ML070240605

Technical Specifications, Amendment No. 228 for Use of Metamic Poison Insert Assemblies in the Spent Fuel Pool

ML070240605
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/26/2007
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Saba F, NRR/DORL/LPL4, 301-415-1447
Shared Package
ML070160040	List: ML070160038 ML070240605
References
TAC MD2674
Download: ML070240605 (10)

Text

(4) E0I, pursuant to the Act and 10 CFR Parts 30,.40 and 70, to receive, possess and use at any time any byprbduct; source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) EQI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as reqUired any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis byproduct, source orspecial nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6) E0I, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special. nuclear materials as may be produced by the opieration of the facility.

c. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:,

(1), Maximum Power Level-EOI is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A,as revised through Amendment No. 228, are hereby incorporated in the renewed license. E0I shall operate the facility in accordance with the-Technical Specifications.

(3) Safet Analysis Repor The licensee's SAR supplement submitted pursuant to 10 CFR 54.21 (d),

as revised on March 14, 2001, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than May 20, 2014.

(4) Physical Protection E0I shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, Renewed License No. DPR-51 Rlev*sed by letter dated October 20, 2004 Revised by letter dated November 22, 2004 Amendment No. 2 2 8

Spent Fuel Pool Boron Concentration 317.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Boron Concentration LCO 3.7.14 The spent fuel pool boron concentration shall be >2000 ppm.

APPLICABILITY: When fuel assemblies are stored in the spent fuel pool.

ACTIONS-,

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool boron -- ----------------- NOTE---------

concentra~tion lim it. not within LCO

.. . 3.0.3

. .. .is..not

... applicable.

A.1 Suspend.movement of fuel Immediately assemblies in the spent fuel pool.

AND A.2 Initiate action to restore Immediately spent fuelpool boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the spent fuel pool boron concentration is 7 days

> 2000 ppm. I ANO-1 3.7.14-1 Amendment No. 2-1-6, 2 2 8

Spent Fuel Pool Storage 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Pool Storage LCO 3.7.15 Fuel assemblies shall be stored in the spent fuel pool within the acceptable limits of Table 3.7.15-1 or in accordance with Specification 4.3.1.1. I APPLICABILITY: Whenever any fuel assembly is stored in the spent fuel pool. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 -- NOTE not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately non-complying fuel assembly to an acceptable storage location in accordance with Table 3.7.15-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify by administrative means the parameters Prior to storing the associated with the fuel assembly are in accordance fuel assembly in the with Table. 3.7.15-1 or Specification 4.3,1.1. spent fuel pool.

SR 3.7.15.2 Verify Metamic properties are in accordance with, In accordance with and are maintained within the limits of, the Metamic the Metamic Coupon Coupon Sampling Program. Sampling Program.

ANO-1 3.7.15-1 Amendment No. 245, 2 2 8

Spent Fuel Pool Storage 3.7.15 Table 3.7.15-1 Loading Restrictions for Spent Fuel Storage Racks Regi0n 1- Minimum Burnup Requirements at Varying Initial U-2351Enrichment and CoolIng Time (Notes I & 2)

Enrichment 2.0 2.5 3.0 3.5 4.0 4.5 5.0 Cooling Time Minimum Burnup (GWD/MTU) 0 2.3 9,2 15.5 22.1 27.7 33.0 39.0 5 2.2 8.7 14.8 21.1 26.7 31.1 37.1 10 2.1 8.3 14.0 20.0 25.6 29.8 35.3 15 2.0 8.1 13.6 19.4 25.3 29.1 34.0 20 2.0 8.0 13.5 19.0 24.6 28.6 33.3 Region 2- Minimum Burnup Requirements at Varying Initial U-235 Enrichment and Cooling Time (Ntes 1 & 2)

Enrichment 2.0 2.5 3.0 3.5 4.0 4.5 5.0 CooQling TimeMini'mum BumUp (GWD/MTU) 0 4.5 11.7 18.7Q 2567 30.6 36.9, 42.8 5 4.2 11. 17.6 24.2 29.1 34.4 40.7 10 4.0 10.6 16.7 23.0 28.1 33.0 38.6 15 4.0 10.1 15.9 22.4 27.4 31.8 37.4 20 4.0 9.8 15.7 21.8 26.8 31.2 36.4 Region 3 Loading Restrictions Unrestricted storage Is allowed for fuel assemblies with an initial U-235 enrichment less than or equal to 4,35 wt%.

