ML20042D750

Proposed Tech Specs Re Use of Solid Stainless Steel or Solid Zircaloy-4 Filler Rods in Place of Fuel Rods

ML20042D750
Person / Time
Site:	North Anna
Issue date:	03/29/1990
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20042D749	List: ML20042D748 ML20042D750
References
NUDOCS 9004050312
Download: ML20042D750 (7)

Text

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES FOR NORTH ANNA UNITS 1 AND 2.

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Remove i<om the previous submittal (Serial No. 773, dated 1/16/90) pages 5-4 for Unit 1 and 2 Technical Specifications and insert the attached.

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y,'004050312900329 n-p,DR ADOCK 05 coo 33g PDC

DESGN FEATURF) ,

DESIGN PRFMURE AND TEMPERATURE 5.2.2 The reactor cor.L.;nment building is designed and shall be maintained for a mar'aum internal pressure of 45 psig and a temperature of 280*F.

53 REACTOR CORE FUEL ASSEMBUES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly nominally containing 264 fuel rods clad with Zircaloy 4, except that substitutions of Zircaloy 4 or stainless steel filler rods or open water channels for fuel rods may be made in fuel assemblies if justified by the cycle specific rotoad analysis using an NRC approved methodology. Should more than 30 rods in the core, or 10 rods in any assembly, be replaced per refueling, a special report describireg the rumber of rods replaced shall be submitted to the Commission pursuant to Specification 6.9.2 within 30 days of the cycle startup. Each fuel rod shall have a nominal active fuel length of 144 inches. The initlat core loading shall have a maximum enrichment of 3.2 weight percent U 235. Reload fuel shall be similar in physical design to the inillal core loading and shall have a maximum enrichment of 4.1 weight percent U 235.

CONTROL ROD ASSEMBLIES 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. The nominal values of absorber material shali be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTORCOOLANTSYSTEM DESIGN PRESSURE ANDTEMPERATURE ,

5.4.1 The reactor coolant system is designed and shall be maintained:

i NORTH ANNA - UNIT 1 54 ,

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I DF. SIGN FEATURES 53 REACTORCORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly nominally containing 264 fuel rods clad with Zircatoy 4, except that substitutions of Zircaloy 4 filler rods or open water channels for fuel rods may De made in fuel assemblies if justified by the cycle specific reload analysis using an NRC approved methodology. Should more than 30 rods -

the core, or 10 rods in any assembly, be replaced per refueling, a speclat report describing the number of rods replaced shall be submitted to the Cormission pursuant to Specificallon 6.9.2 within 30 days of the cycle startup. Each fuel rod shall have a nominal active fuel length of 144 inches. The Initial core loading shall have a maximum enrichment of 3.2 weight percent U-235. Reload fuel shsill be similar in physical design to the Inlllal core loading and shall have a maximum enrichment of 4.1 weight percent U 235.

CONTROLROD ASSENEL!ES 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. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmlum. All control rods shall be clad with stainless steel tubing.

5.4 REACTORCOOLANTSYSTEM DESIGN PRESSURE 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.

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b. For a pressure of 2485 psig, and j

c. For a temperature of 650'F, except for the pressurizer which is 680'F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9957 i 10 cubic feet i at a nominal Tavg of 525'F.

NORTH ANNA - UNIT 2 54 i h

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ATTACHMENT 2 MARKUP OF THE NORTH ANNA MERITS TECHNICAL SPECIFICATIONS l

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DESIM FEATURES t 4.0 4.0 DESIGN FEATURES (continued) 4.3 REACTOR CORE 4.3.1 Fuel Assemblies Amai@*

The reactor core shall contain 157 fuel assemblies each with fuel

1. 1. 1. 1. m # Tue' assimb1mcontaining 264 ct fuel rods clad with Each Zircaloy 1 _ro5 s.. hall hav,_e a . nominal a,p.ive fuel length

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. ___ . . _ .. a g g _ _ _ _ _ . . . . _ , . .- es of initialcore'loadingshali~haveamaximumenrichmentof3.1The weight percent U-235. .

- design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent' U-235.

4.3.2 Control Red Assemblian k

The reactor core shall contain 48 full length control rod assemblies.

The full length control rod assemblies shall contain a nominal 142 inches of a6sorber material.

absorber material shall be 80 percent silverThe15nominal percentvalues indium of and 5 percent stainless cadmium. Allcontrolrodsshallbecladwith steel tubing.  !

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North Anna Units 1 & 2 45 Amendment Nos. xxx & yyy I

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ATTACHMENT 3 10 CFR 50,92 SIGNIFICANT HAZARDS DETERMINATION J

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a Significant Hazards Determination The proposed change to revise the previously submitte.d licensing amendments (Letter dated 1/16/90) to be consisten', with Generic Lette.' 90 02 does not result in a significant hazards consideration per 10 CFR 50.92.

1. The proposed change does not significantly increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluatedin the safety analysis report, in fact, the proposed change will have no impact on the probability of occurrence or the consequences of an accident or malfunction of equipment. The only additional requirement is to require a special report be submitted to the NRC describing the number of rods replaced if more than 30 rods in the core, or 10 rods in any assembly are replaced per refueling, along with editorial changes.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated. No physical changes or modifications are being made to the plant or its equipment. As noted above, the only changes are editorial in nature and to require a special report be submitted to the NRC describing the number of rods replaced if more than 30 rods in the core, or 10 rods in any assembly are replaced per refueling.

3. The proposed amendment does not involve a significant reduction in a margin of safety. No physical changes or modifications are being made to the plant or Its equipment. No changes are being made to the cycle specific reload I

analysis. As previously stated, the only changes are editorial and to require a special report be submitted to the NRC describing the number of rods replaced if more than 30 rods in the core, or 10 rods in any assembly are replaced per refueling, i

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