ML19352A150

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Proposed Tech Spec Change for Tech Specs 5.3,5.4,5.5 & 5.6 Re Reactor Core,Reactor Coolant Sys & Fuel Storage
ML19352A150
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 03/06/1981
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19352A149 List:
References
NUDOCS 8103110533
Download: ML19352A150 (6)
v • d • e


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O ATTACHME T 1 PROPMED TECHNICAL SPECIFICATION CHANGE NORTH ANNA UNITS 1 AND 2 l

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DESIGN FEATURES _ _ , ,

DESIGN PRESSURE AND TEMPERATURE

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5.2.2 The reactor containment building is designed and shall be main-tained for a maximum internal pressure of 45 psig and a temcerature of 280*F.

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, 5.3 REACTOR CORE l

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, FUEL ASSEMBLIES

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5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel l assemoly containing 254 fuel rods clad with Zircaloy -4 Each fuel red shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 1780 grams uranium. The initial core leading t

shall have a maximum enrichment of 3.2 weight percent U-235. Relcad fuel shall be similar in physical design to the initial core loading and l shall have a maximum enrichment of Jet weight percent U-235.

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! 4.1 CONTROL ROD ASSEMPLIES 5.3.2 The reactor core shall contain 48 full length centrol rod assemblies. The full length control rod asser.blies shall contain a nominal 142 inches of absorttr material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods shall be clad witn stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM I

', DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant systam is designed and shall be maintained:

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l j . .10RTs ANNA - UNIT 1 5-4 'r:-2 : t "-  !!

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p DESIGN FEATURES

a. In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for nor=al degradation pur-suant 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.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant syste= is 9957 + 10 cubic fett at a nominal T,yg of 525'F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks containing new and/or spent fuel are designed and shall be maintained with a nominal 14 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks to ensure a k equivalent of < 0.95 with the storage pool filled with unborated watI The k cf <~0.95 includes a conservative allowance of ibiME Ak/k for uncertIf$ ties"' l 3.47.

The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that, on a best estimate basis, k will not exceed .03 with fuel of the h'ighest anticipated enrichsent T$ place assuming eptimum'rederatien.*

If fresh fuel is stored dry for a core loading in the spent fuel racks, a center-to-center distance between new fuel assemblies will be admini-stratively limited to 28 inches. On a best estimats oasis, k f will not exceed .98 with fuel of the highest anticipated enrichmen! In place assuming optimum moderation.*

  • E.G., an aqueous foam envelopment as the result of fire fighting.

NORTH ANNA - UNIT 1 5-5 Alu t "1 3

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" :: 30 DESIGN FEATURES l

5.3 REACTOR CORE i

FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with ee-h fuel assembly containing 264 fuel rods clad with Zircaloy -4. Each fuel rod l shall have a nominal active fuel length of 144 inches and contain a I

maximum total weight of 1780 grams uranium. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of.3e6 weight percent U-235.

l db l CONTROL R00 ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length control rod assemblies.

l 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 cadmium. All control l rods shall be clad with stainless steel tubing.

5. 4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND 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, 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, axcept for the pressurizer which is 680*F.

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

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0 21-00 DESIGN FEATURES -

i 5.5 METEOROLOGICAL TOWER LOCATICN 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 rUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained l with:

a. A X,ff equivalent to less than or equal to 0.95 when ficoded with unborated water, which includes a conservative allowance of +-M-delta k/k for uncertainties. 3.Y*

b.

A nominal 14 inch center-to center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The new fuel pit storage racks are designed and shnii be maintained witn a nominal 21 inch center-to-center distance between new fuel assemolies such that, on a best estimate besis, k,ff will not exceed .98, with fuel of the highest anticipated enrichment in place, when aqueous foam moderation is assumed.

5. 6.1. 3 If new fuel for the first core loading is stcred dry in the spent fuel storage racks the center-to-center distance between the new fuel assemblies will be administratively aqueous limitad foam moderation to 28 inches and the k'II shall not exceed 0.98 when is assumed.

ORAINAGE 5.6.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 288.83 feet Mean Sea level, USGS datum.

i CAPACITY t

' 5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 066 fuel assemblies.

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NORTH ANNA FUEL REQUIREMENTS TOTAL ANNUAL 3 ,,

Discharge Required Reloadl

,, (Burnup)- Enrich. Batch No of Feed Feed SWU- Feed Feed SUU (MWD /HTU) (w/o) Size Assem. (MTU) (MTU30g) (kgx103) (MTU) (MTU30 a) (kgx1G 3)

.33000- 3.40 71' 1420 4110 4860 3390 137 162 113 36000 3.60 65 1300 3990 4710 3360 133 157 112 39000 3.80 60 1200 3900 4620 3360 130 154 112 42000 4.00 56 1120- 3840 d

4530 3360 128 151 112 g 5

45000 4.20 52 1040 3750 4440 3330 125 148 111 h

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1. The reload batch sizes and enrichments are for equilibrium 18 month reload cycles.
2. This tofal la for the number of 18 month reload cycles remaining in the 40 year licensed lifetime for North Anna Unit 1 or 2-(i.e. 30 years).

3.- These annual feed .and SWU requirements are conservative (i.e. , higher) than the pre?iminary results f rom studies of the effect of high burnup on annual fuel requirements.

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