ML19320A207
| ML19320A207 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/17/1976 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19320A201 | List: |
| References | |
| NUDOCS 8004210510 | |
| Download: ML19320A207 (6) | |
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w;TE0 STATES 14UCLEAft liECULATORY cO.",11sslON y
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9 ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR CNE - UNIT 1 AMENDMENT TO FALILITY OPERATING LICENSE Amendment No. 17 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
.A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated October 7, 1976, as supplemented by letters dated October 18, November 11, November 16, and November 19, 1976, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (tha Act),
and the Commission's rulec :;id 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 amendment will not be inimical to the cormion 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.
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- s 2.TAccordingly,thelicenseisamandedby.changestothe. Technical Specifications as indicated in the attachment to this license
? amendment, and paragraph 2.b(2) of. Facility Operating License
- No. DPR-51.is hereby amended to read as follows:
b(2)~ Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to recei_ve, possess, and use. at any time any byproduct, source and special nuclear materials as reactor fuel, sealed neutron sources for reactor startup, scaled sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors, in accordance with the limitations for storage and amounts required for reactor operation 'as described in the Final Safety Analysis Report, as amended and in the application for license amendment dated October 7, 1976, as supplemented by letters dated October 1B, llovember 11, November 16 and November 19, 1976.
3.
This license amendment is effective as of the date of its issuance.
1 FOR THE fiUCLEAR REGULATORY C0t@tISSI0tl GM.::. - ' mad byI Ze!1.. ::J r Karl R. Goller, Assistant Director-for Operating Reactors Division of Operating Reactors Atta' chment:
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- Changes to the Technical
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Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMEf!DMEflT NO.17
- FACILITY OPERATIflG LICENSE N0. DPR-51
~ DOCKET f!0. 50-313 Replace existing pages 59, 59a, and 116 of-the Appendix A portion of the Technical Specifications with the attached revised pages bearing the same~ numbers.; The changed areas on the revised pages are identified by a marginal line.
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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.
Irradiated fuel _ shall not be removed from the reactor until the unit 3.8.11 has been suberitical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.8.12' 'All fuel handling in the Auxiliary Building shall cease upon notifi-
. cati 3% cf the issuance of a tornado watch for Pope, Yell, Johnson, or Logan counties in Arkansas. ' Fuel handling operations in progress will be completed to the_ extent necessary to place the fuel handling bridge and crane in their normal parked and locked position.
No loaded ' spent fuel shipping cask shall be carried above or into 3.8.13 the Auxiliary Building equipment shaf t unless atmospheric dispersion conditions are equal to or better than those produced by Pasquill In addi-type D stability accompanied by a wind velocity of 2 m/sec.
. tion,-the railroad spur door of the Turbine Building shall be closed
,uad the fuel handling area ventilation system shall be in operation.
For the maximum fuel pool heat load capacity (i.e., seven reload 3.8.14 batches (413 assemblies) stored in the pool at the time of discharge of the full core) the full core to be discharged shall be cooled in the reactor vessel 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.
3.8.15 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool.
3.8.16 The. spent fuel shipping cask shall not be carried by the l
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.
Bases Detailed written procedures will be available for use by refueling personnel These procedures, the above specifications, and the design of the fuel handl-ing equipment as described in Section 9.7' 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 This1 permits maintenance on the instrumentation. Continuous mon-sufficient.
itoring of radiation levels and neutron' flux provides immediate indication of.
an unsafe condition. The decay heat removal pump is used to maintain a uni-form boron concentration.(1) The shutdown margin indicated in Specification the core'suberitical, even with all control rods withdrawn 3.8.4 will keep (2)- The boron concentration will be maintained above 1800 ppm.
from the core.
'Although this concentration is sufficient to maintain the core keff 1 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 replacement. The keff with all rods in the core and with refueling boron concentration is approxi-mately 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.
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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.
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.
Specification 3.8.11 is required as the safety analysis for the fuel handling 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)
Specification 3.8.14, which requires cooling of the full core for 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge to the spent fuel pool when seven reload batches are already stored in the pool, is necessary to assure that the maximum design heat load of the spent fuel pool cooling system will not be exceeded.
Specification 3.8.15 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 loca' cions adjoining the walls at the north and st ath ends of the pool, in the vicinity of cask storage area and fuc' tilt pool access gates, until the review specified in 3.8.16 is com: ated.
Specification 3.8.16 assures that the spent fuel cask drop accident cannot occur prior to completion of the NRC staff's review of this potential accident and the completion of any modifications that may be necessary to preclude the accident or mitigate the consequences.
Upon satisfactory completion of the NRC's review, Specification 3.8.16 shall be deleted.
REFERENCES (1) FSAR, Section 9.5 i
(2) FSAR, Section 14.2.2.3 (3) FSAR, Section 14.2.2.3.3 59a i
Amendment No.117
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.. n fm 5.4 NEW AND SPENT FUEL STORAGE FACILITIES Applicability Applies to storage facilities for new and spent fuel assemblies.
l Objective To assure that both new and spent fuel assemblies will be stored in such a manner that an inadvertent criticality could not occur.
Specification 5.4.1 New Fuel Storage 1.
New fuel will normally be stored in the new fuel storage pool.
The fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 21 inches in both directions.
This spacing is sufficient to maintain a Keff of less than.9 even if flooded with unborated water, based on fuel with an enrichment of 3.5 weight percent U235.
2.
New fuel may also be stored in the spent fuel pool or in their shipping containers.
5.4.2 Spent Fuel Storage Irradiated fuel assemblies will be stored, prior to 1.
offsite shipment, in the stain 1uss steel lined spent fuel pool, which is located in the auxiliary building.
The pool is sized to accommodate a full core of irradiated fuel assemblies in addition to the concurrent storage of two and one-third cores of spent fuel previously discharged.
2.
The spent fuel pool is filled with borated water with a minimum concentration of 1800 ppm boron during refueling.
3.
One spent fuel storage rack position is designed to accommodate a special container for storage of a leaking fuel assembly.
4 The spent fuel pool and new fuel pool racks are designed as seismic Class 1 equipment.
5.
The design is based upon storage of spent fuel containing no more than 45.2 grams of Uranium-235 per longitudinal centimeter of assembly.
REFERENCES FSAR, Section 9.6 i
116 Amendment No. 17-
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