ML20078F057
| ML20078F057 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/27/1995 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078F059 | List: |
| References | |
| NUDOCS 9502010292 | |
| Download: ML20078F057 (4) | |
Text
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UNITED STATES s
, *I NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. aDBE5 NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 LQQPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.167 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated July 26, 1994, as supplemented by letters dated December 27, 1994, and January 27, 1995, compiles 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 nperate in conformity 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 license amendment will not be inimical to the common defense and security or to the health and safety of the public; and i
l 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.
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9502010292 950127 PDR ADOCK 05000298 P
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. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
2.
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.167, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W)4 h hb -
William D. Beckner, Director Project Directorate IV-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 27, 1995 i
I I
l ATTACHMENT TO LICENSE AMENDMENT NO.167 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
REMOVE PAGE INSERT PAGE 215a 215a i
e LTMITING CONDITIONS FOR' OPERATION BURVEILIANCE REOUTREMENTS
.3.12.A (cont'd) 4.12.A (cont'd)
A.
Control Room Emergency Filter System A.
Control Room Emergency Filter Systan i
Except as specified in Specification 1.a. At least once per OPERATING CYCLE, l
[
l
- 1. -
3.12.A.2 below, the Control Room the pressure drop across the com-Emergency Filter system, the diesel bined HEPA filters and charcoal generators required for operation of absorber banks shall be demonstrated this system and the main control to be less than 6 inches of water at i
room air radiation monitor shall be a flowrate of 900 CPM 1101.
l f
OPERABLE at all times when PRIMARY or SECONDARY CONTAINMENT INTEGRITY b.
The tests and sample analysis of is required.
Specifications 4.12.A.1.c and 4.12.A.1.d shall be performed at least once every 18 months for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of a stem operation and fol-loving si ificant painting, fire or chemical release in any ventilation sone communicating with the system.
c.
The results of the in-place cold DOP l 1eak tests on the HEPA filters shall show 2 99% DOP removal. The results of the halogenated hydrocarbon leak tests on the charcoal adsorbers shall show 2 99% halogenated hydro-l carbon removal. The DOP and haloge-i nated hydrocarbon tests shall be l
2.
From and after the date that the performed at a flowrate of 900 cm j
l Control Room Emer ency Filter system 110%.
is made or foun to be inoperable i
for any reason, reactor operations
- d. The results of laboratory carbon (
are permissible only during the sample analysis shall show 2 99%
succeeding seven days unless the radioactive methyl iodide removal j
system is sooner made OPERABLE.
with inlet conditions of: velocity Refueling requirements are as speci-2 39 FPM, 2 1.75 mg/m inlet iodide l 8
fied in Specification 3.10.G.
concentration, 2
95%
R.H.
and 3.
If these conditions cannot be met, reactor SHUTD0k'N shall be initiated
- e. Cold DOP testing shall be performed l and the reactor shall be in COLD after each complete or partial re-SHUTD0k'N within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
placement of the HEPA filter bank or after any structural maintenance on f
the system housing,
- f. Halogenated hydrocarbon ta: ting l shall be performed after each com-plete or partial replacement of the charcoal absorber bank or after any structural maintenance on the system l
- housing, i
- g. The system shall be operated at l least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
- h. At least once per OPERATING CYCLE l I
automatic initiation of the system shall be demonstrated, t
- 1. At least once per OPERATING CYCLE demonstrate the Control Room Emer-gency Filter System can maintain i
positive pressure relative to adj acent areas at a flowrate of
$ 990 cm.
l Amendment No. 97,M2,167
-215a.
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