For fuel assemblies with an Initial U-235 enrichment greater than 4.35 wt%, the burnup of at least one fuel assembly in each 2 x 2 section of storage cells is at least 20.1 GWD/MTU.

Note 1: Linear interpolation between burnups for a given cooling time is allowed. However, Slinear interpolation between cooling times is not allowed, therefore the cooling time of a given assembly must be rounded down to the nearest cooling time.

Note 2:When it is necessary to store fuel assemblies in Region. I or Region 2 that do not meet.the bumup versus U-235 enrichment restrictions, fuel assemblies, including fresh orjIrradiated fuel assemblies with a maximum U-235 enrichment of 4.95 wt%, may be-stored In a 2 x 2 checkerboard (i.e., 2 assemblies and 2 empty cells) arrangement.

ANO-1 3.7.15-2 Amendment No. 246, 2 2 8

Spent Fuel Pool Storage 3.7.15 Table 3.7.15-1 (continued)

Loading Restrictions for the Spent Fuel Storage Racks Rack Interface Requirements Inaddition to the above requiremehts for each individual rack, the following requirements must be met oh the interfaces between and Within racks:

a. In the Region 1 and Region 2 racks, a fresh fuel checkerboard and uniform spent fuel loading may be placed in the same rack.

b. In Region 1 and Region 2 racks, if adjacent racks contain a checkerboard of fresh fuel assemblies, the checkerboard must be maintained across the gap, i.e., fresh fuel assemblies may not face each other across a gap.,

c. in Regioi 3, niform loading of fresh fuel With a maximum U-235 enrichment of 4.35wt% may be combified With 3 of 4tloadingi*n the safme rack loas 0ng a ow of fiesh and spent fuel in the 3 o 4 Iladig paipttern faces the Uniform loading of all fresh fuel with a maximum U-235 enrichment Of 4.35 wt%.

d. If adjacent Region 3 racks contain diffeirent loading patterns (one rack contains all fresh fuel with a maximUm U-235 enrichment of 4.35 wt% and the other rack contains a 3 of 4 loading pittern)., both fdesh "andspent fuel must be in the outer row of the rack containing the 3 of 4 pattern.

e. Ifadjacent Region 3 racks both contain 3 of 4 loading patterns, both racks may not have fresh fuel, facingd the other rack. Aloading pattern with both Region 3 racks containing 3 of 4 patterns with all friesh fuel in the outer row of one rack and fresh and spent fuel in the outer row of the second rack is allowed.

f. All interfaces between dissimilar racks (Region 1-Region 3 and Region 2-Region 3) are permitted.

ANO-1 3.7.15-3 Amendment No. 228 I

Fuel Storage 4.3 4.0 DESIGN FEATURES 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 4.95 weight percent;

b. kw.g 0.95 if fully flooded with 444 ppm of borated water, which includes an allowance for uncertainties as described in Section 9.6.2.4.3 of the SAR;

c. ke, < 1.0 if fully flooded with unborated water, which includes an aliowancefor uncertainties as described in Section 9.6.2.4.3 of the SAR;

d. A nominal 10.65 inch center to center distance between fuel assemblies placed in the storage racks;

e. New or partialy spent fuel assemblies stored in accordance withTable 3.7.15-1 in the spent fuel storage racks;

f. New or partially spent fuel assemblies with cooling times, U-235 enrichment or discharge burnup in the unacceptable range of Table 3.7'.151 for fuel'assemblies stored in Region t or Region 2 may be stored in a 2 x 2 checkerboa-rdconfiguratioh ,(iLe., 2 assemblies and 2 empt cells); and

g. Neutron absorber (Metamic) installed between fuel assemblies in the Region 3 racks.

