ML20203A541
| ML20203A541 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/04/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203A547 | List: |
| References | |
| NUDOCS 9902100029 | |
| Download: ML20203A541 (5) | |
Text
-
l.'
FtEFUELING OPERATIONS 3/4 9.12 SPENT FUEL ASSEMBLY STORAGE 4
LIMITING CONDITION FOR OPERATION 3.g.12 Spent fuel assemblies stored in either the Spent Fuel Pool or cask loading pit shall be subject te one of the following conditions:
a.
Spent fuel assemblies regardless of bumup can be placed in Region 1.
i b.
Spent fuel assemblies within the bumup enrichment range shown in Figure 3.9-1 for Region 2 fuel shall be placed in Region 2 or 3.
c.
Spent fuel assemblies within the bumup enrichment range shown in Figure 3.9-1 for Region' 3 fuel shall be placed in Region 3.
APPLICABILITY: Whenever irradiated fuel assemblies ye in the spent fuel pool or cask loading pit.
ACTION j
a.
Wdh the requirements of the above specification not satisifed, suspend all other movement of fuel assemblies and crane operations with loads in the fuel storage areas and move non-complying fuel assemblies to Regioni. Until the requirements of the above specification are satisifed, boron concentration of the a
j, spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, f
b.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
I SURVEILLANCE REQUIREMENTS 4.9.12 The bumup of each spent fuel assembly stored in Regions 2 and 3 shall be ascertained by analysis of its bumup history and independently verified prior to storage in Regions 2 or 3. A i
complete record of such analyals shall be kept for the time period that the spent fuel assembly j
remains in Regions 2 or 3 of the spent fuel pool or cask loading pit.
I l
}
i 3
CALLAWAY-UNIT 1 3/4915 Amendment No.129 9902100029 990204 PDR ADOCK 05000483
.P.
PDR vn:
i'-
j FIGURE 3.9-1 i
l MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF l
INITIAL ENRICHMENT TO PERMIT STORAGE IN REGIONS 2 AND 3 i
+
55000 4
e
~..
t
-l 50000 s^h!. / J.^.',.:FOR REGION 2 AND3S"ORAGE
~
/
ACCEPTABLE.BURNUR D0 MAIN
.'s,.45000.
i s
- C i.
i
. k.. r'.... s.... <s.
u.
.s
, ~.
. s a
s.
..J.
g, 3
.. s,
.v-
<40000
,, s.
w
. y :::s :
':l.:-
.. : i..
p+..
$.'y'.. e.:
Ph: !
l N
x
- p. s..
,u,.
.w.
%>. :. s x n. '.:'...
o..
/,
g
- g.
25000
.3 h
~
1 p.
p.
20000
^v e
4 J
g
=
s i(
n 15000 w
/&
/
h
-J 10000 w
UNAC CEPTAB LE BURNUP D OMAIN E-FOR1 REGION 2 OR 3 STO)tAGE 5000 0,....,....,....,....,....,....,....
1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 FUEL ASSEMBLY INITIAL ENRICHMENT (w/o U-235)
CALLAWAY. UNIT 1 3/4 9-16 Amendment No.49;99:09:499,129
.~.
_._ _ _. _ _ _.... _ _ _. _ _ _ _ _. _ _. _ _ _ _ _ _ _ _ _ ~. _. _. _ _ _ _.
REFUELING OPERATIONS l
BASES removal capability. With the reactor vessel heat removed and at least 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling. Thus, in the event of a
.l failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
4 3/4 9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensurea that the containment purge penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release cf radioactive material from the containment atmosphere to the environment.
3/4.9.10 and 3/4.911 WATER LEVEL - REAQTOR VESSEL AND STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 9g% of the assumed 10% lodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.
3/4 9.12 SPENT FUEL ASSEMBLY STORAGE The racks for the spent fuel pool and cask loading pit are designed for storage of both new fuel and irradiated fuel. Prior to storage of fuel assemblies in either the spent fuel pool or cask loading pit, overall pool storage Regions shall be prepared in accordance with 0
administrative controls. The restrictions placed on fuel assemblies stored in the spent fuel pool and cask loading pit ensure inadvertent criticality will not occur. Region 1 is designed to accommodate new fuel with a maximum nominal initial enrichment of 5.0 weight percent U-235, or spent fuel regardless of the discharge fuel bumup. Region 2 and Region 3 are designed to accommodate fuel of various initial enrichments which have accumulated minimum bumups within the acceptable domain according to Figure 3.9-1, in the accompanying LCO.
3/4.9.13 EMERGENCY EXHAUST SYSTEM The limitations on the Emergency Exhaust System ensure that all radioactive materials released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operation of the system with the hesters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses. ANSI N5101975 will be used as a procedural guide for surveillance testing. ASTM D 3803-1989 will be used as a procedural guide for the laboratary testing of charcoal samples.
CALLAWAY-UNIT 1 B 3/4 9-3 Amendment No. 0+;446,129
_ __.: ~. ~
i J
DESIGN FEATURES i
l 5 3 REACTOR CORE I
FUEL ASSEMBLIES l
5.3.1 The core shall contain ig3 fuel assemblies with each fuel assembly normally containing 5
264 fuel rods clad with Zircaloy 4 or Zirlo, except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4, stainless steel, or Zirlo may be made if justified by a cycle-specific l
l reload analysis. Each fuel rod shall have a nominal active fuel length of 144 inches and contain l
a maximum total weight of 1766 grams uranium. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichment of 5.00 weight percent j
I CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. All control rods shall be hafnium, silver-indium-cadmium, or a mixture of both types. All control rodt shall be clad with stainless steel tubing.
i.
i 54 REACTOR COOLANT SYSTEM i
DESIGN PRESSURE AND TEMPERATURE i
j 5.4.1 The Reactor Coolant System is designed and shall be maintained:
i j
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal, degradation pursuant to the applicable Surveillance Requirements, i
b.
For a pressure of 2485 psig, and j
l c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total volume of the Reactor Coolant System, including pressurizer and surge line, is 12,135
- 100 cubic feet at a nominal T.,, of 557'F.
5.5 METEOROLOQlCAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
CALLAWAY-UNIT 1 56 Amendment No. 12,22,24,41,M, 499:449,129
d
'2 DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained:
l a.
With a 4 equivalent to less than or equal to 0.95 when flooded with unborated l
water, which includes an allowance for unwrtainties as described in Section 9.1 of the FSAR. This is based on fresh fuel with the maximum initial enrichment of LA235 in Region 1 and on spent fuel with an acceptable combination of initial enrichment and discharge exposures, shown in Figure 3.91 for Region 2 and Region 3, and _
b.
With a nominal 8.99 inch center-to-center distance between fuel essemblies l
placed in the storage racks, and c.
For fuel with nominal enrichments greater than 4.60 weight percent U-235, the combination of enrichment and integral fuel bumable absorbers shall be sufficient so that the requirements of Specification 5.6.1.1.a are met. Integral fuel bumable absorbers are not required for Region 1 rack locations on the periphery of the pool adjacent to a concrete wall.
5.6.1.2 The 4 for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.
DJSAINAGE 5.6.2 The fuel storage poolis designed and shall be maintained to prevent inadvertent j
draining of the pool below elevation 2040 feet.
CAPACITY 5.6.3 The spent fuel storage poolis designed and shall be maintained with a storage capacity limited to no more than 2363 fuel assemblies. The cask loading pit is designed and shall be
~
maintained with a storage capacity limited to no more than 279 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 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.
CALLAWAY-UNIT 1 57 Amendment No. 49;e9;64:499,129 (Next page is 5 9) i
.....