ML20205Q768
| ML20205Q768 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/16/1999 |
| From: | Gramm R Office of Nuclear Reactor Regulation |
| To: | Entergy Operations |
| Shared Package | |
| ML20205Q771 | List: |
| References | |
| DPR-51-A-195, NPF-06-A-203 NUDOCS 9904220062 | |
| Download: ML20205Q768 (10) | |
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h UNITED STATES
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j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20666-0001 l
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO.1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.195 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 28,1996, as supplemented by letters dated February 23 and March 15, l
1999, 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; l
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.
l 9904220062 990416 PDR ADOCK 05000313 P
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I t 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 Soecifications The Technical Specifications centained in Appendix A, as revised through l
Amendment No. 195, 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 and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
k h
Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning l
Division of Licensing Project Management Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance: April 16,1999 l
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k ATTACHMENT TO LICENSE AMENDMENT NO.195 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove Insert 59 59 59b 59b l
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3.8.6 During ths hrndling of irradictsd fusl in tha roactor building, et least cna dont en ths paracnnal end emerg:ncy hetchss chsll be c!p ble* of being closed.
The' equipment hatch cover shall also be capable
- of being closed. At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated within the reactor pressure vessel.
3.8.7 Isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be closed.
3.8.8 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.
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3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core 4
shall cease; action shall be initiated to correct the conditions so l
that the specified limits are met, and no operations which may
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increase the reactivity of the core shall be made. The provisions of Specification 3.0.3 are not applicable.
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3.8.10 The reactor building purge isolation system, including the radiation monitors shall be tested and verified to be operable within 7 days prior to refueling operations. The provisions of Specification 3.0.3 are not applicable.
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3.8.11 Irradiated fuel shall not be removed from the reactor until the 1
unit has been subcritical 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 complete core offload, a full core to be discharged shall be suberitical 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 3.0.3 are not applicable.
J 3.8.12 All fuel handling in the Auxiliary Building shall cease upon j
notification of the issuance of a tornado watch for Pope, Yell, j
Johnson, or Logan counties in Arkansas.
Fuel handling operations
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in progress will be completed to the extent necessary 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.
3.8.13 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 Specification 3.0.3 are not applicable.
- Administrative controls shall ensure that appropriate personnel are aware that both personnel airlock doors and/or equipment hatch are open, a specific individual (s) is designated and available to close an airlock door and the equipment hatch cover following a required evacuation of the reactor building, and any obstruction (s) (e.g.,
cables and hoses) that could prevent closure of an airlock door and the equipment hatch cover be capable of being quickly removed.
Amendment No.
59 M, M, M, M, M, M, M 4.196
rcplacement. Tho koff with all rods in the coro end with refusling boren canc:ntretien is cpproximately 0.9.
Sp:cification 3.8.5 allcws tha centrol 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.
1 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.
Per specification 3.8.6, tha reactor building personnel and/or emergency airlock doors and the equipment hatch may be open during movement of irradiated fuel in the reactor building provided at least one door of each airlock and the equipment hatch are 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 and the equipment hatch will be closed following evacuation of the reactor building.
For closure, the equipment hatch cover will be in place with a minimum of four bolts securing the cover to the sealing surface.
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 /> (8); 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 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 L
59b gndmentNo.M,H,M,M4,M4,
@ TE4 UNITED STATES g
Ij NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 206664m01
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.203 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 28,1996, as supplemented by letters dated February 23 and March 15,1999, 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 bemi satisfied.
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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 l
Operating License No. NPF-6 is hereby amended to read as follows:
J (2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 203, 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 and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A M%
Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 16,1999 4
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ATTACHMENT TO LICENSE AMENDME(IT NO.203 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-363 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Remove logarj 3/4 9-4 3/4 9-4 B 3/4 9-1 B 3/4 9-1 4
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j REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4-The containment building penetrations shall be in the following status:
a.
The equipment door is capable of being closed, l
b.
A minimum of one door in each airlock is capable
- of being closed, and l
c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Exhausting through OPERABLE containment purge and exhaust system HEPA filters and charcoal adsorbers.
APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be determined to be in its above required conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment.
4.9.4.2 The containment purge and exhaust system shall be demonstrated OPERABLE at the following frequencies:
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a.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or l
(2) following pairting, fire or chemical release in any ventilation zone communicating with the system by:
- Administrative controls shall ensure that appropriate personnel are aware that both personnel airlock doors and/or equipment door are open, a specific individual (s) is designated and available to close an airlock door and the equipment door following a required evacuation of containment, and any obstruction (s)
(e.g., cables and hoses) that could prevent closure of an airlock door and the equipment door be capable of being quickly removed.
ARKANSAS - UNIT 2 3/4 9-4 Amendment No. 446,203
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3/4.9 REFUELING OPERATIONS l
l BASES 3/4.9.1 BORON CONCENTRATION The limitations on reacfivity conditions during REFUELING ensure that: 1) the reactor will remain subcritical during CORE ALTERATIONS, and
- 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the I
boron dilution incident in the accident analyses.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the accident analyses.
The minimum requirement for reactor suberiticality prior to movement of more than 70 irradiated fuel assemblies to the spent fuel pool ensures that sufficient time has elapsed to allow radioactive decay of the short-lived fission products such that the heat generated will not exceed the cooling capacity of the j
spent fuel pool cooling system. This decay time and total assembly limitation is conservatively within the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY of the containment purge and exhaust system HEPA filters and charcoal adsorbers ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
Operation of the containment purge and exhaust system HEPA filters and charcoal adsorbers and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
The containment personnel airlock doors may be open during movement of irradiated fuel in the containment and during CORE ALTERATIONS provided a minimum of one door in the airlock and the equipment door are capable of being closed in l the event of a fuel handling accident and the plant is in MODE 6 with 23 feet of water above the fuel seated within the reactor pressure vessel.
Should a fuel.
handling accident occur inside containment, a minimum of one personnel airlock door and the equipment door will be closed following an evacuation of containment.
For closure, the equipment door will be held in place by a minimum of four bolts.
ARKANSAS - UNIT 2 B 3/4 9-1 Amendment No. u,u6,203
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