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

a. Fuel assemblies having a maximum U-235 enrichment of 4.95 weight percent; I

b. kff - 0.95 under normal conditions, which includes an allowance for uncertainties as described in Section 9.6.2.4.3 of the SAR;

c. ke,

• 0.98 with optimum moderation, which includes an allowance for uncertainties as described in Section 9.6.2.4.3 of the SAR;

d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks; and

e. Fuel assembly loading prohibited in interior storage cells as shown in Figures 4.3.1.2-1 and 4.3.1.2-2, based on U-235 fuel enrichment.

ANO-1 4.0-3 Amendment No. 24-, 2 2 8

Design Features 4.0 Figure 4.3.1.2-1 Fresh Fuel Storage Rack Loading Pattern for a Maximum Enrichmient of 4.95 wt% U-235 I NO NO NO NO NO NO NO NO NO NO "NO" Indicates a location in which fuel loading is prohibited.

ANO-1 4.0-5 Amendment No. 245, 228

Design Features 4.0 Figure 4.3.1.2-2 Fresh Fuel Storage Rack Loading Pattern for a, Maximum Enrichment of 4.2 wt% U-235 AORH NO NO NO NO NO NO NO NO "NO" Indicates a location in which fuel loading is prohibited.

ANO-1 4.0-6 Amendment No. 2 2 8 1

Programs and Manuals 5.5 5.0 ADMINSTIRATIVE CONTROLS 5.55 Programs and Manuals 5.5.16 Reactor Buildingq Leakaaqe Rate Testing. Program A program shall be established to implement the leakage rate testing of the reactor building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance With the guidelines contained in Regulatory Guide 1.163, "Perf formance-Based Containment Leak-Test Program," dated September 1995, except that the next Type A test performed after the April 16, 1992 Type A test shall be performed no later than April 15, 2007.

in addition, the reactor building purge supply and exhaust isolation valves shall be leakageirate tested once prior to entering MODE 4 from MODE 5 if hot performed withinh the previous 92 days.

The peak calculated reactor building internal pressure for the design basis loss of coolant a'ccident Pa, is 54 psig.

The maximum allowable reactor building leakage rate, L., shall be 0.20% of containmenhtair weight per day at Pa.

Reactor Building leakage rate acceptance criteria is _*1.OLa. During the first unit startup following each test performed in accordance with this program, the leakage r:qate aceptance criteria are < 0.60La for the Type B and Type C tests and< 0.75La for Type A tests.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Reactor Building Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Reactor Building Leakage Rate Testing Program.

ANO-1 5.0-25 Amendment No. 2-1-6,2-1-9, 22 8

Programs and Manuals 5.5 5.0 ADMINSTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.17 Mdtamic Coupon Samping Program A coupon surveillance program will be implemented to maintain surveillance of the Metamic absorber material under the radiation, chemical, and thermal environment of the SFP. The purpose of the program is to establish the following:

• Coupons will be-examined on a two year basis for the first three intervals with the first coupon retrieved for inspection being on or before February 2009 and thereafter at increasing intervals over the service life of the inserts.

0 Measurements to be performed at each inspection will be as follows:

A) Physical Observations of the surface appearance to detect pitting, swelling or other degradation, B) Length, Width, and thickness measurements to monitor for bulging and-swelling C) Weight and density to monitor for material loss, and D) NeUtron attenuation to confirm the B-1 0 concentration or destructive chemical testing to dietrm-inte the boron content.

• The provisions of SR 3.0.2 are applicable to the Metamic Coupon Sampling Program.

• The provisions of SR 3.0.3 are not applicable to the Metamic Coupon Sampling Program.

ANO-1 5.0-25a Amendment No. 228 1