ML20235T830
| ML20235T830 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 09/30/1987 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235T831 | List: |
| References | |
| NUDOCS 8710130239 | |
| Download: ML20235T830 (5) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION n
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'j WASHINGTON, D. C. 20555
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MISSISSIPPI POWER & LIGHT COMPANY SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 56 License No. NPF-29 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
1 A.
The application for amendment by Mississippi Power & Light Company, j
System Energy Resources, Inc. (formerly Middle South Energy, Inc.)
and South Mississippi Electric Power Association, (the licensees) dated July 6,1987, as supplemented September 14, 1987, complies with the standards and req)uirements 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; l
l B.
The facility will operate 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 j
in compliance with the Comission's regulations; 1
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and 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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8710130239 870930 PDR ADOCK 05000416 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2)
I of Facility Operating License No. NPF-29 is hereby amended to read as follows:
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Technical Specifications l
l The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 36, are hereby incorporated into this license.
System Energy Resources, Inc. shall operate the facility in.accordance with the Technical Specifications and the Environmental Protection l
Plan.
3.
This license amendment is effective as of its date of issuance.
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FORTHENUCLEA[f.REGULATO 1 n 4
Herber
. Berkow, Director
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Projec Directorate 11-2 Division of Reactor Projects-I/II' Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: September 30, 1987 l
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 36 FACILITY OPERATING LICENSE NO. NPF-29 1
DOCKET NO. 50-416 i
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l Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and j
contain vertical lines indicating the area of change. The corresponding.
i overleaf page(s) have been provided to maintain document completeness.
j Remove Insert i
3/4 1-19 3/4 1-19 i
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I REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) b.
At least once per 31 days by; 1.
Starting both pumps and recirculating demineralized water to the
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test tank.
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2.
Verifying the continuity of the explosive charge.
3.
Determining that the available weight of sodium pentaborate is j
greater than or equal to.5500 lbs and the concentration of boron in solution is within the limits of Figure 3.1.5-1 by chemical analysis.*
4.
Verifying that each valve, manual, power operated or automatic, in the flow path that is not locked, sealed, or otherwise 1
secured in position, is in its correct position.
c.
Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm at a pressure of greater than or equal to 1220 psig is met, without actuation of the pump relief valve.
d.
At least once per 18 months during shutdown by; 1.
Initiating one of the standby liquid control system subsystems, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from i
another batch which has been certified by having one of that batch successfully fired.
Both system subsystems shall be tested in 36 months.
l 2.
Demonstrating that the pump relief valve opens within 3% of l
the nominal valve setpoint of 1400 psig and verifying that the relief valve does not actuate during recirculation to the test tank.
3.
- Demonstrating that all heat traced piping between the storage tank and the reactor vessel is unblocked by pumping from the storage tank to the test tank and then draining and flushing the piping with demineralized water.
4.
Demonstrating that the storage tank heater is OPERABLE by verifying the expected temperature rise for the sodium pontaborate solution in the storage tank after the heater is energized.
- This test shall also be performed anytime water or boron is added to the solution or when the solution temperature drops below the limit of Figure 3.1.5-1.
- This test shall also be performed whenever both heat tracing circuits have been found to be inoperable and may be performed by any series of sequential, overlapping or total flow path steps such that the entire flow path is included.
1 GRAND GULF-UNIT 1 3/4 1-19 Amendment No.36 l
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