ML20133H663
| ML20133H663 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/15/1985 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20133H641 | List: |
| References | |
| ULNRC-1192, NUDOCS 8510180060 | |
| Download: ML20133H663 (7) | |
Text
{{#Wiki_filter:_. ._. _ _ . . _ . . _ . _ - _ - _ _ _ . _ . - . Enclosure 3 ULWRC-1192 I October 15, 1985 i i J t
. s i ,t i MARKED TECilNICAL SPECIFICATION PAGES I
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' REVisl0N I RLFlitt(NG OPERATIONS 3/4.9_12 SPENT FUEL ASSEMBLY STORACE s, ,
' t!MtitNG CON 0! TION FOR OPERATION 3.9.12 Spent fuel assemblies stored in Region 2 shall be subject to the following conditions:
a. The combination of initial enrichment and cumulative exposure shall be within the acceptable domain of Figure 3.9-1, and
- b. No spent fuel assemblies shall be placed in Region 2 nor shall any storage location be changed in designation from being in Region 1 to being in Region 2, while refueling operations are in progress.
APPLICA8t'LITY: Whenever irradiated fuel assemblies are in the spent fuel pool. ACTION:
- a. With the requirements of the above specification not satisfied, suspend all other movement of fuel assemblies and crane operations with loads in the fuel storage areas and move the non-complying fuel assem011es to Region 1. Until these requirements of the above specification are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours.
\- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
$URVEILLANCE REQUIREMENTS 4.9.12 The burnup of each spent fuel assembly stored in Region 2 shall be ascertained by analysis of its burnup history and independently verified, prior to storage in Region 2. A complete record of such analysis shall be kept for i
the time period that the spent fuel assembly remains in Region 2 of tne spent i lupt pool. l e 3/4 9-15 f CALLAWAY - UNIT L ) I I J -m
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3 ,9.,, l Fo A ( f NYTIAL. SNRguthcgr, W/o u435 ) FIGURE 9;1A4*. MIfl! MUM REQUIRCO FUEL ASSEMBLY titWtts h PO40Rc AS A FUf1CT!0fl 0F Ifl!TIAL EfiRICHMEflT Pg STORAGE Ifl REGI0fl 2 T CC R H LT 1 sh A4 o vu..'o
r qEstcs n uuats CIYlS!ON J 5.1 REACTOR CORE - . FUEL AS$!wGLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4 Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1766 grams uranium. The initial core loading shall have a maximum enrichment of 3.10 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.-Ser weight percent U-235. 4,20 CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control red assemblies. The full-length control' rod assemblies shall contain a nominal 142 inches of absorber material. All control rods shall be hafnium, clad with stainless steel tuning. 5.4 REACTOR COOLANT SYSTEM DE5fGN PRES $URE ANO TEW ERATURE , 5.4.1 The Reactor Coolant System is designed and shall be maintained:
- a. In a cordance with the Code requirements specified in Section 5.2 of
) the FSAR, with allowance for normal degradation pursuant to the -
applicable Surveillance Requirements,
- b. For a pressure of 2485 psig, and
- c. For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUM( 5.4.2 The total volume of the Reactor Coolant System, including pressurizer and surge line, in 12,135 : 100 cubic feet at a nominal T,yg of $57'F. S5 METEOROLOG! cat. TOWER LOCATTON 5.5.1 The meteorological tower shall be located as shown on Figure 5.11. CALLAWAY a UNIT 1 $*6 -l ;
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m DESIGN FEATURES 1 ~ l ( 5.6 FUEL STORAGE CRll! CAL!!Y ,
- 5. 6.1.1 The spent fuel storage racks are designed and eall be maintained with:
- a. A k,ff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative al fcwar.ca of 2.6%
ak/k for uncertainties as described in Section 4."L of the FSAR. yt/.10 This is based on new fuel with an enrichment of todW%eignt percent U-235 in Region 1:and an spent fuel,with combination of initial enrichment: and. discharge exposures, shown in Figure ht-t, in Region 2, and' ' J.9-f 9.N <
- b. A nominal' 9644* inch center-to-center distance between fuel assemblies placed-~in the ,s,torage racks. .
5.6.1'.T The k,gg,foiJnew fuel i for-the first core loading stored dry in the spent fuel' storage racks shall' not* exceed 0.98 when aqueous foam moderation is
~
assumed. -
... ORAINAGE
$.6.2~ The spent-fuel' storage pool is designed and shall be maintained to prevent inadvertent draining of' the pool below elevation 2040 feet.
CAPACITY 5.G.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited.to no more than 1344 fuel assemelles.
- 5. 7 COMPCN(NT CYCt.!C OR TRANSIENT lIMIT
$. 7.1 The components identified in Tanle 5.7 1 are designed and shall be maintained within the cyclic or transient limit!. of Table 5.7 1.
I t l l CALLAWAY
- UNIT 1 17
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% FIGURE 5.6-1 MIN! MUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 CALLAWAY - UNIT 1 5-8 -
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