ML20070G767
| ML20070G767 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/07/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070G773 | List: |
| References | |
| NUDOCS 9103120395 | |
| Download: ML20070G767 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION o
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.137 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated May 31, 1989, complies with the standards and requirements of the Atomic Energy Act 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the 6ctivities 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 Commission's regulations; D.
The issuance of this licent.e 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 Commission's regulations and all applicable requirements have been satisfied.
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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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.137, 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
,(
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!)Tk+.y Theodore R. Quay, Director ProjectDirectorateIV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 7, 1991
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ATTACHMENT TO LICENSE AMENDMENT NO.137 FACILITY OPERATING LICENSE NO. OPR-46 00CKET 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 a vertical line indicating U.: area of change.
REMOVE PAGE INSERT PAGE 115 115 l
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17MITSNC CONDITIONS FOR OPERATIONS SL'RVEILLANCE REOUIREMENTS
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3.5.A (cont'd).
4.6.A (cont'd.)
2.
From and after the date that one of
- 2. When it is determined that one core i
the core spray subsystems is made or spray subsystem is inoperable, the found to be inoperable for any reason, operable core spray subsystem and continued reactor operation is per.
the LPCI subsystem shall be demon-missible during the succeeding soven strated to be operable immediately.
days provided that during such seven The operable core spray subsystem 1
' days all active components of the shall be demonstrated to be oper-other core spray subsystem and active able daily thereafter.
components of the LPCI subsystem and the diesel generators are operable.
3.
Both LPCI subsystems shall be opera.
- 3. LPCI subsystem testing shall be as ble:
follows:
(1) prior to reactor startup from a J113 Frecuenev Cold Condition, except as specified in 3.22.B.1, or
- a. Simulated Auto.
Once/ Operating matic Acutation Cycle (2) when there is irradiated Test fuel in the vessel and when the reactor vessel pressure
- b. Pump Operability Once/ month is greater than atmospheric pressure, except as specified
- c. Motor Operated Once/ month in 3.5.A.4 and 3.5 A.5 below.
Valve Operabil,ity d.
Pump Flow Rate Once/3 months c
During single pump LPCI, each RHR pump shall deliver at least 7700 GPM but no more than 8400 CPM against a system head equivalent to a-reactor vessel pressure of 20 psid above dry-vell pressure with water level below the jet pumps. At the same condi-tions, two LPCI flow shall be at least 15,000 GPM.
4
- e. Recirculation pump discharge valves shall be tested each refueling outage.to verify full open to full closed in t s 26 seconds.
l 4.
From and after the date that one of 4 When it is determined that one of the the RHR (LPCI) pumps is made or found RHR-(LPCI) pumps is inoperable at a to be inoperable fer-any reason, con.
time when it is required to be oper-tinued reactor r,peration is permissi.
ating the remaining active components ble only during the succeeding thirty of the LPCI subsystems, the contain-days provided that-during such thirty ment cooling subsystem and both core days the remaining active components spray systems shall be demonstrated of the LPCI subsystem and all active to be operable immediately and the components of both core spray sub-operable LPCI pumps daily thereafter.
systems and the diesel generators are operable.
' Amendment No. 57,76,P0,95,97,137 115
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