ML20150E512
| ML20150E512 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/05/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150E516 | List: |
| References | |
| NUDOCS 8807150176 | |
| Download: ML20150E512 (6) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
- l WASHING TON, D. C. 20655
'+,..... g NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.123 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 April 29, 1988, complies with the standards and requirements of the Atemic 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 conformity with the application, as arrended, the provisions of the Act, and the rules and regulations of the Comissien; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of t5a ?ublic, 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 comon 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.123, are hereby incorporated in the license.
The licensee s.all 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 COW.ISSION db b
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 5,1988 l
t; 3 ATTACHMENT TO LICENSE AMENDMENT NO.123 FACILITY OPERATING. LICENSE N0. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 107 111 112
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g-LIMfTfNG CONDfTf0NS FOR OPERATION SURVEILLANCE REQUfREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Applicability:.
Applicability:
Applies to the operating status of Applies to the surveillance require-the-Standby Liquid Control System.
ments of the Standby Liquid Control System.
Objective:
Objective:
To assure the availability of a sys.
To verify the operability of the tem with the capability to shutdown Standby Liquid Control Syste=,
the reactor and maintain the shutdown condition without the use of control rods.
Specification Specification:
A.
Normal System Availability A.
Normal System Availability During periods when fuel is in the The operability of the Standby Liquid reactor and prior to startup from a Control System shall be shown by the Cold Condition, the Standby Liquid performance of the following tests:
Control System shall be operable, except as specified in 3.4.B below.
1.
At least once per month each pump This system need not be operable loop shall be tested for operability when the reactor is in the Cold by recirculating demineralized water Condition and all control rods are to the test tank.
fully inserted and Specification 3.3.A is met.
2.
At least once during each operating cycle:
a.
Check that the settings of the systen relief valves are 1450 < P < 1680 psig and the valves will reset at P > 1300
- psig, b.
Manually initiate the system, except explosive valves, and pump boren solution from the Standby Liquid Control Storage Tank through the l
recirculation path. Minimum pump flow rate of 38.2 spm against a system head of 1300 psig shall be l
verified. After pamping boron solution the system will be flushed with demineralized water, c.
Manually initiate one of the Standby Liquid Control System Pumps and i
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Amendment No. f.123
_107 L
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3.4 BASES (cont'd.)
' The volume versus concentration requirement of the solution is such that, should evaporation occur from any point within the curve, a lov level alar =
will annunciate before the te=perature versus concentration requirements are exceeded.
The quan~'ty of stored boron includes an additional margin (25 percent) beyond the amount needed to shutdown the reactor to allow for possible imperfect mixing of the che=ical solution in the reactor water.
A minimum quantity of 2840 gallons of solution having a 16.0 percent sodium pentaborate concentration, or the equivalent as shown in Figure 3.4.1, is required to meet this shutdown requirement.
The NRC's final rule on Anticipated Transients Without Scram (ATWS),
10CFR50.62, requires that the Standby Liquid Control System (SLCS) be modified to provide a minimum flow capacity and boron content equivalant in control capacity to 86 gpm of 13 weight percent sodium pentaborate solution for a 251 inch I.D. vessel.
For Cooper Nuclear Station, with a 218 inch I.D.
vessel, the equivalent minimum flow rate is 66 spm at 13 weight percent sodium pentaborate. This equivalence is met with both SLCS pu=ps supplying their minimum flow race of 38.2 gpm with a solution concentration of at least 11.5 weight percent of sodium pentaborate.
Because ATWS is a very low probability event and is considered to be beyond the design basis for CNS, the surveillance and limiting condition for operation requirements need not be more stringent than the original SLCS design basis requirements. The SLCS changes made as a result of the ATWS rule do not invalidate the original system design basis.
4.4 BASES STANDBY LIOUID CONTROL SYSTEM Experience with pump uperability indicates that the monthly test, in combination with the tests during each operating cycle, is sufficient to maintain pump performance. The only practical time to fully test the liquid control system is during a refueling outage. Various components of the system are individually tested periodically, thus making unnecessary more frequent testing of the entire system.
The bases for the surveillance requirements are given in subsection III.9.6 of the Final Safety Analysis Report, and the details of the various tests are discussed in subsection III.9.5.
The solution temperature and volume are checked at a frequency to assure a high reliability of operation of the system should it ever be required.
Amendment No. 102, 123
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NE8RA5KA PU6LIC PowtR DISTRICT COOPER NUCLEAR STAfl0H Sodium Pentaborate Solution Volume-Concentration Requirements FIGURE 3.4.1 Amendment No.123 112
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