ML032650709

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Part 21 Report for Seabrook Re Apparent Abnormality of Boral Coupon That Was Removed from Spent Fuel Pool for Inspection
ML032650709
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 09/15/2003
From: Peschel J
Florida Power & Light Energy Seabrook
To:
Office of Nuclear Reactor Regulation
References
Download: ML032650709 (2)


Text

I-IUo JK91512003 US. NuclearRegualmy Commission OperationsCenterEventReport PageI Power Reactor Event# 40159 Site: SEABROOK Notification Date I Time: 0911512003 16:40 (EDT)

Unit: I Region: I State: NH Event Date I Time: 09115/2003 (EDT)

Reactor Type: 11 W-4-LP Last Modification: 0/15/2003 Containment Type: DRY AMB NRC Notified by: JAMES PESCHEL Notifications: CORNELIUS HOLDEN NRR HQ Ops Officer: RICH LAURA HAROLD GRAY RI Emergency Class: NON EMERGENCY 10 CFR Section:

21.21 UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit Init Power Initial RX Mode Curr Power Current RX Mode I N Yes 100 Power Operation 100 Power Operation PART 21 ISSUE AT SEABROOK ON SPENT FUEL POOL TEST COUPONS The licensee reported an apparent abnormality involving Boral spent fuel pool test coupons. Westinghouse built the spent fuel pool racks using Boral material manufactured by ARR Inc. Specifically, Inspection of test coupons revealed bulging or blistering of the aluminum cladding. The information provided by the licensee does not include any other affected plants.

L .' (C-1

-i5-20W 17:04 NESCO LICENSING 603 73 7740 P.02-02 Licensee FPLE Seabrook Site Seabrook Station Docket 50-443 y (Ig Reactor Type Westinghouse PWR Date September 15.2003 IOCFR 21 Notification FPLE Seabrook has identified an apparent abnormality of a BoraI coupon that was removed fom ithe Spent Fuel Pool for inspection. Bora] test coupons (Boron carbide &

Aluminum Composite Material) have been located in the Spent Fuel Pool as monitoing specimens to assess the pefmance of similar Boral neutron poison material incorporated into the spent fhel pool racks. Westinghouse Electric Corporation built the spent fuel pool racks using Boral matrial mufactured by ARR Inc. of Livornia, ML Visual inspection of one Boral Coupon indicated bulging of the Boral aluminum cladding that nomally encapsulates, and is adhered to, the internal Boron carbide & Aluminum Composite laYer. The structural integrity of the clad material has been affected but there as been no evidence of loss or redistribution of the boron carbide in the active poison layer of the Boral Material at this time. A number of bulges were observed on the periphery of the coupon. The inspection yielded no apparent loss of neutron absorbing material. Two additional coupons were inspected. The inspection of these coupons resulted in similar bulges being observed.

All sixteen irradiated Boral coupons were inspected and characterized after all coupons had been removed from their stainless steel jackets. These inspections indicated a range in coupon condition from blisters approximately equivalent to those previously inspected too slightly blistered and one coupon with no outward indication of blisters.

The boron-10 areal density in the Boral has been measured via neutron attenuation testing. This testing determined that areal density was within specification and no loss of control material existed. Furthermore, the impact of the blistering on the flux trap has been determine to be small and within bounds of the criticality analysis. Thus, the Boral is presently performing its design function.

However. the rate of blister formation and the long-tem effect of these blisters on the criticality analysis is not known.- Analysis performed to date suggest that this blistering will continue. Thus over a period of time, this condition could worsen which may result in operation of the spent fuel pool outside the bounds of the criticality analysis. PPLE Seabrook considers the above condition to be reportable pursuant to 10 CFR 21.21.

Because of the uncertainty in the fture state of the Boral, Seabrook is planning to implement a Boral Monitoring program and to add a blistering allowance in the Spent Fuel Pool criticality curves.

The six Boral racks constitute 576 of the 1236 storage cells in spent fuel pool. AUl the spent fel storage racks are freestanding self-supporting modules.

TOTAL P.02