ML20112D232
| ML20112D232 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20112D236 | List: |
| References | |
| NUDOCS 8501140145 | |
| Download: ML20112D232 (5) | |
Text
.
am
. /
8 o,,
UNITED STATES NUCLEAR REGULATORY COMMISSION o
g
.g WASHINGTON, D. C. 20555 s,...../
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY 1
PENNSYLVANIA POWER COMPAfiY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.87 License No. DPR-66 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated June 25, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and j
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.
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. DPR-66 is hereby amended to read as follows:
5 8501140145 841231
~
DRADOCK05000g
- ,f (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendirent No. 87,are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented within 30 days of issuance.
FOR THE NUCL LATORY COMMISSION k
d Vr'gh,Ch Operating Reactors
- 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 31, 1984 G
L..
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 87 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 6-2 3/4 6-2 B 3/4 6-1 8 3/4 6-1 T
--na-rv-
-,e s,-- --
-4 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
{
An overall integrated leakage rate of:
a.
1.
. L, 0.10 percent by weight of the containment air per 24 houfsatP,,(33.3psig),or b.
A combined leakage rate of < 0.60 L for all penetraticns and valves subject to Type B and C tests af identified in Table 3.6-1, when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L,v,alves subor (b) with the measured combined leakage rate for penetrations and restore the leakage rate (s) ject to Types B and C tests exceeding 0.60 L,
to within the limit (s) prior to increasing t$e Reactor Coolant System temperature above 200'F.
SURVEILLANCE Rt0VIREMENTS f
4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50* using the methods and provisions of ANSI M45.4-1972:
A Type-A test (Overall Integrated Containment Leakage Rate) shall a.
be conducted at 40 2 10-month intervals during shutdown at P, (38.3-psig).
l
- Exemption to Appendix J of 10 CFR 50, Section III.D.1(a), granted on December 5,1984.
BEAVER VALLEY - UNIT 1 3/4 6-2 Amendment No, 87 l
l l
L
3/4.6 CONTAINMENT SYSTEMS i
BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accioent analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure,_ P. As an added conservatism, the measured overall integrated leakage rate,is further limited to < 0.75 L during performance of the periodic test to account for possible degradatio$
of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
The exemption to 10 CFR 50 Appendix J.III.D.1(a) allows Type A tests to be conducted on a 40 210-month schedule, not in conjunction with any ISI tests. -
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate-for the containment air locks are required to meet the restrictions on CONTAllmENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
BEAVER VALLEY - UNIT 1 8 3/4 6-1 Amendment No. 87.
--