ML20127C473
| ML20127C473 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/13/1993 |
| From: | Gates W OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20127C467 | List: |
| References | |
| NUDOCS 9301140225 | |
| Download: ML20127C473 (3) | |
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION in the Matter of Omaha Public Power District i
Docket No. 50-285 (Fort Calhoun Station 1
Unit No. 1)
)
APPLICATION FOR AMENDMENT OF OPERATING LICENSE Pursuant to Section 50,90 of the regulations of the U. S. Nuclear.
Regulatory Commission ("the Commission"), Omaha Public Power District, holder of facility Operating License No. DPR 40, herewith requests that the Technical Specifications set forth in Appendix A to that License be amended to revise the requirements for containment integrity and the Personnel Air Lock to reflect provisions of Combustion Engineering Standard Technical Specifications.
l The proposed changes in Technical Specifications are discussed in Attachment A of the Application for Amendment dated February 13, 1992, as l
supplemented January 8, 1993. A supplement to the discussion and l
justification for the proposed changes transmitted by the Application for Amendment dated February 13, 1992, as supplemented January 8,- 1993, is i
attached. A No Significant Hazards Consideration Analysis, which demonstrates that the proposed changes do not involve a significant hazards consideration,-
is appended in Attachment B to the Application for Amendment dated February 13,1992.(LIC-92-021A). The proposed changes in specifications would not authorize any change in the types or any increase in the amounts of effluents or a change in the authorized power level of the facility.
WHEREFORE, Applicant respectfully requests that the Definitions Section and Sections 2 and 3 of Appendix A to Facility.0perating License No. OPR-40 be amended in the form attached as Attachment A to the Application for Amendment dated February 13, 1992, as supplemented Janauary 8, 1993.
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2-A copy of this Application, including its attachments, has been submitted to the Director - Nebraska State Division of Radiological Health, as required by 10 CFR 50.91.
OMAHA PUBLIC POWER DISTRICT By Vicepsident Subscribed and sworn to before me this.!.JDA day of Jexwen,1993, f.k (buk
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Notary Public GEAAL FRAROState of R&ta:La J T GLEASON -
d My Coma hp JWy M 1994
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Technical Specification (NUREG-212 Rev 2)ld still, require the purposeful 3.6.1.1 is not sufficient in itself to resolve this concern, as it wou violation of one specification (containment integrity) to perform the required actions of another specification This note is consistent with that provided(PAL door inolerability).
in draft NUREG 1432 Specification 3.6.2.
The allowed air leakage rate references Specification 3.5L4) for acceptance criteria as opposed to restating the actual values in the Standard TS.
Current Specification 3.5(3)d. implements the requirements to conduct leakage testing of Standard TS surveillance requirement 4.6.1.3, therefore no changes are proposed to the surveillance requirements.
BASIS OF SPECIFICATION 2.6 The basis of Specification 2.6 is bcing revised to include statements concerning administrative 1y opening locked or seal closed valves consistent with Generic letter 91-08.
SPECIFICATION 3.5 " CONTAINMENT TEST" Specification 3.5 C Tests)" is being(4) " Containment Isolation Valves Leak Rate Tests (Type revised to include valves IA-3092, IA-3093, and IA-3094 to the Type C testing program. As discussed in LER-91 031 dated January 15, 1992, these valves are permanently installed valves in the Personnel Air Lock to allow icak testing of ttue PAL with both of the PAL doors closed.
ADNINISTRATIVE CHANGES Specifications 3.5(fication 2.6(1)d).
- 1) through 3.5(7 have been renumbered to reflect the relocation of Speci 1
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