ML20133G941
| ML20133G941 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/14/1997 |
| From: | Salehi K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133G944 | List: |
| References | |
| NPF-06-A-178 NUDOCS 9701160233 | |
| Download: ML20133G941 (9) | |
Text
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UNITED STATES 3
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2006M001
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 178 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
1 A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated August 23, 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 i
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
4 9701160233 970114 PDR ADOCK 05000368 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. NPF-6 is hereby amended to read as follows:
i 2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.178, 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 C0fMISSION r
Kombiz Salehi, Acting Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 14, 1997
4 ATTACHMENT TO LICENSE AMENDMENT NO. 178 FACILITY OPERATING LICENSE NO. NPF-6
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DOCKET NO. 50-368 Revise 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. The corresponding overleaf pages are also provided to maintain document completeness.
I REMOVE PAGES INSERT PAGES j
3/4 9-14 3/4 9-14 3/4 9-16 3/4 9-16 i
B 3/4 9-3 8 3/4 9-3 5-5 b-5 i
REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying with 31 days after removal that laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52. Revision 2 March 1978.
3.
Verifying a system flow rate of 39,700 cfm i10% during.
system operation when tested in accordance with ANSI i
l N510-1975.
b.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verify-ing within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of *egulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of. Regulatory Guide 1.52, Revisioh 2, March 1978.
c.
. At leastace per 18 months by verifying that the pressure
. drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the system at a flow rate of 39,700 tfm i105.
d.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEP.A filter banks remove 5 99% of the DOP when they are testad in-place in accordance ~ith ANSI N510-1975 while operating the system at a fice rate of 39,700 cfm i 10%.
e.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove
> 99.95% of a halogenated hydrocarbon refrigerant test gas when They are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 39,700 cfm 110%.
ARKANSAS - UNIT 2 3/4 g-13 e
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REFUELING OPERATIONS FUEL STORAGE LIMITING CONDITION FOR OPERATION 3.9.12.a Storage in the spent fuel pool shall be restricted to fuel assemblies having initial enrichment less than or equal to 5.0 w/o U-235.
l The provisions of Specification 3.0.3 are not applicable.
3.9.12.b Storage in Region 1 or Region 2 (as shown on Figure 3.9.1) of the spent fuel pool shall be further restricted by the limits specified in Figure 3.9.2.
In the event a cross-hatch storage configuration is deemed necessary for a portion of either Region 1 or Region 2, vacant spaces diagonal to the four corners of any fuel assembly or vacant spaces on two opposite faces of any fuel assembly shall be physically blocked before any such fuel assembly may be placed in that region. Also, the Region 1 storage cells adjacent to the Region 2 interface are restricted to fuel assemblies that are outside of the area of the graph enclosed by Curve A on Figure 3.9.2.
In the event a checkerboard storage configuration is deemed necessary for a portion of Region 2, vacant spaces adjacent to the four faces of any fuel assembly shall be physically blocked before any such fuel assembly may be placed in Region 2.
The provisions of j
Specification 3.0.3 are not applicable.
3.9.12.c The boron concentration in the spent fuel pool shall be maintained (at all times) at greater than 1600 parts per million.
APPLICABILITY:
During storage of fuel in the spent fuel pool.
ACTION:
I suspend all actions involving the movement of fuel in the spent fuel pool if it is determined a fuel assembly has been placed in an incorrect location l
until such time as the correct storage location is determined. Move the assembly l
to its correct location before resumption of any other fuel movement.
i
)
Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined the pool boron concentration is less than 1601 ppm, i
until such tire as the boron concentration is increased to 1601 ppm or j
greater.
SURVEILLANCE REQUIREMENTS 4,9.12.a varify all fuel assemblies to be placed in the spent fuel pool have an initial enrichment of less than or equal to 5.0 w/o U-235 by checking the assemblies' design documentation.
4.9.12.b Verify all fuel assembljes to be placed in the spent fuel pool are within the limits of Figure 3.9.2 by checking the assemblies' design and burnup documentation.
4.9.12.c Verify at least once per 31 days the spent fuel pool boron concentration is greater than 1600 ppm.
ARKANSAS - UNIT 2 3/4 9-14 Amendment No. 44
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nGURE 3.9.2 MINIMUM BURNUF VS INITIAL ASSEMBLY AVERAGE U-235 LOADING 50.0 473 45D
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4 4 8 4 4 4. M 8. E 4 M M % 9 4 4 V % E. E. 4 E. S Imidal Asasambly Average U 235 landing Per Unk Length (g/ inch)
Curve A = 68.008x 19.366 when x > 0.399181 Curve B = 239.0lx'-347.75x'+243.18x-41.452 Curve C = -714.35x'+1335.80x -946.44x'+394.52x 47.040 8
l l
ARKANSAS-UNIT 2 3/4 9-16 Amendment No. 49,
1 KEFUELING OPERATIONS BASES l
I 3/4.9.9 and 3/4.9.10 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WATER LREEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 12% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM The limitations on the fuel handling area ventilation system ensure that all radioactive materials released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere. The operation of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
2/4.9.12 FUEL STORAGE Region 1 and Region 2 of the spent fuel storage racks are designed to assure fuel assemblies of less than or equal to 5.0 w/o U-235 enrichment that are within the limits of Figure 3.9.2 will be maintained in a subcritical array with K,gg 50.95 in unborated water. These conditions have been verified by criticality analyses, i
The requirement for 1600 ppm boron concentration is to assure the fuel assemblies will be maintained in a subcritical' array with K,ff 50.95 in the event of a postulated accident.
l ARKANSAS - UNIT 2 B 3/4 9-3 Amendment No. 44,M 6,
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DESIGN FEATURES VOLUKE 5.4.2 The total water and steam volume of the reactor coolant system is 10,295 1 400 cubic feet at a nominal T of 545'F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY - SPENT FUEL j
5.6.1.1 The spent fuel racks are designed and shall be maintained so that the calculated effective multiplication factor is no greater than 0.95 (including all known uncertainties) when the pool is flooded with unborated water.
1 CRITICALITY - NEW FUEL 5.6.1.2 The new fuel storage racks are designed and shall be maintained with a nominal 26.0 inch center-to-center distance between new fuel l
assemblies such that K gg will not exceed 0.98 when fuel having a maximum o
enrichtant of 5.0 weight percent U-235 is in place and aqueous foam mode.vation is assumed and K,gg will.not exceed 0.95 (including a conservative allowance for uncertainties) when the storage area is flooded with unborated water.
DRAINhqE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 399' 10 ".
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 988 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
ARKANSAS - UNIT 2 5-5 Amendment No. M,M,M,