ML20206L430
| ML20206L430 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/07/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206L435 | List: |
| References | |
| NUDOCS 9905140020 | |
| Download: ML20206L430 (7) | |
Text
p tet UNITED STATES g
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 A..... )'
ENTERGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. INC.
SQ.UTH MISSISSIPPI ELECTRIC POWER ASSOCIATION ENTERGY MISSISSIPPl. INC.
DOCKET NO,50-416 GRAND GULF NUCLEAR STATION. UNIT 1 i
i AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No.138 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated January 12,1999, superseding its original application dated May 31,1996, 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 wifh the application, the provisions of the Act, and the rules and regulations of the Commission;
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C.
There is reasonable assurance (i) 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 Commission's regulations; j
D, The issuance of this 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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j 9905140020 990507 PDR ADOCK 05000416 P
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2 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) of Facility Operating License No. NPF-29 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
are hereby incorporated into this license. Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 day of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
A Mw Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specificationc l
Date of issuance: May 7, 1999 j
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ATTACHMENT TO LICENSE AMENDMENT NO.138 l
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FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
l Remove 103m1 3.9-1 3.9-1 3.9-1a i
B 3.9-3 B 3.9-3 B 3.9-4 B 3.9-4
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Refueling' Equipment Interlocks 3.9.1 l*
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~3.9 REFUELING OPERATIONS
. 3.9.1 Refueling Equipment Interlocks LCO 3.9.1-
.The refueling equipment interlocks shall be OPERABLE.
APPLICABILITY:
During in-vessel fuel movement with equipment associated with the interlocks.
ACTIONS.
l CONDITION REQUIRED ACTION COMPLETION TIME
- A.
One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable, associated with the i
inoperable interlock (s).
QB A.2.1 Insert a control rod Immediately j
withdrawal block.
AND A.2.2 Verify all control rods Immediately are fully inserted in core cells containing one or more fuel assemblies.
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' GRAND GULF 3.9-1 Amendment No. -1@0,138
.A.
so A.
y Refueling Equipment Interlocks j
3.9.1 l
SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of the 7 days following required refueling equipment interlock inputs:
a.
All-rods-in, j
j b.
Refuel platform position, and c.
Refuel platform main hoist, fuel loaded.
l GRAND GULF 3.9-la Amendment No. -100,138
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Refueling Equipment Interlocks B 3.9.1 BASES (continued) l APPLICABILITY In MODE 5. a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment. The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5.
The interlocks are only required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.
In MODES 1. 2, 3. and 4. the reactor pressure vessel head is on, and no fuel loading activities are possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.
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l ACTIONS A.1. A.2.1. and A.2.2 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LC0 does not apply or the Surveillances are not needed. This can i
be performed by ensuring fuel assemblies are not moved in the reactor vessel or by ensuring that the control rods are inserted and can not be withdrawn.
Therefore. Required Action A.1 requires that in-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn). Suspension of in-vnsel fuel movement shall not preclude completion of movement of a component to a safe position.
Alternatively. Required Actions A.2.1 and A.2.2 require that a control rod withdrawal block be inserted and that all control rods subsequently verified to be fully inserted. Required Action A.2.1 ensures that no control rods can be withdrawn. This action ensures that control rods cannot be inappropriately withdrawn because an electrical or hydraulic block to control rod withdrawal is in place. Required Action A.2.2 is performed after placing the rod withdrawal block in effect and provides a verification that all rods in core cells containing one or more fuel assemblies are fully inserted. The allowance to not verify that control rods associated with defueled cells are inserted is
~(continued)
GRAND GULF B 3.9-3 Amendment No. 138
P Refueling Equipment Interlocks i
B 3.9.1 BASES ACTIONS to allow control rods to be withdrawn in accordance with (continued)
LCO 3.10.6 while complying with these actions. This verification that all required control rods are fully inserted is in addition to the periodic verifications required ty SR 3.9.3.1 and SR 3.10.5.2.
Like Required Action A.1 Required Actions A.2.1 and A.2.2 ensure that unacceptable operations are blocked (e.g.,
loading fuel into a cell with the control rod withdrawn.)
SURVEILLANCE SR 3.9 1.1 REQUIREMENTS-Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
The 7 day Frequency is based on engineering judgment and is considered adequate in view of other indications of refueling interlocks and their associated input status that are available
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to unit operations personnel.
REFERENCES 1.
10 CFR 50. Appendix A. GDC 26.
2.
USAR. Section 7.7.1.5.
3.
USAR. Section 15.4.1.1.
GRAND GULF B 3.9-4 Amendment No. 138
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