ML20062C933
| ML20062C933 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/17/1978 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062C929 | List: |
| References | |
| NUDOCS 7811150175 | |
| Download: ML20062C933 (8) | |
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UN4TED STATES NUCt. EAR REGUt.ATORY COMMISSION g
x,*, j WASHINGTON. D. C. 20555 u ry 5
%, *..J 4 CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
. DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. OPR-26
'1.
,The Nuclear Regulatory Commission (the Commision) has found that:
A.
The application for amendment by Consolidated E:lison Company of New York, Inc. (the licensee) dated March 21, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regu-lations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; e*
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;
- b, D.
The issuance of this amendment.will not be inimical to the common defense and security or to the health and safety of the public;
...e and iP E.
The issuance of this ai.endment is in accordance with 10 CFR Part 51 of the Commission's replations and all applicable requirements have been satisfied.
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Accordingly, Facility Operating License No. OPR-26, is hereby I
amended as indicated belcw and by changes to the Technical Specifications as indicated in the Attachment to this license amendment:
t A.
Delete existing paragraphs 2.B.(2) and 2.B.(3), renumber existing paragraph 2.8.(4) as 2.B.(5), and insert new paragraphs 2.B.(2), 2.B.(3) and 2.B.(4) as follows:
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i 2.B.
(2). Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance 5-with the limitations for storage and amounts re-quired for reactor operation, as described in the Final Facility Description and Safety Analysis Report, as supplemented and amended, and as de-scribed in the Commission's authorization for 4.
Amendment No.14 to this license.
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(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, I
to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor
, instrumentation and radiation monitoring equipment cali-i bration, and as fission detectors in amounts as required;
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(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any by-product, source, or special nuclear material without 8
restriction to chemical or physical fom, for sample analysis or instrument calibration or associated with j-j.
radioactive apparatus or components; B.
Revise paragraph 2.C.(2) to read as follows:
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(2) Technical Soecifications i
I l. !.1 The Technical Specifications contained in Appendices
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A and B, as revised through Amendment No. 42, are l
hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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A. Schwencer, Chief Operating Reactors Branch fl Division of Operating Reactors
Attachment:
a Changes to the Technical Specifications Date of Issuance:,0ctober 17, 1978 4
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r ATTACHMENT TO LICENSE AMENDMENT NO.12 l
FACILITY OPERATING LICENSE NO. DPR-26 DOCKET 50-247 Revise Appendix A as follows:
Remove Pages Insert Pages i
11 11 4.15.1 4.15.2 6.19 6.19 r
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TABLE OF CONTENTS (Continued)
Section Title Page 3.10 Control Rod and Power Distribution Limits 3.10-1 Shutdown Reactivity 3.10-1 Power Distribution Limits 3.10-1.
Quadrant Power Tilt Limits 3.10-4 Rod Insertion Limits 3.10-5 Rod Misalignment Limitations 3.10-6 Inoperable Rod Position Indicator Channels 3.10-6 Inoperable Rod Limitations 3.10-7 Rod Drop Time 3.10-7 Rod Position Monitor 3.10-7 Quadrant Power Tilt Monitor 3.10-7 Notification 3.10-8 3.11 Movable In-Core Instrumentation 3.11-1 3.12 Shock Suppressors (Snubbers).
