ML14210A239

Correction Letter Regarding Amendment Nos. 275 and 156 Issuance of Amendment Regarding the 8-Percent Extended Power Uprate

ML14210A239
Person / Time
Site:	Beaver Valley
Issue date:	07/31/2014
From:	Jeffrey Whited Plant Licensing Branch 1
To:	Emily Larson FirstEnergy Nuclear Operating Co
Whited J
References
TAC MC4645, TAC MC4646
Download: ML14210A239 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 31, 2014 Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2- CORRECTION LETTER REGARDING AMENDMENT NOS. 275 AND 156 REGARDING ISSUANCE OF AMENDMENT FOR THE 8-PERCENT EXTENDED POWER UPRATE (TAC NOS. MC4645 AND MC4646)

Dear Mr. Larson:

By letter dated July 19, 2006, 1 the Nuclear Regulatory Commission (NRC) issued Amendment No. 275 to Facility Operating License No. DPR-66 for the Beaver Valley Power Station, Unit No. 1 (BVPS-1) and Amendment No. 156 to Facility Operating License No. NPF-73 for the Beaver Valley Power Station, Unit No.2 (BVPS-2) in response to your application dated October 4, 2004. 2 Amendment Nos. 275 and 156 consisted of changes to the Technical Specifications and Facility Operating License, authorizing an approximate 8-percent increase in the licensed rated thermal power from 2,689 megawatts thermal (MWt) to 2,900 MWt.

Amendment No. 275 was effective as of July 19, 2006, and was to be implemented prior to startup following the fall 2007 refueling outage. Amendment No. 156 was effective as of July 19, 2006, and was to be implemented prior to startup following the spring 2008 refueling outage.

During a conversation between Mr. Phil Lashley, of your staff, and the NRC staff, it was noted that Table 4, "Parameters and Assumptions Used in Radiological Consequence Calculations Fuel Handling Accident for BVPS-1 and 2," on page 172 of the NRC staff's Safety Evaluation (SE) dated July 19, 2006, 3 contained errors. Specifically, the values of Iodine 131 (1-131) and Krypton 85 (Kr-85) Core fractions released from damaged rods listed in the table are incorrect.

In the NRC staff's SE the values are listed as 0.12 for 1-131 and 0.14 for Kr-85. This was an inadvertent typographical error. The values that were submitted in the application and the values that should be in Table 4 of theSE are 0.08 for 1-131 and 0.10 for Kr-85. To correct this error, a revised copy of page 172 is enclosed. Please replace the page 172 that was issued by letter dated July 19, 2006, with the enclosed page.

1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML061720274.

2 ADAMS Accession No. ML042920300.

3 ADAMS Accession No. ML061720376.

E. Larson If you have any questions, please contact me at 301-415-4090.

Sincerely,

~~Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosure:

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- 172-Control room 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.01 E-4 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.58E-4

• Note: The partition coefficient of 1.0 is applied only to the flashed portion of the break flow, A partition coefficient of 100 is applied to the unflashed portion of the break flow.

Table 4 Parameters and Assumptions Used in Radiological Consequence Calculations Fuel Handling Accident For BVPS-1 and 2 Parameter Power level, MWt 2918 Peaking factor 1.75 Number of fuel rods in fuel assemblies 264 Total number of fuel assemblies 157 Number of fuel rods damaged 137 Reactor shutdown time before fuel movement, hr 100 Core fractions released from damaged rods 1-131 0.08 Other halogens 0.05 Kr-85 0.10 Other noble gases 0.05 Alkali metals 0.12 Iodine effective pool decontamination factor 200 Duration of release Instantaneous Atmospheric dispersion values (sec/m 3)

Exclusion area boundary 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.25E-3 (BVPS-1 )/1.04E-3 (BVPS-2)

Low population zone 0 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6.04E-5 Control room BVPS-1 BVPS-2 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4.75E-3 9.39E-4 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.66E-3 6.69E-4

E. Larson If you have any questions, please contact me at 301-415-4090.

Sincerely,

/RA/

Jeffrey A. Whited, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosure:

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PUBLIC LPLI-2 R/F RidsRgn1 MaiiCenter Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDoriDpr Resource RidsNrrDorllp11-2 Resource RidsNrrPMBeaverValley Resource RidsNrrLAABaxter Resource RidsNrrDraArcb Resource JParillo, NRR ADAMS Accession Number: ML14210A239 *via e-mail OFFICE LPLI-2/PM LPLI-2/LA ARCB/BC LPLI-2/BC (A) LPLI-2/PM UShoop BSchaaf NAME JWhited ABaxter JWhited (JDozier for)* (REnnis for)

DATE 07/30/14 07/30/14 07/28/14 07/30/14 07/31/14 OFFICIAL RECORD COPY