ML20235P549
| ML20235P549 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/10/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235P552 | List: |
| References | |
| NUDOCS 8707200525 | |
| Download: ML20235P549 (4) | |
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n acog'o UNITED STATES y,_
NUCLEAR REGULATORY COMMISSION n
,E WASHINGTON, D. C. 20555 i
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ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 f
License No. DPR-51 The Nuclear. Regulatory Commission (the Commission) bas fou$d that:
1.
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated May.6, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended j
l (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 I
endangering the health and safety of the public, and (ii) that l
such activities will be conducted in compliance with the Commission's regulations; 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 sccordance with 10 CFR Part 51 of the Commission's regulations and all applicable l
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 amendment, and paragraph 2.c.(2) of Facility Operating License No.
OPR-51 is hereby amended to read as-follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.107,'are hereby incorporated in the license.
The licensee shall operate the facility in accordsnce with.the Technical Specifications.
3.
.This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION m
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects l
Office ~of Nuclear Reactor Regulation l
Attachment:
Changes'to the Technical Specifications Date of Issuance:
July 10,1987 l
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ATTACHMENT TO LICENSE AMENDMENT NO.107 TO FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace 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 indicating the areas of change.
Remove hsert l
59a 59a l
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3.8.15^
The spent fuel shipping task 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 Specific 6tions 3.0.3 and 3.0.4 are not applicable.
3.8.16 Storage in the spent fuel pool shall be restricted to tuki 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 f aces 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 pieced 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 inter-locks 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 I
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 main-tained through the reactor core to minimi y}heeffectsofaborondilution incident and prevent boron 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 failure of the operating decay heat removal loop will not result in a complete loss of decay heat removal capability.
With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, j
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.
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The shutdown margin indicated in Specification 3.8.4 will keep tgcore subcritical, even with all control rods withdrawn from the core Although the refueling boron concentration is sufficient to maintain the core k
< 0.99 if all the control rods were removed from the core, only a fewcobcIrodswillberemovedatanyonetimeduringfuelshufflingand Note:
- A one tima exception to 3.8.15 is granted for the period of July 13, 1987 through August 12, 1987.
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Amendment No. U, EB, 57, 76. 107 59a I
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