ML20117H953
| ML20117H953 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/23/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20117H936 | List: |
| References | |
| NUDOCS 9609100094 | |
| Download: ML20117H953 (13) | |
Text
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PROPOSED TECHNICAL SPECIFICATION CHANGES l
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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) i i
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1 CRITICALITY ANALYSIS i
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PROPOSED TECHNICAL SPECIFICATION CI(ANGES i
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v 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 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 event fuel pool sball be maintained (at all times) at greater than 1600 parts per ndllion.
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 in 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 fuel in the spent fuel pool if it is determined the pool boron concentration is less than 1601 ppm, until such time as the boron concentration is increased to 1601 ppm or greater.
SURVEILLANCE RFOUIREMENTS 4.9.12.a Verify 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 l
checking the assemblies' design documentation.
4.9.12.b Verify all fuel assemblies to be placed in the spent fuel pool are
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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.
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ARKANSAS - UNIT 2 3/4 9-14 Amendment No. 44
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s' REFUELING OPERATIONS BASES 3/4.9.9 and 3/4.9.10 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL 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 ILmitations on the fuel handling area ventilatior. 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 syttom and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
3/4.9.12 FUEL STORAGE Region 1 and Region 2 of the spent fuel storage racks are designed to assure fuel assemblies of less then 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 suberitical array with K,gg 50.95 in unborated water. These conditions have been verified by criticality analyses.
The requirement for 1600 ppm 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.
ARKANSAS - UNIT 2 B 3/4 9-3 Amendment No. M,%6,
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DESIGN FEATURES VOLUME 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 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 - 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 Keff 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 and X,gg will not exceed 0.95 (including a conservative allowance for uncertainties) when the storage area is flooded with unborated water.
DRAINAGE 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. e4,-7+,95,
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1 MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS l
(FOR INFO ONLY) i
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t' t.
J 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 4rt_ gag w/o U-235.
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.The provisions of Specification 3.0.3 are not applicable.
3.9.12.b Storage in Reaion 1 or Region 2.(as shown on Figure 3.9.1) of the spent fuel pool shall be further restricted by hbweney-end-enrieheuenb-lhnits specified in Figure 3.9.2.
In the event a cross-hatch storaae confiouration is deemed necessary for a cortion of either Reaion 1 or Reaion 2.
vacant soaces diaconal to the four corners of any fuel assembiv or vacant soaces on two ocoosite faces of any fuel assembiv shall be ohvsically blocked before any such fuel assembly may be niaced in that racion.
Also, the Reaion 1 storaos cells adiacent to the Reaion 2 interface are restricted to fuel assemblies that are outside of the area of the araoh enclosed by curve A on Fiaure 3.9.2.
In the event a checkerboard storage configuration is deemed necessary for a portion of Region 2, vacant ' spaces adjacent to the ig.gr_ faces of any fuel assembly wh&eh f::: ;;t c::t th; 2;;i;; 2 i;;;;p ;;it;;i; p:;; n;;tri;t;d) shall be physically blocked before any such fuel assembly may be placed in Region 2.
Thi; will p;;;;;; in;3._;;;;t
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The provisions of Specification 3.0.3 are not applicable.
3.9.12.c The boron concentration i the spent fuel pool shall be maintained (at all times) at greate.
'an 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 in bhe gg incorrect 2:;i;;
12E&g gg until such time.as the correct storage location is determined. Move the j
assembly to its correct location before resumption of any other fuel movement.
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, until such time as the boron concentration is increased to 1601 ppm or greater.
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SURVEILLANCE REQUIREMENTS 4.9.12.a Verify all fuel assemblies to be placed in the spent fuel pool had3 an initial enrichment of less than or equal to 4r+ M w/o U-235 by checking the assemblies; design documentation.
4.9.12.b Verify all fuel assemblies to be placed in n;;is; ef the spent fuel pool are within the ;;;ich;.;;t ;;d b;;;;p 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.
i ARKANSAS - UNIT 2 3/4 9-14 Amendment No. 44
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V FIGURE 3.9.2 MINIMUM BURNUP VS. INITIAL ENRICHMENT FOR REGION 2 STORAGE h
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1.0 (o,1,4) 2.0 3.0 4.0 (o,4,1) initial Assembly Average Enrichment (w/o U-235) i ARKANSAS-UNIT 2 3/4 9-16 Amendment No. 43
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1 REFUELING OPERATIONS e
BASES 3/4.9.9 and 3/4.9.10 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL i
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.
j l
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 j
discharge to the atmosphere. The operation of this system and the i
resulting iodine removal capacity are consistent with the assumptions of the accident analyses.
3/4.9.12 FUEL STORAGE Region 1 and Recion 2 of the spent fuel storage racks fe_ggg designed to assure fuel assemblies of less than or equal to 4rt 5.0 w/o U-235 enrichment thg1 ggg;will b; 2.cinteined in ; ;;beritical ersey with X,44-50.0; in unter;ted w;ter.
Th;;; ;;;diti;n; h;;; i;;; ;;rified by criti;;11ty en ly;;;.
n;gien 2 cf th; sp;nt f;;l terag; r;;h; i; d;;ign;d t: ;;;;;; f;;l eseemb M ee within the burnup ;.nd initi;l enri;F.;nt limits of Figure 3.9.2 will be maintained in a suberitical array with Keff 50.95 in unborated 1
^
water. These conditions have been verified by criticality analyses.
The requirement for 1600 ppm boron concentration is to assure the fuel assemblies will be maintained in a subcritical array with K,gg 50.95 in the event of a postulated accident.
I ARKANSAS - UNIT 2 B 3/4 9-3 Amendment No. +3,% 6,
/
Y DESIGN FEATURES I
VOLUME 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.
l 5.6 FUEL STORAGE CRITICALITY - SPENT 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 - NEW FUEL 5.6.1.2 The new fuel storage racks are designed and shall be maintained i
with a nominal 266.0 inch center-to-center distance between new fuel l
assemblies such that K gg will not exceed 0.98 when fuel having a maximum e
enrichment of 4v4_5 0 weight percent U-235 is in place and aqueous foam 2
moderation is assumed and K gg will not exceed 0.95 (includino a conservative l
e allowance for uncertainties) when the storage area is flooded with unborated water.
The ::1 ulated K gg includ :
conserv:tive alleuene: ef 2.1S Ak/k-fee e
une :t:fettee,-
i DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be naintained to prevent inadvertent draining of the pool below elevation 399' 10b".
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. e4,74,96,
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1 CRITICALITY ANALYSIS 1