L-06-083, Supplemental Information in Support of License Amendment Request Nos. 302 and 173

Supplemental Information in Support of License Amendment Request Nos. 302 and 173

ML061360075
Person / Time
Site:	Beaver Valley
Issue date:	05/12/2006
From:	Lash J FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-06-083, TAC MC4645, TAC MC4646
Download: ML061360075 (8)

Text

FENOC FirstEnergy Nuclear Operating Cornpany James H. Lash 724-682-5234 Site Vice President Fax: 724-643-8069 May 12, 2006 L-06-083 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Supplemental Information in Support of License Amendment Request Nos. 302 and 173 (Unit No. 1 TAC No. MC4645/Unit No. 2 TAC No. MC4646)

On October 4,2004, FirstEnergy Nuclear Operating Company (FENOC) submitted License Amendment Request (LAR) Nos. 302 and 173 Extended Power Uprate (EPU) by letter L-04-125 (Reference 1). During a phone call held on April 18, 2006, the NRC staff reviewers of LAR 302/173 requested that additional information be provided regarding the Effective Full Power Year (EFPY) and fluence projections associated with the EPU for Beaver Valley Power Station (BVPS) Unit No. 1 and Unit No. 2. Attachment 1 of this submittal provides the requested information discussed during the phone call.

The supplemental information provided by this transmittal has no impact on either the proposed Technical Specification changes or the no significant hazards consideration transmitted by Reference 1.

No new regulatory commitments are contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager - FENOC Fleet Licensing, at (330) 315-7243.

I declare under penalty of perjury that the foregoing is true and correct. Executed on May I, ,2006.

Sincerely, es H. Lash

Beaver Valley Power Station, Unit Nos. 1 and 2 Supplemental Information in Support of License Amendment Request Nos. 302 and 173 (Unit No. 1 TAC No. MC4645/Unit No. 2 TAC No. MC4646)

L-06-083 Page 2 Attachments:

1. Summary of EFPY and Fluence Projections for BVPS-1 & BVPS-2

References:

1. FENOC Letter L-04-125, License Amendment Request Nos. 302 and 173, dated October 4, 2004.

c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. A. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

Attachment I of L-06-083 Summary of EFPY and Fluence Projections for BVPS-1 & BVPS-2 During a phone call held on April 18, 2006, the NRC staff reviewers of License Amendment Request (LAR) 302/173, Extended Power Uprate (EPU) requested that additional information be provided regarding the Effective Full Power Year (EFPY) and fluence projections associated with the EPU for Beaver Valley Power Station (BVPS) Unit No. 1 and Unit No. 2. The following provides the requested information discussed during the phone call.

The BVPS reactor vessel fluence and EFPY projections associated with the EPU have changed over the course of time since the EPU LAR was submitted in the 2004 timeframe.

In the EPU LAR, assumptions were made that the 1.4% measurement uncertainty uprate would occur in June of 2001 followed in June of 2003 by the 8% power uprate. The actual timing of these events changed over time, with the 1.4% measurement uncertainty occurring in June of 2001 to be followed by the 8% power uprate (now projected in 2006).

This delay in implementing the 8% power uprate coupled with improved operational capacity factors and shorter outages resulted in a change in the projected EFPY associated with the End-Of-Life (EOL) for each unit.

The BVPS-1 and BVPS-2 Reactor Vessel core design history is identified in Tables I and

2. As noted in the tables, both BVPS-1 and BVPS-2 have been operating using a Low-Low Leakage Core (L4P) configuration over the past five cycles and it is planned that these core designs will be maintained. The cycle fluences from these core designs are identified in WCAP 15571 (Capsule Y) for BVPS-1 and WCAP 16527 for BVPS-2. In the EPU LAR, the projected EOL for BVPS-2 was 32 EFPY based on the WCAP 15675. In WCAP 16527, the Capsule X report for BVPS-2 submitted in FENOC letter (L-06-050) dated April 7, 2006, the projected EOL is 36 EFPY. The increase in the projected EOL from 32 EFPY to 36 EFPY for BVPS-2 is a result of the improved operating capacity factor and shorter outage durations experienced to date.

