ML20086A647
| ML20086A647 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/06/1991 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086A649 | List: |
| References | |
| NUDOCS 9111190283 | |
| Download: ML20086A647 (4) | |
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.![o UNITED STATES p,
NUCLEAR REGULATORY COMMISSION 4
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ENTERGY OPERATIONS 170.
DOCKET f40. 50-313 ARKANSAS NUCLEAR ONE. UNIT N0. -1 AMENDMENT T0-FACILITY OPERATING LICENSE Anenoment No. 153 License No. DPR-51 1.
The Nuclear Regulatory Cons.ission (the Comission) has found that:
A.
The application for arnendnent by Entergy Operations, Inc. (the-licensee) dated June 27, 1991, as supplenented August 22, October 4, and October 16, 1991, cunplies with the standarcs and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commissior.'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 cf the Comission; C.
There is reasonable assurance:
(1) that the activities authorized by this amer.dment can be conducted without endangering the health and safety of the public, end (ii).that such activities will be conoucted in compliance with the Comission's regulations; D.
The issuance of this license amendment will not be inimical to the cuum.on 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 Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arenan.ent, and Paragraph 2.C.(2) of Facility 0perating 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.153, are hereby incorporated in-the license. The licensee shall operate the facility in accordance-with the Technical Specifications.
3.
Tre license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g a /lb John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Chur.ses to the Technichi Specifications Date of Issuance: November 6, 1991 e
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l ATTACHMENT TO LICD!SE AMENDMENT NO.153 '
FACILITY OPERATING LICENSE NO. OPR-51 DOCKET NO. 50-313 Revise the following pages of. the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicatirig the area of change.
REMOVE PAGES INSERT PAGES 59a-59a i
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3.8.15* The spent fuel shipping cask shall not be carried by the Auxiliary Building crane pending the evaluation of the spent fuel cask drop accident and the crane design by AP&L and NRC review and approval. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
3.8.16 Storage in the spent fuel pool shall be restricted to fuel assemblies having initial enrichment less than or equal to 4.1 w/o U-235.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
3.8.17 Storage in Region 2 (as shown on Figure 3.8.1) of the spent fuel pool shall be further restricted by burnup and enrichment limits specified in Figure 3.8.2.
In the event a checkerboard storage configuration is deemed necessary for a portion of Region 2, vacant spaces adjacent to the faces of any fuel assembly which does not meet the Region 2 burnup criteria (non-restricted) shall be physically blocked before any such fuel assembly may be placed in Region 2.
This will prevent inadvertent fuel assembly insertion into two adjacent storage locations. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
3.8.18 The boron concentration in the spent fuel pool shall be maintained (at all times) at greater than 1600 parts per million.
Bases Detailed written procedures will be available for use by refueling personnel.
These procedures, the above specifications, and the design of the fuel handling equipment as described in Section 9.6 of the FSAR incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety.
If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition.
The requirement that at least one decay heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel at the refueling temperature (normally.140'F), and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boren stratification.(*)
The requirement to have two decay heat removal loops operable when there is less than 23 feet of water above the core, ensures that a single fe llure of the operating decay heat removal loop will not result in a complete loss of decay heat removal capabilit y.
With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating decay heat removal loop, adequate time is provided to initiate emergency procedures to cool the core.
The shutdown margin indicated in Specification 3.8.4 will keep the core suberitical, even with all control rods withdrawn from the core.(8) Although the refueling boron concentration is sufficient to maintain the core k 5 0.99 ifallthecontrolrodswereremovedfromthecore,onlyafewcontro1*fbdswill be removed at any one time during fuel shuffling and Note:
- An exception to 3.8.15 is granted for the period of October 15, 1991, through January 31, 1992, for the movement of two spent fuel rods utilizing a 17 ton shipping cask.
Amendment No. 11, JJ, J/, /A, Jp7, 59a 153
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