ML14183A214

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Amend 139 to License DPR-23,adding Footnote to TS 3.14.3.2.a & 3.14.4.2.a,suspending Requirements of Fire Protection TS for Duration of Containment Integrated Leak Rate & Structural Integrity Tests
ML14183A214
Person / Time
Site: Robinson 
Issue date: 03/31/1992
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML14183A215 List:
References
DPR-23-A-139 NUDOCS 9204070197
Download: ML14183A214 (4)


Text

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g UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

139 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 March 5, 1992, as supplemented March 6, 1992, 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:

9204070197 920331 PDR ADOCK 05000261.

P PDR

-2 B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 139, 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.

FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, 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: March 31, 1992

ATTACHMENT TO LICENSE AMENDMENT NO.

139 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 3.14-3 3.14-3

a. For the Containment Vessel Electrical Penetration Area initiate an inspection once per shift with particular emphasis on identifying any potential hazards for fire.*
b. For all other areas, within one (1) hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
c. Restore the system to operable status within 14 days or prepare and submit a Special Report to the Commission within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

3.14.4 Fire Hose Stations 3.14.4.1 Each fire hose station in Table 3.14.2 shall be operable.

3.14.4.2 With a hose station in Table 3.14.2 inoperable:

a. Route an additional equivalent capacity hose to the unprotected area from an operable hose station within one hour if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24'hours.*
b. Restore the hose station to operable status within 14 days or prepare and submit a Special Report to the Commission within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.

3.14.5 CO, Fire Protection System 3.14.5.1 The CO2 Fire Protection Systems for 1) the Diesel Generator Rooms and, 2) North and South Cable Vaults shall be operable, each:

a. With a complete bank (19 cylinders for the Diesel Generator Room and 18 cylinders in the North and South Cable Vaults) of fully charged CO2 cylinders in service,
b. With the system aligned to deliver to the protected areas, and
c. With automatic initiation logic operable. For the Diesel Generators, this includes two dedicated heat detectors per room for CO2 actuation.
d. A CO2 cylinder,shall be deemed fully charged if it contains not less than 90% of the full charge weight.

3.14.5.2 With any of the CO2 Fire Protection Systems in a condition of readiness less than required by the above:

For the duration of containment vessel ILRT and SIT pressurization, temperature stabilization, data collection, and depressurization, the requirements of Technical Specifications 3.14.3.2.a and 3.14.4.2.a may be suspended.

3.14-3 Amendment No. 9139