ML20070B492
| ML20070B492 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/24/1991 |
| From: | Gwynn T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070B494 | List: |
| References | |
| NUDOCS 9101310195 | |
| Download: ML20070B492 (5) | |
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ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated July 10, 1990, 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 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 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.
9101310195 910124 DR ADOCK 050 3
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.
DPR-51 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 142, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION v/
_,, 'M-- s-Thomas P. Gwynn, cting Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 24, 1991
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e ATTACHMENT TO LICENSE AMENDMENT NO.14?_
FACILITY OPERATING LICEh5E NO. OPR-51 DOCKET NO. 50-313 Revise the f ollowing page of the Appendix "A* Technical Specifications with the ottacheo page. The revised page is iaentified by Amendment number and conto 1ns vertical lines indicating the area of change. The corresponaing overleaf page is also provided to maintain document completeness.
REMOVE PAGE INSERT PAGE 104 104
e 4.7.2 Control Rod Program Verification (Group Vs. Core Positions)
Applicability Applies to surveillance of the control rod systems.
Objective To verify that the designated control rod (by core position) is operating in its programmed functional position and group (rods 1 through 12, group 1-8).
Specification 4.7.2.1 Whenever the control rod drive patch is reconnected (after test, l
reprogramming, or maintenance), each control rod drive mechanism shall be selected from the control room and exercised by movement of sufficient travel to verify that the proper rod has responded as shown on the unit computer printout or on the input to the computer for that rod.
4.7.2.2 Whenever power or instrumentation cables to the control rod drive assemblies atop the reactor or at the bulkhead are disconnected or removed, an independent verification check of their reconnection shall be performed.
4.7.2.3 Any rod found to be improperly programmed shall be declared inonerable until properly programmed.
Bases Each control rod has a relative and an absolute position indicator system.
One set of outputs goes to the plant computer identified by a unique number associated with only one core position. The other set of outputs goes to a programmable bank of 68 edgewise meters in the control room.
In the event that a patching error is made in the patch panel or connectors in the cables leading to the control rod drive assemblies or the control room meter bank is improperly transposed upon reconnection, these errors and transpositions l
will be discovered by a comparative check by (1) selecting a specific rod from one group (e.g., rod 1 in regulating group 6), (2) noting the program-approved core position for this rod of the group, (3) exercising the selected rod, and (4) noting that a) the computer prints out both absolute and relative position response for the approved core position, and b) the proper meter in the control room display bank indicates both absolute and relative meter positions.
This type of comparative check will not assure detection of improperly connected cables inside the reactor building.
For these, (Specification 4.7.2.2) it will be necessary for a responsible person, other than the one doing the work, to verify by appropriate means that each cable has been matched to the proper control rod drive assembly.
Amendment No. 102, 104 i
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