ML20117P642
| ML20117P642 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/20/1996 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117P644 | List: |
| References | |
| NUDOCS 9609240399 | |
| Download: ML20117P642 (5) | |
Text
_
eS E8c g
og lt UNITED STATES j
y-j j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 206 6 0001 i
\\...../
ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 License No. DPR-51 i
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:
j A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated May 19, 1995, as supplemented by letters dated July 21, 1995, and June 10, September 10 and 13, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l
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.
V I
9609240399 960920 PDR ADOCK 05000313 P
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:
i 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 184, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
[J^
0Ll,
e./ ogTep (4.
d,e cow Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
September 20, 1996 I
3 1
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 184 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 1
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 59 59 59b 59b 1
1 l
r 3.9.6 During th2 b:ndling of irradiated funi in the rsector building, at least one door on the personnel and emergency hatches shall be capable
- of being closed. The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces. At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated within the reactor pressure vessel.
- 3. 0. "1 Isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be closed.
l 3.8.0 when two irradiated fuel assemblies are being moved simultaneously by the bridges within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemblies at all times.
l 3.P.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall ceases action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may l
increase the reactivity of the core shall be asade. The provisions of specification 3.0.3 are not applicable.
3.8.10 The reactor building purge isolation system, including the radiation monitors shall be tested and verified to be operable j
within 7 days prior to refueling operations. The provisions of Specification 3.0.3 are not applicable.
3.6.11 Irradiated fuel shall not be removed from the reactor until the unit has been suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.
In the event of a l
cosplete core offload, a full core to be discharged shall be subcritical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge of more than 70 assemblies to the spent fuel pool. The provisions of specification 3.C.3 are not applicable.
3.9.12 All fuel handling in the Auxiliary Building shall cease upon notification of the. issuance of a tornado watch for Pope, Yell, Johnson, or Logan counties in Arkansas. Fuel bandling operations in progress will be completed to the extent macessary to place the fuel handling bridge and crane in their normal parked and locked position. The provisions of Specification 3.0.3 are not applicable.
3.9.13 No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmospheric dispersion conditions are equal to or better than those produced by Pasquill Type D stability accompanied by a wind velocity of 2 m/sec.
In addition, the railroad spur door of the Turbine Building shall be closed and the fuel handling area ventilation system shall
.be in operation. The provisions of Specification 3.0.3 are not applicable.
3.8.14 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool. The provisions of l
Specification 3.0.3 are not applicable.
l
- Administrative controls shall ensure that appropriate personnel are sware that both personnel airlock doors are open, a specific individual (s) is designated and available to close an airlock door following a required evacuation of containment, and any obstruction (s) (e.g., cables and hosas) that could prevent closure of an airlock door be capable of being quickly removed.
Amendment No. M,M,M,p,M,Mhl84 59
... =. - -.
-. -.. -.. - ~. -.... ~ - -..
- - ~
replacement. The keff with all rods in the core and with refueling boron concentration is approximately 0.9.
Specification 3.8.5 allowe 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.
l The specification requiring testing reactor building purge termination is to verify that these components will function as required should a fuel j
handling accident occur which resulted in the release of significant fission products.
l i
Because of physical dimensions of the fuel bridges, it is physically j
Lapossible for fuel assemblies to be within 10 feet of each other while being handled.
i Per specification 3.8.6, the reactor building personnel and/or emergency airlock doors may be open during movement of irradiated fuel in the reactor building provided at least one door is capable of being closed in the event of a fuel handling accident and the plant is in REFUELING SHUTDOWN with 23 feet of water above the fuel seated within the reactor pressure vessel. Should a fuel handling accident occur inside the reactor building, at least one of the personnel and/or emergency airlock doors will be closed following evacuation of the reactor building.
Specification 3.8.11 is required as:
- 1) the safety analysis for the fuel handling accident was based on the assumption that the reactor had been shutdown for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> (s); and, 2) to assure that the maximum design heat l
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 at the north and south ends of the pool, in the vicinity of cask storage area and fuel tilt pool access gates.
Specifications 3.8.15 and 3.8.16 assure fuel enrichment and fuel burnup 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 will remain within the limits of the spent fuel pool accident and criticality analyses.
REFERENCES (1)
FSAR, Section 9.5 (2)
FSAR, section 14.2.2.3 (3)
FSAR, Section 14.2.2.3.3 Amendment No. %,W,%,HG,184 59b
-. _ _