ML20141A891
| ML20141A891 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/09/1997 |
| From: | Beckner W NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141A894 | List: |
| References | |
| NUDOCS 9705150042 | |
| Download: ML20141A891 (5) | |
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i UNITED STATES p
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2008H001
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 176 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 5, 1997, 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 activities authorized by this amendment can be cor. ducted 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 license 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.
9705150042 970509 PDR ADOCK 05000298 P
2.
Accordingly, the license is amended to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in Licensee's application dated May 5, 1997, and reviewed in the Staff's safety evaluation report dated May 9,1997. This license is also hereby 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-46 is hereby amended to read as follows:
d 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 176, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
The license amendment is effective as of its date of issuance.
3.
FOR THE NUCLEAR REGULATORY COMMISSION Y
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William D. Beckner, Project Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 9, 1997 I
ATTACHMENT TO LICENSE AMENDMENT NO. 176 FACILITY 0PERATING LICENSE NO. OPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating that area of change.
REMOVE PAGES INSERT PAGES 107.
107 110 110 4
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LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM Aonlicability:
Applicability:
Applies to the operating status of Applies to the surveillance require-the Standby Liquid Control (SLC) ments of the Standby Liquid control System.
(SLC) System.
Obiective:
Obiective:
To verify the OPERABILITY of the SLC To assure the OPERABILITY of a sys-System.
tem with the capability to SHUTDOWN the reactor and maintain the SHUT-DOWN condition without the use of control rods.
Soecification:
Soecification:
A.
Normal System Operation A.
Normal System Operation 1.
During periods when fuel is in the The OPERABILITY of the SLC System reactor and prior to startup from a shall be shown by the performance of Cold Condition, the Standby Liquid the following tests:
Control System shall be operable, except as specified in 3.4.B below.
1.
At least once each 3 months each This system need not be operable subsystem shall be tested for OPERA-when the reactor is in the Cold BILITY by recirculating demineral-Condition and all control rods are ized water to the test tank and fully inserted and Specification verifying each pump develops a flow 3.3.A is met.
rate 2 38.2 gpm at a discharge pres-sure 2 1300 psig.
2.
At least once during each OPERATING CYCLE:
a.
Manually initiate the system, except explosive valves, and pump boron solution from the SLC Storage Tank through the recirculation path.
Verify each pump develops a flow rate 2 38.2 gpm at a discharge pressure 21300 psig. After pumping boron solution the system will be flushed with demineralized water.
Amendment No. ':,12 3,152,144,176
-107-
3.4 BASES STANDBY LIOUID CONTROL SYSTEM A.
The Standby Liquid Control (SLC) System consists of two, distinct subsystems, each containing one positive displacement pump and independent suction from the SLC storage tank, and discharge to a common injection header through parallel explosive valves. The purpose of the SLC System is to provide the capability of bringing the reactor from RATED POWER to a cold, xenon-free SHUTDOWN CONDITION assuming that none of the withdrawn control rods can be inserted.
To meet this objective, the system is designed to inject a quantity of boron that produces a concentration of 660 ppm of boron in the reactor pressure vessel in less than 125 minutes.
The 660 ppm concentration in the reactor pressure vessel is required to bring the reactor from RATED POWER to a 3.0 percent Ak suberitical condition, considering the hot to cold reactivity difference, xenon poisoning, etc. The time requirement for inserting the boron solution was selected to override the rate of reactivity insertion caused by cooldown of the reactor following the xanon poison peak.
The conditions under which the SLC System must provido shutdown capability are identified in Limiting Conditions for Operation. If no more than one OPERABLE control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and the SLC System is not required.
Thus, the basic reactivity requirement for the core is the primary determinant of when the SLC System is required.
B.
Only one of the two SLC subsystems is needed for operating the system.
One inoperable subsystem does not immediately threaten shutdown capability, and reactor operation can continue while the inoperable subsystet is being repaired.
The seven day completion time is based on the availatility of an OPERABLE subsystem capable of performing the intended SLC system function and the low probability of a Design Basis Accident (DBA) or severe transient occurring concurrent with the failure of the Control Rod Drive (CRD) system to shut down the plant.
l Amendment No. 22, M S,152 4M,176
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