ML20133P521
| ML20133P521 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/22/1997 |
| From: | - No Known Affiliation |
| To: | |
| Shared Package | |
| ML20133P523 | List: |
| References | |
| NPF-06-A-178 NUDOCS 9701240311 | |
| Download: ML20133P521 (3) | |
Text
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4 REFUELING OPERATIONS SURVEILLANCE REQUIREEsTS (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 + 105 during.
system operation when tested in accordance With ANSI M510-1975.
b.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorter 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 Regulatory 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 least.mce 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 1105.
d.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEP.A filter banks remove & 995 of the D0P when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 39,700 cfm i 105.
a.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers reenve
> 99.955 of a halogenated hydrocarbon refrigerant test pas when They are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 39,700 cfm 1105.
O e ARKANSAS - LMIT 2 3/4 9-13 970124031197b122 PDR ADOCK 05000368 P
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REFUELING OPERATIONS FUEL STORAGE LIMITING CONDITION FOR OPERATION 1
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 rigure 3.9.1) of the spent i
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 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:
Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined a fuel assembly has been placed au an incorrect location l
until such time as the correct storage location is determined. Move the assembly to its correct location before resumption of any other fuel movement.
Suspend all actions involving the movement of fu si ib the spent fuel pool if it is determined the pool boron concentration is f.es s than 1601 ppm, until such time as the boron concentration is inctsase d to 1601 ppm or greater.
SURVEILLANCE REQUIRDENTS 4.9.12.a Verify all fuel assemblies to be r. aced in the spent fuel pool have an initia) anrichment 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 assemblies 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 la): the spent fuel pool boron concentration is greater than 1600 ppa.
ARKANSAS - UNIT 2 3/4 9-14 Amendment No. 43,178
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ARKANSAS-thit 2 3/4 9-15 Amendment No-*43
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FIGURE M.2 MDS4UM BURNUP V1 INITIAL AMEMBLY AVERACE U-235 LOADING SQD 47J es
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su mb Y
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373 Rastnced ---
[' to Region 1 35A Non-metricted j
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N Specir4 j
2J es M. M. M M. M M.M M M M M M S M M
.8. 8. M M. M..M M S.
hidal Assensbh Average U-235 Imading Per Unk lange (ghwh) l Deg A = 68.008x 19.366 when x > 0.399181 i
Curve B = 239.0!x' 347.75x +243.18x 41.452
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8 Curve C = -714.35x*+1335.80x'-946.44x'+394.52x-47.040
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i ARKANSAf-UNIT 2 3/4 9-16 Asnandsment No. 44,178 4
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==d 3 /4.e.10 navan LEVEL-REACTOR VIS3EL AED SPENT FUEL POOL
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MTER LEVEL I
The restrictions on minimum water level ensure that sufficient water dayth is available to remove 99% of the assumed 126 iodine gay activity j
released from the rupture of an irradiated fuel assembly. The minimum unter depth is consistent with the assumptions of the accident analysis.
1 j
214.9.11 FUIL EannLING AREA V]prffLATICE SYSTEM
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J The limitations on the fuel handling area ventilation system ensure 3
that all radioactive materials released from an irradiated fuel assembly l
will be filtered through the NEPA filters and charcoal adsorbers prior to j
discharge to the stasephere. The operation of this system and the
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resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
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l 3 /4. e.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
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within the limits of Figure 3.9.2 will be maintained in a suberitical array with l
I,gg 50.95 in unborated water. These conditions have been verified by criticality analyses.
The requirement for 1600 ppa boron concentration is to assure the fuel assemblies will be maintained in a suberitical array with K,gg 50.95 in the event of a postulated accident.
naInssas - UsIT 2 s 3/4 9-3 Amendment so. 44,466,178
9 t
es DESIGN FEATURES M
5.4.2 The total water and steem volume of the reactor coolant system is 10,295 t 400 cubic feet at a mamtmal T of 545'F.
avg 5 5 METEORDIAGIckL TOWER EDCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STOR&GE CRITIchLITY - APENT FUEL 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.
CRITICALITY - EEW 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
1 assemblies such that E.gg will not exceed 0.98 when fuel having a maximum enrichment of 5.0 weight percent U-235 is in place and aqueous foam moderation is assumed an6 E.gg will not exceed 0.95 (including a conservative allowance for uncertainties) when the storage area is flooded with unborated water.
M &IEAGE 5.6.2 The spent fuel etcrage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 399' 10 ".
C&PACITY 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 COMPORIENT CTCLIC CEt TR&ESIENT 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.
AREARSAs - UNIT 2 5-5 Amendment No. M,M,M,178
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