ML19316B016
| ML19316B016 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/16/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19316B017 | List: |
| References | |
| NUDOCS 8005280167 | |
| Download: ML19316B016 (5) | |
Text
.
s km at c,,
- g
'o, UNITED STATES 8
f NUCLE AR REGULATORY COMMISSION
$.M, ';, ',J/ [ 7.
- ?wb.4[j,5 W ASWNGT ON, D. C. 20Ws a
.g, s.
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. OPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Thc application for amendment by Carolina Power & Light Company (the licensee) dated May 9,1980, 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 confonnity 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 :,ecurity 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-71 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 27, are hereby incorporated l
in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
l TDc) S~2 gOM 7
l i
3 3.
This license amendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION 3
4-l l
homas Ippolito, Chief Operating Reactors Branch #2 Division of Licensing l
I
Attachment:
Changes to the Technical Specifications Date of Issuance: May 16,1980 l
}
l 1
3 e
k 1
ATTACHMEtiT TO LICEflSE Af1EllDf1EilT fl0. 27 FACILITY OPERATIf4G LICEfiSE fl0. DPR-71 DOCKET fl0. 50-325 Replace the following pages of the Technical Specifications contained in Appendix A of the above-indicated license with the attached pages. The changed area of the revised page is reflected by a marginal line.
Remove Insert 3/4 7-31 3/4 7-31 3/4 7-32 3/4 7-32 89^520..-/N
i i
TABLE 4.7.5-1 liYDRAULIC SNUBBER INSPECTION SCHEDULE
~
os E5 NEXT REQUIRED NUMBER OF SNUBBERS FOUND IN0PERABLE INSPECTION INTERVAL **
fk DURING INSPECTION OR DURING INSPECTION INTERVAL
- x C
18 months + 25%
25 0
12 months T 25%
1 6 months T 25%
2 124 days T 25%#
l 3 or 4 62 days T25%
5, 6, or 7 31 days
_ 25%
+
>8 This categorization
- Snubbers may be categorized into two groups, " accessible" and " ina These two groups nay be inspected independently according to the above schedule.
- The required inspection interval shall not be lengthened more than one step at a time and th
})
provisions of Specification 4.0.2 are not applicable.
16, 1980, a one-time only
- for the inaccessible snubber inspection interval scheduled to end May 26, 1980.
exemption is allowed to extend this inspection interval through May
$a R
PLANT SYSTEMS 3/4.7.6 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.6 Each sealed source containing radioactive material in excess of 100 taicrocuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcuries of removable contamination.
APPLICABILITY: At all times.
ACTION:
Each sealed source with removable contamination in excess of the above limit shall be innediately withdrawn from use and:
)
Either decontaminated and repaired, or a.
b.
Disposed of in accordance with Commission Regulations.
The Provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
I SURVEILLANCE REOUIREMENTS l
4.7.6.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:
a.
The licensee, or l
b.
Other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
4.7. 6.2 Test Frecuencies_- Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.
Sources in use - At least once per six months for all sealed a.
sources containing radioactive material:
i I
BRUNSWICK - UNIT 1 3/4 7-32 l
~
t w -,