ML14175A635
| ML14175A635 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/30/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A637 | List: |
| References | |
| DPR-23-A-050 NUDOCS 8010310220 | |
| Download: ML14175A635 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20956 CAROLINA POWER AND LIGHT COMPANY DOCKET NO.
50-261 H. B. ROBINSON, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.50 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated December 18, 1974, as supplemented September 20, 1979 and July 14, 1980, 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 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.
8-0 10a 8o720
-2
- 2.
Accordingly, paragraph 2 of the Facility Operating License DPR-23 is amended as indicated below:
B. 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 with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis'Report as supplemented and amended; C. Pursuant to the Act and 10 CFR Parts 30, 40 and 70 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 moni toring equipment calibration and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or com ponents.
E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
The license is also amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License DPR-23 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
50, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION teven A. Varga, Chle Operating Reactors anch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications nate of Issuance: September 30, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO.
50-261 Replace the following pages of the Appendix A Technical Specification with the enclosed pages.
The revised pages are identified by amendment number and contains a vertical line indicating the area of change.
Remove Insert 11 ii 4.16-1
Section Title e
3.10.5 Deleted 3.10.6 Inoperable Control Rods 3.1C-8 3.10.7 Power Ramp Rate Limits 3.1C-9 3.10.8 Required Shutdown Margins 3.1C-9 3.11 Movable In-Core.Instrumentation 3.11-1 3.12 Seismic Shutdown 3.12-1 3.13 Shock Suppressors (Snubbers)
.1 1 3.14 Fire Protection System 3.1L1 3.14.1 Fire Detection Instrumentation 3.1--1 3.14.2 Fire Suppression Water System 3.1L-1 3.14.3 CO2 Fire Protection System 3.14-2 3.14.4 Fire Hose Stations 3.14-2a 3.14.5 Fire Barrier Penetration Fire Seals 3.14-3 3.15 Control Room Filter System 3.1:-1 4.0 Surveillance Requirements 4.1-1 4.1 Operational Safety Review 4.1-1 4.2 Primary System Surveillance 4.2-1 4.3 Primary System Testing Following Opening 4.3-1 4.4 Containment Tests 4.4-1 4.4.1 Operational Leakage Rate Tests 4.4-1 4.4.2 Isolation Valve Tests 4.4-4 4.4.3 Post Accident Recirculation Heat Removal System 4.4-4 4.4.4 Operational Surveillance Program 4.4-3 4.5 Emergency Core'Cooling, Containent Cooling and Iodine Removal Systems Tests 4.5-1 4.5.1 System Tests 4.5-1 4.5.2 Component Tests 4.5-2 4.6 Emergency Power System Periodic Tests 4.6-1 4.6.1 Diesel Generators 4.6-1 4.6.2 Diesel Fuel Tanks 4.6-2 4.6.3 Station Batteries 4.6-2 4.7 Secondary Steam and Power Conversion System 4.7-1 4.8 Auxiliary Feedwater System 4.8-1 4.9 Reactivity Anomalies 4.9-1 4.10 Radioactive Effluents 4.1 -1 4.11 Reactor Core 4.12 Refueling Filter Systems 4.12-1 4.13 Shock Suppressors (Snubbers) 4.13-1 4.14 Fire Protection System 4.14-1 4.15 Control Room Filter System 4.15-1 4.16 Radioactive Source Leakage Testing 4.16-1 0
Design Features 5.1-1 5.1 Site 2
Containment 5.2-1 5.2.1 Reactor Containment
- .2-1 Penetrations 5.2-1
.3 ContainmentSystems Reactor 5.3-1 Reactor Core
.. 2 Reactor Coolant System3.
Fuel Storage Seismic Design ii Amendment No.
50
16 RAD-OACTIVE SOURCE LEAKAGE VESTING Applicabili ty:
Applips to by-Tprochict, reurce aW rpocial nurlenr rONin live matrAl usd at H. B. Robinson Unit 2.
Objective:
'he objective of this specification is to assure that leokage from by--proluct,
- source, and special. 1111clear radi oar tive material sources does not exceed allowable limits.
Sp>ecif1 iation:
4.16.1 The leakage test shall be capable of detecting the presence of.005 microcurie of radioactive mia terial on the test sample.
If the test reveals the presence of.005 microcurie or more of removable contamination, it shall inmandiately be withdrawn fron use, decontaminated, and repa ired, or be disposed of in accordance with Commission regulations.
Sealed sources are exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting miterial or 1.0 microdites or less of alpha omitting mAterial.
4.16.2 Tests for leakage and/or contamination shall he performed by the licensee or by other persons specifically authorized by the Commission or an agreement State as follows:
A.
Each sealed source, except startup sources subject
- o core flux, containing radioactive material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
B.
The periodic leak test required does not apply to sealed sources that are stored and not being used.
The sources excepted from this test shall be tested for leakage prior to any use or transfer to another user unless they have, been.eak tested within six months prior to the date of use or transfer.
In the absence of a certificate from a transferor indicating that a test has been iule within six months prior to the transfer, senld sources shall not he put into "se until tested.
C.
Startup sources shall be leak tested prior to Nid following any repair or maintinance and beore eig subjected to core flux.
4.16-1 Amendment No.
50