3.12-1 3.13 Fire Protection and Detection Systems 3.13-1 f
4 Surveillance Requ'irements 4.1-1 h
4.1 Operational Safety Review 4.1-1 l
4.2 Primary System Surveillance 4.2-1 4.3 Reactor Coolant System Integrity Testing 4.3-1 4.4 Containment Tests 4.4-1 Integrated Leaksge. Rate Test - Pre-Operational 4.4-1 Integrated Leakage Rate Test - Post-operational 4.4-2 Report of Test Results 4.4-4 Continuous Leak Detection Testing via the Containment Penetration and Weld Channel Pressurization System 4.4-4 Corrective Action 4.4-4 Isolation Valve Tests 4.4-4 Residual Heat Removal Systems 4.4-5 Annual Inspection 4.4-6 Containment Modification 4.4-6 4.5 Engineered Safety Features 4.5-1 Safety Injection System 4.5-1 Containment Spray System 4.5-2 Hydrogen Recombiner System 4.5-2 Component Tests 4.5-3 4.6 Emergency Power System Periodic Tests 4.6-1 Diesel Generators 4.6-1 Diesel Fuel Tanks 4.6-2 Station Batteries 4.6-2 4.7 Main Steam Stop Valves 4.7-1 4.8 Auxiliary Feedwater System 4.8-1 4.9 Reactivity Anomalies 4.9-1 4.10 DELETED 4.11 DELETED 4.12 Shock Suppressors (Snubbers) 4.12-1 4.13 Steam Generator Tube Inservice Surveillance 4.13-1 Inspecti.on Requirements 4.13-1 Corrective Measures 4.13-4 Reports 4.13-4 4.14 Fire Protection and Detection Systems 4.14-1 4.15 Radioactive Materials Surveillance 4.15-1 l
1 Amendment No. J$. 71, JJ, JJ, 35, 42 11 i.
4.15 RADIOACTIVE MATERIALS SURVEILT>NCE Applicabilitv Applies to the surveillance of sealed special nuclear, source and byproduct material sources.
Obiective To assure that leakage from byproduct, source, and special nuclear radioactive material sources does not exceed allowable limits.
Specificatien A.
Tests for leakage and/or contamination shall be performed as follows:
l 1.
Each sealed source, except startup sources and fission detectors, containing radioactive material, other than Hydrogen-3, with a half life greater than thirty days and in any form other than gas shall be cesced for leakage and/or contamination at six month intervals.
2.
The periodic leak test required does not apply to sources that are stored and not being used. These sources shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferer indicating that a test has been made withis six months prior to the transfer, sealed sources shall not be put into use until tested.
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Primary startup sources and fission detectors shall be leak tested prior to being subjected to core flux and following repair or maintenance to the source.
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i Amendment No. 42 4.15-1 r
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Sealed sources are exempt from Speci,fication 4.15.A d en the source contains 100 3.
microcuries or less of beta and/or gamma emitting material or 5 microcuries or less of alpha emitting material.
C.
The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, the sealed source shall immediately be withdrawn from use and either decontaminated and repaired, or be disposed of in accordance with Commission regulations.
D.
A Special Report shall be prepared and submitted to the Commission pursuant to r
Specification 6.9.2.e within 30 days if source leakage tests reveal the presence of y,0.005 microcuries of removable contamination.
Basis The objective of this specification is to assure that leakage from byproduct, source, and special nuclear radioactive material sources does not exceed the allowable limits specified in the Code of Federal Regulations.
l Amendment No. 42 4.15-2 1
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SJECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Region I Olfice of Inspection and Enforcement within the time period specified each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
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I Each containment integrated leak rate test shall be the subject of a a.
summary technical report including results of the local leak rate test since the last report. The report shall include. analyses and interpreta-tions of the results which demonstrate compliance in meeting the leak rate f
limits specified in the Technical Specifications.
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b.
A report covering the X-Y xenon secbility tests within three months upon completion of the tests.
To provide the Commission with added verifications of the safety and c.
reliability of the pre-pressurized Zircaloy-clad nuclear fuel, a limited program of non-destructive fuel inspections will be conducted. The pro-gram shall consist of a visual inspection (e.g., underwater T7, periscope, or other) of the two lead burnup assemblies in each region during the first, second, and third refueling shutdowns. Any condition observed by this inspection which would lead to unacceptable fuel performance may be the object of an expanded surveillance effort. If another domestic plant which contains pre-pressurized fuel of a similar design reaches fuel exposures equal to or greater than at Indian Point. Unit No. 2, and if a limited in-spection program is or has been perfe, med there, then the program may not have to be performed at Indian Point Unit No. 2.
Lvever, such action re-quires approval of the Nuclear Regulatory Commission. The results of these inspections will be reported to the Nuclear Regulatory Commission.
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Inoperable fire protection and detection equipment (Specification 3.13),
i Sealed source leakage in excess of limits (Specification 4.15).
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Amendment No.
J6, 33, 36; J7, 42 s_19 g
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