ML20062G097
| ML20062G097 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/16/1990 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20062G095 | List: |
| References | |
| NUDOCS 9011280386 | |
| Download: ML20062G097 (3) | |
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t ATTACHMENT 1 MARKED-UP TECHNICAL SPECIFICATION PAGE P3E Specification Chanae DescriDtion 5-6 5.3, " Reactor Core"- Allows ZIRLO clad fuel rods and ZIRLO filler rods to be utilized in the V(,SNS core, i
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9011280386 901116 t
DESIGN FEATURES 5.3 REACTOR CORE pt 3 g() g\\og c.htM ng , , .
FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies withnach fuel :
assembly normally containing 264 fuel rods that with Zircoloy 4 .except that. -
I i stainless steel, or rodsvacancies, by by filler rods consisting say beof made:if hircaloy-4,rerElRLDd\eh justified by l a cy reloed analysis.
Each fuel rod shall have a nominal active fuel length of 144 inches.-U-235.
percent -The initial core loading thall have a maximum enrichment of 3.2 weight Reload fuel shall be similar in physical desipt to the initial core loading and shall have a maximum enrichment of 4.25 weigit percent U-235..
CONTROL R00 A55DBLIES -
5.3.2 The reactor core shall contain 48 full length control rod assemblies. -
The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
si'ever 15 percent indium and 5 percent cadmium. ' All control rods shall -
clad wIth stainless steel tubing.
, 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AN0 TEMPERATURE 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.
applicable with allowance Surveillance fer normal degradation pursuant to the.
R** trements,
- b. For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680'F.
VOLUME '
5.4.2 9407 1 100 The total water and steam volume of the reac%r coolant system is-cubic feet at a noeinal T,yg of 586.8'F.
- 5. 5 HETEOROLOGICAL TOWER LOCATION 5 0.1 The.meteorologice) tower shall be located as shown on Figure 5.1-1.
SumER - UNIT " .
6 Ameadment No. 21. II. 92. ' 74
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' - . j ATTACHMENT 2 l
SAFETY EVALUATION FOR THE VIRGIL C.-SUW4ER NUCLEAR STATION TRANSITION TO WESTINGHOUSE VANTAGE + FUEL Description of Amendment Request:
Virgil C. Summe- Nuclear Station (VCSNS)-Technical Specification' 5.3,
" Reactor Core " currently requires Zircaloy-4 to be the material used, for '
fuel rod cladding. VCSNS Specification 5.3 also requires that any filler rods (used as substitutions for fuel rods) be composed of stainless stell or Zircaloy-4 The zirconium based alloy (Zircaloy-4) and- stainless steel are '
specified because their mechanical, chemical, and nuclear' properties ~ have been evaluated and determined to be sufficient to support the licensir.g basis for VCSNS.
With this Technical Specifications Change Request. South Carolina' Electric & ;
Gas Company (SCE&G) is proposing to revise the wording of Specificaticn ' 5.3 6 to allow utilization of an advanced material, -ZIRLO, for both claddini and filler rods. VCSNS is requesting this revision'because ZIRLO *s tte cladding material used in the Westinghouse VANTAGE + fuel- design, which ' tNS intends i
to utilize during CycD 7. Use. of VANTAGE + fue' is expected ' to allow higher fuel burnups, offer e increased resistance to cladding corrosion, and reduce V fuel cycle costs. Other unique design features of VANTAGE + fuel include I ZIRLO guide thimbles, the option to use annular axial blanket pellets, and
- modified fuel assembly dimensions.
i SCE&G intends for this revision to be . a . permanent _ ~ change in ' the ' VCSNS Technical Specifications. The change in cladding an<l filler rod material-does not affect the purpose of Specification 5.3; only the composition of the two components has been changed.. The safety evaluation?for this; proposed change shows that all current design and safety criteria;will-'be' satisfied with the~ use of VANTAGE + fuc1 assemblies in the Cycle 7 core and subsequent.
reload cores.
Safety Evaluation:
The enclosed evaluation, " Safety Evaluation for the Virgil C. Summer Nuclear Station, Upgrade to Westinghouse 17 X-17 VANTAGE + Fuel," describes.the effects-of using VANTAGE + fuel assemblies in a mixed fuel core (with VANTAGE 5 and-
' LOPAR assemblies) and an all VANTAGE + core. This -evaluation- confirms that the VANTAGE + assemblies with ZIRLO cledding material will conform to current fuel design bases and do .not change the. existing ' reload.- design and safety, analysis limits.
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