ML14183A607
| ML14183A607 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 12/22/1994 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A605 | List: |
| References | |
| DPR-23-A-153 NUDOCS 9501030187 | |
| Download: ML14183A607 (8) | |
Text
- R UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. DPR-23
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee), dated June 29, 1994, 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.
- 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:
9501030187 941222 PDR ADOCK 05000261 P
-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 153, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION illiam H. Bbman, Director Project Directorate II-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 21, 1994
ATTACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3.3-3 3.3-3 3.3-4 3.3-4 3.3-6 3.3-6 3.3-10 3.3-10
p bte at n with less than thr Oops in service is 3.3.1.2 During power operation, the requirements of 3.3.1.1 may be modified to allow any one of the following components to be inoperable. If the system is not restored to meet the requirements of 3.3.1.1 within the time period specified, the reactor shall be placed in the hot shutdown condition utilizing normal operating procedures. If the requirements of 3.3.1.1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.
- a.
One accumulator may be isolated or otherwise inoperable relative to the requirements of 3.3.1.1.b for a period not to exceed four hours.
- b.
If one safety injection pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c.
If one residual heat removal pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.3-3 Amendment No.99, T1fL, T19, 146, 153
d Id e residual heat exchanger becoO inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- e.
If any one flow path including valves of the safety injection or residual heat removal system is found to be inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The hot leg injection paths of the Safety Injection System, including valves, are not subject to the requirements of this specification.
- f.
Power or air supply may be restored to any valve referenced in 3.3.1.1.g. and 3.3.1.1.h. for the purpose of valve testing or maintenance providing no more than one valve has power restored and provided that testing and maintenance is completed and power removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except for accumulator isolation valves (MOV 865 A.B.&C) which will have this time period limited to four hours.
3.3-4 Amendment No. IN, 11, 1J4. 153
3.3.2.2 During r operation, the requirements 3.3.2.1 may be modifie o allow any one of the followin omponents to be inoperable. If the system is not restored to meet the requirements of 3.3.2.1 within the time period specified, the reactor shall be placed in the hot shutdown condition utilizing normal operating procedures. If the requirements of 3.3.2.1 are not satisfied within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.
- a.
If one fan cooler unit or the flow path for a fan cooler unit becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided both containment spray pumps are operable.
- b.
If one containment spray pump becomes inoperable during normal reactor operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided the four fan cooler units are operable.
- c.
If either containment spray system flow path including valves becomes inoperative during normal operation, the reactor may remain in operation for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.3.2.3 When the reactor is in the hot shutdown condition, the requirements of 3.3.2.1 and 3.3.2.2 shall be met. Except that any one component as defined in 3.3.2.2 may be inoperable for a period equal tO the time period specified in the subparagraphs of 3.3.2.2 plus 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, after which the plant shall be placed in the cold shutdown condition utilizing normal operating procedures.
3.3-6 Amendment No. 153
3 3.7 Extendedlintenance When it is determined that maintenance to restore components or systems to an operable condition will last longer than periods specified. the circumstances of the extended maintenance and the estimated date for returning the components or systems to an operable condition shall be promptly reported to the Director Office of Nuclear Reactor Regulation and to the Director Region II Office of Inspection and Enforcement. The purpose of prompt reporting is to allow the NRC to review the circumstances of the request for extended outage and to render a timely decision on whether to extend the specified out-of-service period while reactor operations continue.
Basis During low temperature physics tests, there is a negligible amount of stored energy in the reactor coolant, therefore an accident comparable in severity to a Design Basis Accident is not possible, and the engineering safety features systems are not required.
The operable status of the various systems and components is to be demonstrated by periodic tests, defined by Specification 4.5. A large fraction of these tests will be performed while the reactor is operating in the power range. If a component is found to be inoperable, it will be possible in most cases to effect repairs and restore the system to full operability within a relatively short time. For a single component to be inoperable does not negate the ability of the system to perform its function.
but it reduces the redundancy provided in the system design and thereby limits the ability to tolerate additional equipment failures. For this reason, the unit is allowed to operate only for a limited time as specified when this condition occurs.
3.3-10 Amendment No.153
CORRECTED COPY AMENDMENT NO. 153 TO FACILITY OPERATING LICENSE NO. DPR H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DISTRIBUTION:
Docket File PUBLIC PD II-1 Reading File S. Varga J. Zwolinski OGC G. Hill, IRM (2)
C. Grimes, DOPS/OTSB ACRS (4)
OPA OC/LFDCB Region IV, WCFO (4)
B. Boger, RII cc:
Robinson Service List