ML20081J477
| ML20081J477 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/31/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081J483 | List: |
| References | |
| NUDOCS 8311080581 | |
| Download: ML20081J477 (4) | |
Text
_
f UNITED STATES NUCLEAR REGULATORY COMMISSION
. p f,..,,
l WASHINGTON C. C. 20555 l
PUBLIC SERVICE ELECTRIC AND GAS COMPANY _
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NdCLEAR GENERATING' STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 54 License No. OPR 70 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated July 22, 1983, complies with the standards and requirements of the Atomic Energy A_ct 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 Comission; 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 complian:e 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 Comission's regulations and all applicable requirements have been satisfied.
8311090581 831031 PDR ADOCK 05000272 P
PDR o
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license.
amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-70 is hereby amended to read as follows:
(2) Technical Specificati ns t
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The ifcensee 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 C0MMISSION'
\\
6 rga,' Chief, te Operating Reactors B'ra i
- 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 31, 1983 9
4
..~
~._
l ATTACHMENT TO LICENSE AMENDMENT NO. 54 l
FACILITYCPERATINGLfCENSENO.Dr%70 00CKET NO. 50-272 ReviseAppendixAasfo,J1ows:
{
Remove Pages Insert Pages 3/4 6-2 3/4 6-2 e
- e we e e
+*
__m__
__________.__m-_
CONTAINMENT SYSTEMS CONTA MMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage ratqs shall be limited to:
a.
Ar. overall integrated leakage rate of < L, 0.10 percent by weight of the containment air per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> $ at design pressure.
(47.0 psig).
valves subject to Type B anF C test $'for all cenetrations and A combined leakage rate of < 0.60 L b.
as identified it Table 3.6-1, when pressurized to P
- a APPLICABILITY: MODES,1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, r (5) with the measured combined leakage rate fcr a
all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the leakage rate (s) to within the limit (s) prior to e
increaking the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REOUTREMFNTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-lg72:
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at design pressure (4770 psig) cu. ing each 10-year service period.* The third test of each set shall be conducted l
during the shutdown for the 10-year plant inservice inspection.
- Ihe second inservice Integrated Leak Bate Test shall be
- perfor:ned at the fif th refueling outage, 6ut no later than May, 1984.
SALEM - UN*T 1 3/4 6-2 Amendment No. 54