ML20006A428
| ML20006A428 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/17/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006A429 | List: |
| References | |
| NUDOCS 9001260252 | |
| Download: ML20006A428 (4) | |
Text
)
n u
,r[ge org"*,,
i UNITED STATES u
? y 3e, NUCLEAR REGULATORY COMMISSION E
[
WA$HINGTON, D. C. 20556 l
f'
%, v,/
1 PljBLIC. SERVICE ELECTRIC.& GAS COMPANY i
l PHILADELPHIA FIECTRIC COMPANY DELPARVA.POWEk AND. LIGHT. COMPANY i
ATLANTIC CITY ELECTRIC COMPANY t
DOCKET NO. 50 311 SALEM GEEFRATING. STATION,. UNIT NO. 2 AMENDMENT TO FACILITY.0PERATING. LICENSE Amendment No, 95 License No. DPR-75 1.
Tre Muclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amenoment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company,(Delmarva Power and Light Company and Atlantic City Electric Company the licensees) dated l
September 25, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comissinn's rules and regulations set forth in 10 CFR Chapter I; j
B.
The f acility will operate in conformity with the applicatior-, the i
provisions of the Act, and the rules and regulations of the Comitsion; 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 compliarte with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amenoment will'rct be inimical to the corron defense and security or to the health and safety of the public; and E.
The issuance of this amerdment is in accordance with 10 CFR Part 51 of the Comission's reculations and all applicable requirements have been satisfied.
2.
Accordingly, the license'is amended by changes to the Technical Specifica-tions as indicated in the attachment te this license amendment, and paragraph 2.C.(?) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
9001260252 900117 PDR ADOCK 05000311 P
.m
,y
p.,
4 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. SS
, 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 its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY C0"."ISSION
'fil v
L-Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 17, 1990 l
l l
l'
m
- s-l ATTACHMENT TO LICENSE AMENDMENT NO. 85 i
FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Page Insert Page
{
i L
3/4 6-2 3/4 6-2 k.
1 I
i I
1 e
+
l l-r l
l l.'
CONTAINMENT SYSTEMS CONTAINMENT LEAKACE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
[
An overall integrated leakage rate of less than or equal to La, l
a.
0.10 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at i
design pressure (47.0 psig).
b.
A combined leakage rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C tests as identified in Table 3.6 1, when pressurized to Pa.
1 APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
i Vith either (a) the measured overall integrated containment leakage rate exceeding 0.75 La, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than or equal to 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La prior to increasing the Reactor Coolan System temperature above 200'F.
SURVEILLANCE REQUIREMENTS 1
P 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 1972:
Three Type A tests (Overall Integrated Contairaent Leakage Rate) a.
shall be conducted at 401 10 uonth intervals
- during shutdown at l
design pressure (47.0 psig) during each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection.
The test interval for conducting a Type A test shall be extended from 40110 months to allow the third Type A test, within the first 10 year service period, to be completed during the 10 year plant in service inspection outage (6th refueling outage).
This extension expires upon completion of the 6th refueling outage.
SALEM UNIT 2 3/4 6 2 Amendment No. 05
~