ML14175A723
| ML14175A723 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/24/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A724 | List: |
| References | |
| DPR-23-A-068 NUDOCS 8205030002 | |
| Download: ML14175A723 (4) | |
Text
REGU0 UNITED STATES co 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. 68 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 September 16, 1975, as modified by letter dated January 29, 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.
820 5030OO r-
- e 0
-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 Appendices A and B, as revised through Amendment No. 68, 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 ev.
ef Operating Reactors B anch #1 Division of Licens
Attachment:
Changes to the Technical Specifications Date of Issuance: March 24, 1982
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO.
50-261 Revise Appendix A as follows:
Remove Page Insert Page 4.4-3 4.4-3
(3)
The allowable operational leakage rate, Lto( 2 1),
which shall be met before placing the containment into service and prior to resumption of power operation following a test (either as measured or following repairs and retest) shall be less than 0.7 5Lt (42 or 21).
- g.
Frequency After the initial preoperational leakage rate test, two integrated leak rate tests shall be performed at approximately equal intervals between the major shutdowns for inservice inspection conducted at ten-year intervals.
In addition, an integrated leakage rate test shall be performed at the end of the ten-year interval, which may coincide with the inservice inspection shutdown period.
4.4.1.2 Sensitive or Local Leak Rate Test (SLRT)
- a.
A sensitive leak rate test at 42 psig (testing of penetrations, certain containment isolation valves, and double gasket seals) except for the personnel air lock, will be performed at each refueling. The personnel air lock shall be tested every six months.
- b.
Repairs and retest shall be performed whenever the combined leakage rate of the sensitive leak rate test exceeds 30 percent of L.
For lesser leaks repairs are optional.
4.4-3 Amendment No.
68