ML20137B937
| ML20137B937 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/18/1997 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20137B934 | List: |
| References | |
| NUDOCS 9703240107 | |
| Download: ML20137B937 (2) | |
Text
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t Attachm:nt IV to ET 97-0020 1
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l ATTACHMENT IV i
PROPOSED TECHNICAL SPECIFICATION CHANGES
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Attechment IV to ET 97-0020 P ga 2 of 2 DESIGN FEATURES l
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The =re the!! cent:!r 193 fue! crremb!!:: t"h :::" fue' creemb!y norme!!y cente!r:ng 2Si fue! red: c'ed t"h Zi rr'ey 4 except *het '"!!cd j
rdedut!O. Of fee! rede by f!!: red: cen:!: ting of Z!rrr'ey i er et2!n! ::
fer' er by "?cr9e m y M mrde !!just! Sed by e cyc! rper!'c re! cad i
en-!y !. Each fue! red 05:!! heur a ~2 min ! dee fue!!ength of444 I
'nch=. The 5 t!r! core !ced5; the!! h ve m29 mum nefnc! enr!:hment of j
2.10 rer!;h! p ent U 235. ?!ced fue! ch !! be :!m!!:r % phy er! ded;n 10 p
the.!r tic! Ocre !cedhg.The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of i
Zircaloy or ZlRLO clad fuel rods with an initial composition of natural or sl!ghtly enriched uranium dioxide (UO )
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2 as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods,in l
accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC approved codes and methods and shown by test or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed represeritative testing may be placed in non-limiting core regions.
l CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length ard no part-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. All control rod assemblies shall be hafnium, silver-indium-cadmium, or a mixture of both types. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGNPRESSURE ANDTEMPERATURE 5 4.1 The Reactor Coolant System is designed and shall be maintained:
- 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,
- b. For a pressure of 2485 psig, and
- c. For a temperature of 650 F, except for the pressurizer which is 680 F.
1 VOLUME 5.4.2 The totalvolume of the Reactor Coolant System, including pressurizer and surge line, is 12,1351100 cubic feet at a nominal T of 557 F.
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5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
WOLF CREEK - UNIT 1 5-6 Amendment No. 3AGA9r48; 61 1
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