ML20205D331
| ML20205D331 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/26/1999 |
| From: | Robert Fretz NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205D335 | List: |
| References | |
| TAC-M96367, NUDOCS 9904020168 | |
| Download: ML20205D331 (7) | |
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p UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30066 4001 o
4...../
ENTERGY GULF STATES. INC. "
ENTERGY OPERATIONS. INC.
DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for r.sendment by Entergy Gulf States, Inc.* (the licensee) dated January 12,1999, superceding 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 with the application, as amended, 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 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 license amendment will not be inimical to the common defense and security or to the health and safety of the public; and
- EOl is authorized to act as agent for Entergy Gulf States, Inc, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
"Entergy Gulf States, Inc., has merged with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc. was the surviving company in the merger.
9904020168 990326 PDR ACOCK 05000458 P
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.. 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.
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-47 is hereby amended to read as follows:
(2)
Technical Soecifications and Environmental Protection Plan j
The Technical Specifications contained in Appendix A, as revised through Amendment No.104 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOl shall operate the facility in accordance with tne Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATOilY COMMISSION f
obert J. Fretz, Proj ct. Manager Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor. Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1999
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ATTACHMENT TO LICENSE AMENDMENT NO.104 FACILITY OPERATING LICENSE NO. NPF-47 j
DOCKET NO. 50-458 i
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Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginallines ind;cating the areas of change.
BEMOVE INSERT 3.9-1 3.9-1 3.9-1a B 3.9-3 B 3.9-3 B 3.9-4 B 3.9-4 i
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Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling. Equipment Interlocks LC0 3.9.1-The. refueling equipment interlocks shall be OPERABLE.
APPLICABILITY:
During in-vessel fuel movement with equipment associated with the interlocks.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME j
I 1
A.
One or more required A.1 Suspend in-vessel fuel Immediately
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refueling equipment movement with equipment interlocks inoperable.
associated with the inoperable interlock (s).
93 A.2.1 Insert a control rod Immediately withdrawal block.
6NQ A.2.2 Verify all control rods Immediately are fully inserted in l-core cells containing one or more fuel as:cmblies.
RIVER BEND 3.9-1 Amendment No. Bb 104 e
Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS 3
SURVEILLANCE FREQUENCY SR 3.9.1.1 Perforni CHANNEL FUNCTIONAL TEST on each of the 7 days following required refueling equipment
. interlock inputs:
I a.
All-rods-in, b.
Refuel platform position, and l
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Refuel platform main hoist, fuel loaded.
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RIVER BEND 3.9-la Amendment No. &h 104 L
e Refueling Equipment Interlocks B 3.9.1 i
i BASES (continued) 1 1
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.
l ACTIONS A.I. A.2.1. and A.2.2 I
With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LCO does not apply or~the Surveillances are not needed. This can be performed by ensuring fuel assemblies are not moved in the reactor vessel or by ensuring that the control rods are inserted ar.d 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-vessel fuel movement shall not preclude completion of movement of a component to a safe position.
(
l Alternatively Required Actions A.2.1 and A.2.2 require that a i
control rod withdrawal block be inserted and that all control rods subsequently verified to be fully inserted. Required Action
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A.2.1 ensures that no control rods can be withdrawn. This action j
ensures that control rods cannot be inappropriately withdrawn 1
because an electrical or hydraulic block to control rod I
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)
RIVER BEND B 3.9-3 Amendment No. 104
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Refueling Equipment Interlocks e
B'3.9.1 BASES ACTIONS to allow control rods to be withdrawn in accordance with (continued)
LC0 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 by SR 3.9.3.1 and SR 3 10.6.2.
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 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.
l RIVER BEND B 3.9-4 Amendment No.104 L