ML020430480

Amendment No. 128, Technical Specification Credit for Soluble Boron in the Spent Fuel Pool

ML020430480
Person / Time
Site:	Beaver Valley
Issue date:	02/11/2002
From:	Dan Collins NRC/NRR/DLPM/LPD1
To:	Myers L FirstEnergy Nuclear Operating Co
Collins D, NRR/DLPM, 415-1427
Shared Package
ML020440176	List: ML020020373 ML020430480
References
Download: ML020430480 (6)

Text

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION 3/4.9.12 3/4.9.14 3/4.9.15 PAGE FUEL BUILDING VENTILATION SYSTEM FUEL MOVEMENT................................

SPENT FUEL POOL STORAGE......................

FUEL STORAGE POOL BORON CONCENTRATION........

3/4 3/4 3/4 9-13 9-15 9-17 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..............................

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS..........................

3/4.10.3 PHYSICS TESTS................................

3/4.10.4 REACTOR COOLANT LOOPS........................

3/4 10-1 3/4 3/4 3/4 10-2 10-3 10-4 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.4 Liquid Holdup Tanks..........................

3/4.11.2 GASEOUS EFFLUENTS 3/4.11,2.5 Gaseous Waste Storage Tanks..................

3/4.11.2.6 Explosive Gas Mixture........................

3/4 11-2 3/4 3/4 11-4 11-5 BASES SECTION PAGE 3/4.0 APPLICABILITY......................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL.............................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS.............................

B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES...................

B 3/4 1-4 BEAVER VALLEY -

UNIT 2 IX Amendment No.

128

3/4.9.14 SPENT FUEL POOL STORAGE LIMITING CONDITION FOR OPERATION 3.9.14 The combination of initial enrichment and burnup of each fuel assembly stored in the spent fuel storage pool shall comply with the limits specified in Table 3.9-1.

APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel storage pool.

ACTION:

With the above requirements not satisfied:

a.

Immediately initiate action to move the non-complying fuel assembly to a location that complies with Table 3.9-1.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.14 Verify, by administrative means, the initial enrichment and burnup complies with Table 3.9-1 prior to storing a fuel assembly in the spent fuel storage pool.

Amendment No. 128 BEAVER VALLEY -

UNIT 2 3/4 9-15

Table 3.9-1 FUEL ASSEMBLY MINIMUM BURNUP VS.

U-235 NOMINAL ENRICHMENT FOR STORAGE IN SPENT FUEL RACK REGIONS 1,2,3 Nominal Enrichment (w/o U-235) 1.9 2.0 2.2 2.4 2.6 2.8 3.0 3.2 3.4 3.6 3.8 4.0 4.2 4.4 4.6 4.8 5.0 Region 3 4-out-of-4 Burnup (MWD/MTU) 0 1615 4629 7295 9677 11877 13995 16112 18235 20349 22443 24503 26519 28492 30428 32329 34201 Region 2 3-out-of-4 Checkerboard Burnup (MWD/MTU) 0 0

0 0

0 1798 3556 5268 6940 8581 10198 11800 13394 14979 16552 18110 19650 Region 1 J

J ___________

.1 Note 1:

Linear interpolation yields conservative results.

Amendment No. 128 BEAVER VALLEY -

UNIT 2 Region 1 2-out-of-4 Checkerboard Burnup (MWD/MTU) 0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 3/4 9-16

3/4.9.15 FUEL STORAGE POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.15 The fuel storage pool boron concentration shall be greater than or equal to 2000 ppm.

APPLICABILITY:

When fuel assemblies are stored in the fuel storage pool.

ACTION:

With fuel storage pool boron concentration not within

limits,

a.

Immediately suspend all operations involving the movement of fuel assemblies in the fuel storage pool and initiate action to restore the fuel storage pool boron concentration to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.15 Verify the fuel storage pool boron concentration is within the limit at least once per 7 days.

Amendment No.

128 BEAVER VALLEY -

UNIT 2 3/4 9-17

NPF-73 5.0 DESIGN FEATURES 5.1 SITE LOCATION The Beaver Valley Power Station Unit No.

2 is located in Shippingport

Borough, Beaver County, Pennsylvania, on the south bank of the Ohio River.

The site is approximately 1 mile southeast of Midland, Pennsylvania, 5 miles east of East Liverpool, Ohio, and approximately 25 miles northwest of Pittsburgh, Pennsylvania.

The exclusion area boundary has a minimum radius of 2000 feet around the Unit No.

1 containment building.

5.2 REACTOR CORE 5.2.1 FUEL ASSEMBLIES The reactor shall contain 157 fuel assemblies.

Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2 ) as fuel material.

Limited substitutions of zirconium alloy or stainless steel filler rods for fuel

rods, in 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 staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases.

A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

5.2.2 CONTROL ROD ASSEMBLIES The reactor core shall contain 48 full length and no part 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 cadmium.

All control rods shall be clad with stainless steel tubing.

5.3 FUEL STORAGE 5.3.1 CRITICALITY 5.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Keff

< 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in UFSAR Section 9.1;

b.

Fuel assemblies having a maximum U-235 enrichment as set forth in Specification 3.9.14; BEAVER VALLEY - UNIT 2 5-1 Amendment No.

1 2 8

NPF-73 5.0 DESIGN FEATURES C.

Keff

• 0.95 if fully flooded with water borated to 450 ppm, which includes an allowance for uncertainties as described in UFSAR Section 9.1;

d.

A minimum center to center distance between fuel assemblies placed in the fuel storage racks of 10.4375 inches;

e.

Fuel assembly storage shall comply with the requirements of Specification 3.9.14.

5.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.85 weight percent;

b.

Keff

• 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in UFSAR Section 9.1;

c.

Keff

• 0.95 if moderated by aqueous foam, which includes an allowance for uncertainties as described in UFSAR Section 9.1;

d.

A nominal 21 inch center to center distance between fuel.

assemblies placed in the storage racks.

5.3.2 DRAINAGE The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 751'-3".

5.3.3 CAPACITY The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1088 fuel assemblies.

Amendment No.

128 BEAVER VALLEY -

UNIT 2 5-2