhered to for all operations involving personnel radiation exposure.
6.11 HIGH RADIATION AREA 6.11.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area (as defined in 20.202(b)(3) of 10 CFR 20) in which the intensity of radiation is 1000 arem/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 Special Work Permit (SWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of 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 alarms when a present 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 estab-lished and personnel have been made knowledgeable of them.
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 over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the Special Work Permit.
6.11.2 The requirements of-6.11.1 above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and access to these areas shall be maintained under the administrative control'of the Shift Supervisor on duty and/or the Hcalth Physics. Supervisor.
- Health Physics and Operations personnel shall be taempt-from the SWP require-ments; however, entry into high radiation areas for performing their assigned duties shall be controlled tar the issuance of a Radiation Work Permit provided they comply with approved radiation protection procedures for entry into high
. radiation areas.
9tddi
-129
'(Next page is 140)
Amendment No.16, 34, 53 did 9didWdi 24, 1989,
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UMTED STATES NUCLEAR REGULATORY COMMisslON f
T, W ASHINCTON, D. C. 20565
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO.50-3fg_
ARKANSAS NUCLEAR ONE _ UNIT NO.jL i
_ AMENDMENT TO FACILITY OPERATING LICENSE Anencinent No. 21 l
License No. NPF-6 The Nuclear Regulatory Comission (the Comission) has found that:
1.
The application for amendment by Arkansas Power and Light Com A.
(the licensee) dated October 20, 1980, 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; l
The facility will operate in confomity with the application, I
the provisions of the Act, and the rules and regulations of B.
I the Comission; There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health C.
and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Comission's regulations; The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; D.
and I
The issuance of this amendment is in accordance with 10 CFR P
,t.
51 of the Comission's regulations and all applicable requirements E.
have been satisfied.
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2.
Accordingly, the license is amended by changes to the Techidcal Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. flPF-6 is hereby amended to read as follows:
(2) Techni_ cal _ Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendnent No. 2k 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.
i FOR THE NtlCLEAR REGULATORY COMMISSIO!4
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. Cw Robert A. Clark, Chief Operating Reactors Branch #3.
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 10, 1981 J
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I ATTACHMENT TO LICENSE AMENDffENT NO. 21 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix "A" Technical Specifications l
with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
- Pages XV 6-21
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INDEX i
l ADMINISTRATIVE CONTROLS l
SECTION
.PAGE 6.6 REPORTABLE OCCURRENCE ACTION..............................
6-12 6.7 SAF ETY L IM IT VIOLATION....................................
6-13 6.8 PROCEDURES................................................
6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES..............
6-14 6.9.2 SPECIAL REP 0RTS.........................................
6-18 6.10 RECORD RET ENT IO N.........................................
6-19 I
RADIATION PROTEri10N PR0 GRAM.............................
6-20 6.11 6.-12 ENVIRONMENTAL QUALIFICATION.............................
6-20 6.13 HIGH RADIATION AREA......................................
6-21 l
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t ARKANSAS - UNIT 2 XV Amendment No. 21
ADMINISTRATIVE CONTROLS 6.12.2 By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environ-mental qualification method used for all safety-rclated electrical equipment in sufficient detail to document the degree of compliance with the D0R Guide-l lines or NUREG-0588.
Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further cualified.
6.13 HIGH RADIATION AREA 6.13.1 In lieu of the " control device" or'" alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area (as defined in 20.202(b)(3) of 10 CFR 20) in which the intensity of radiation is 1000 mrem /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 Special Work Permit (SWP)*.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously inty rates the radiation dose rate in the area and alarms when a present integrated dose is received.
Entry into such areas with this monitoring device may be mr.de after the dose rate level in the area has been established ead personnel have been made knowledge-able of them.
An individual qualified in radiation protection procedures who is c.
equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic l
radiation surveillance at the frequency specified in the Special l
Work Permit.
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6.13.2 The requirements of f
.1, above, shall also. apply to each high radiation area in which the intensity of radiation is greater than 1000 l
mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized l
entry into such areas and access to these areas shall be maintained under the administrative control of the Shift Supervisor on duty and/or the health Physics Supervisor.
- Health Physics and Operations personnel shall' be exempt from the SWP require-ments; however,' entry into high radiation areas for performing their assigned duties shall be controlled by the issuance of a Radiation Work Permit provided they comply with approved radiation protection procedures for entry into high radiation areas.
ARKANSAS - UNIT 2 6-21 0/#t #fdd Od%6dt ZH 7989 Amendment No. 21 P00RORGM L