ML20072B070
| ML20072B070 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/04/1994 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072B071 | List: |
| References | |
| NUDOCS 9408150363 | |
| Download: ML20072B070 (3) | |
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UNITED STATES L.kL<)1 NUCLEAR REGULATORY COMMISSION w
7f WASHINGTON, D.C. 20066-0001 g, v y i
ENTERGY OPERATIONS INC.
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DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.173 i
License No. DPR-51 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated March 3, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
i and the Commission's rules and regulations set forth in 10 CFR i
Chapter I; i
B.
The facility will cperate 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.
i 9408150363 940004 PDR ADOCK 05000313-P ppg j
e I 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.173, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
t FOR THE NUCLEAR REGULATORY COMMISSION Y
~--A bl W William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance: August 4, 1994 i
l I
ATTACHMENT TO LICENSE AMENDMENT N0.173 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 area of change.
REMOVE PAGES INSERT PAGES 59a 59a 59b 59b e
E..
3.8.25 Storage in the spent fuel pool shall be resgricted to fuel assemblies l
having initial enrichment less than or equal to 4.1 w/o U 235.
The provisions of Specifications 3.0.3 are not applicable.
3.8.36 Storage in Region 2 (as shown on Figure 3.8.1) of the spent fuel pool l
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 sssembly 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 are not applicable.
3.8.17 The boron concentration in the spent fuel pool shall be maintained (at l
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 indice. tion 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
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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 boron stratification.(l) ine recuirement to have two decay heat removal loops operable when there is less than 23 feet cf water above the core, ensures that a s'cgle 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 l
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 15 provided to initiate emergency procedures to cool the core.
The shutdown margin indicated in Specification 3.8.4 will keep the core subtritical, even with all control rods withdrawn from the core.(2) Although the refueling boron concentration is sufficient to maintain the core keff s 0.99 if all the control rods were removed from the core, only a few control rods will be removed at any one time during fuel shuffling and Amenoment ho. 4J. M. W. 4. MJ, 59a 444, 444, 173
r epl a c eme nt. The keff with all rods in the core and with refueling botan concentration is approximately 0.9.
Specification 3.8.5 allows the control room operator to inform the reactor building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.
The specification requiring testing reactor building purge termination is to verify that these components will function as required should a fuel handling accident occur which resulted in the release of significant fission products.
e Because of physical dimensions of the fuel bridges, it is physically impossible for fuel assemblies to be within 10 feet of each other while being handled.
l Specification 3.8.11 is required as: 1) the safety analysis for the fuel hanoling accident was based on the assumption that the reactor had been shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.(3): and, 2) to assure that the maximum design heat load of the spent fuel pool cooling system will not be exceeded during a full core offload.
Specification 3.8.14 will assure that damage to fuel in the spent fuel pool will not be caused by dropping heavy objects onto the fuel.
Administrative controls will prohibit the storage of fuel in locations adjoining the walls et the north and south ends of the pool, in the vicinity of cask storage erea and fuel tilt pool access gates.
Spen fications 3.8.15 and 3.8.16 assure fuel enrichment and fuel burnup l
l limits assumed in the spent fuel safety analyses will not be exceeded.
Specification 3.8.17 assures the boron concentration in the spent fuel pool l
t will remain within the limits of the spent fuel pool accident and criticali ty analyses.
i REFEREtCES (2)
FS AR. Se:Iton 9.5 (2)
FS AR, Section 14.2.2.3 l
(3)
FSAR, Section 14.2.2.3.3
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l Amencment No. 46. &J. 04,173 59b
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