ML14175A719
| ML14175A719 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/18/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A720 | List: |
| References | |
| DPR-23-A-067 NUDOCS 8204220087 | |
| Download: ML14175A719 (6) | |
Text
.91 UNITED STATES 0-NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
67 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 May 9, 1980, as supplemented January 8, 1982, 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.
8204220087 820316 PDR ADOCK 05000261 P
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-23 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 67, 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.
FO THE NUCL A EGULATORY COMMISSION ve a, ief Operating Reacto s ranch No. I Division of Licen i g
Attachment:
Changes to the Technical Specifications Date of Issuance: March 18, 1982
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 1-2 1-2 3.1-1 3.1-1 6.8-1 6.8-1
1.2.6 Refueling Operation Any operation involving movement of core components when there is fuel in the containment vessel and the pressure vessel head is unbolted or removed.
1.2.7 Operating Basis Earthquake The operating basis earthquake is that earthquake which involves a ground acceleration of 0.10 g horizontally and 0.067 g vertically.
1.2.8 Safe Shutdown Earthquake The safe shutdown earthquake is that earthquake which involves a ground acceleration of 0..20 g horizontally and 0.133 g vertically.
1.3 OPERABLE -
OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s).
Implicit in this definition shall be the assumption that all necessary attendant instru mentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).
When a system, subsystem, train, component or device is determined to be inoperable soley because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification.
1.4 PROTECTION INSTRUMENTATION CHANNEL An arrangement of components and modules as required to generate a single protective action signal when required by a plant condition. A channel loses its identity where single action signals are combined.
1.5 DEGREE OF REDUNDANCY The difference between the number of operable channels and the number of channels which when tripped will cause an automatic system trip.
Amendment No. 67 1-2
3.0 LIMITING CONDITIONS FOR OPERATION Except as otherwise provided for in each specification, if a Limiting Condition for Operation cannot be satisfied because of circumstances in excess of those addressed in the specification, the unit shall be placed in hot shutdown within eight hours and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are taken that permit operation under the permissible Limiting Condition for Operation statements for the specified time interval as measured from initial discovery or until the reactor is placed in a condition in which the specification is not applicable.
3.1 REACTOR COOLANT SYSTEM Applicability Applies to the operating status of the Reactor Coolant System.
Objective To specify those Reactor Coolant System conditions which must be met to assure safe reactor operation.
Specification 3.1.1 Operational Components 3.1.1.1 Coolant Pumps
- a.
At least one reactor coolant pump or the Residual Heat Removal System shall be in operation when a reduction is made in the boron concentration of the reactor coolant.
- b.
When the reactor is critical, except for special low power tests during initial start-up testing, at least one reactor coolant pump shall be in operation.
- c.
Reactor power shall not exceed 10% rated power unless at least two reactor coolant pumps are in operation.
- d.
Reactor power will not exceed 45% of rated power with only two pumps in operation.
- e.
A reactor coolant pump may be started (or jogged) only if there is a steam bubble in the pressurizer or the steam generator temperature is no higher than 50'F higher than the temperature of the reactor coolant system.
3.1-1 Amendment No. 67
6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemented, and maintained that meet or exceed the requirements and recommendations of Sections 5.2 and 5.3 of ANSI N18.7-1976 and Appendix "A" of USNRC Regulatory Guide 1.33 Rev. 2 dated February, 1978, except as provided in 6.8.2 and 6.8.3 below.
6.8.2 Proposed operating procedures, overall plant operating procedures, system descriptions, emergency procedures, fuel handling procedures, periodic test procedures, procedures for equipment maintenance which may affect nuclear safety, annunciator procedures, Fire Protection Program implementa tion procedures and any other procedures determined by the Plant Manager to affect nuclear safety, shall be reviewed by the PNSC and approved by the Plant Manager. Prior to implementation, proposed changes to these procedures must also be reviewed and approved in this manner.
6.8.3 Temporary changes to procedures of 6.8.2 above may.be made 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 License.
- c.
The change is documented, reviewed by the PNSC and approved by the Plant Manager within three weeks of implementation.
6.8-1 Amendment No. 67