The tables include the capacity factor history for each unit and outage durations. In general, capacity factors for the units have improved significantly over the years, and it is projected that capacity factors and outage durations similar to those experienced over the past three to four cycles will be maintained for the remaining licensed life for each unit. As a result of these changes in the anticipated performance, BVPS-1 is projected to reach nearly 30 EFPY at EOL. The fluence value noted in the EPU LAR for BVPS-1 remains conservative based upon the current projections, and the fluence value noted in the EPU LAR for BVPS-2 remains conservative for 32 EFPY.

Sensitivity studies have been performed to determine if and when fluence management measures may be required for BVPS-1 during an extended license period. These sensitivity studies were performed because the BVPS-1 reactor vessel has historically had to address the RTpTS (Reference Temperature, Pressurized Thermal Shock) value during the period near the end of licensed life. The sensitivity analysis used the core fluences identified in WCAP 15571, adjusting the cycle fluence linearly for the projected uprate conditions. This increase coupled with expected capacity factors of between 97% and 98% and an average of 22 days per outage over the remaining licensed life of BVPS-1 would project to approximately 30 EFPY and a fluence value of approximately 3.54 E19 n/cm 2 at EOL. The projections for BVPS-1 are included in Table 3.

of L-06-083 Page 2 of 6 Table 4 identifies the WCAPs associated with the capsule evaluations and the projected fluence and RTpTs for each unit. Following the issuance of the PTS Rule, BVPS-1 evaluated various fluence management approaches. In WCAP 14543, an evaluation was presented to the NRC requesting the consideration of the use of measured fluence values rather than calculated values (reducing the effective fluence by -6.8%) and reducing the effective EOL to 27.1 EFPY resulting in an EOL RTpTS value of 264.50F. In the response to that request, the NRC issued a Safety Evaluation Report (SER) on October 7, 1997, identifying that calculated fluences are to be used and that the EOL RTpTS value would be 267.80F at 28 EFPY. At the time of these evaluations, BVPS-1 operating history appeared to support an EOL value of 28 EFPY. The Capsule Y information provided in WCAP 15571 significantly improved the projected RTpts value for BVPS-1. The value projected at 28 EFPY in WCAP 15571 (2540F) is approximately 130F better than the value projected in the SER. This improvement in the projected RTpts value allows BVPS-1 to reach EOL without concerns for encroaching on the RTpts screening limit value of 2700 F.

of L-06-083 Page 3 of 6 Table 1- (BVPS-1)

History of Capacity Factors and Outage Durations BVPS-1 Capacity Date Outage Duration Core Design Operating Factor Cycles 1 36.69 1976-1979 356 High Leakage 2 65.58 1980-1981 196 High Leakage 3 85.59 1982-1983 106 High Leakage 4 88.09 1983-1984 85 Moderate Leakage 5 87.49 1985-1986 100 Moderate Leakage 6 85.66 1986-1987 81 Moderate Leakage 7 82.92 1988-1989 116 Moderate Leakage 8 85.06 1989-1991 98 Moderate Leakage 9 81.76 1991-1993 84 Moderate Leakage 10 77.40 1993-1995 64 Low Leakage (LP) w/Hf 11 92.88 1995-1996 50 Low Leakage (L3P) w/Hf 12 82.25 1996-1997 114 Low Leakage (L3P) w/Hf 13 66.14 1998-2000 52 Low Low Leakage (L4P) 14 94.24 2000-2001 38 Low Low Leakage (L4P) 15 94.25 2001-2003 53 Low Low Leakage (L4P) 16 98.27 2003-2004 28 Low Low Leakage (L4P) 17 98.63 2004-2006 65 Low Low Leakage (L4P) of L-06-083 Page 4 of 6 Table 2 - (BVPS-2)

History of Capacity Factors and Outage Durations BVPS-2 Capacity Date Outage Core Design Operating Factor Duration Cycles 1 77.40 1987-1989 71 High Leakage 2 79.96 1989-1990 79 Low Low Leakage (L4P) 3 94.49 1990-1992 59 Moderate Leakage 4 93.43 1992-1993 81 Moderate Leakage 5 94.99 1993-1995 46 Moderate Leakage 6 95.20 1995-1996 107 Low Leakage (L3P) 7 57.93 1996-1999 44 - Low Leakage (L3P) 8 91.88 1999-2000 32 Low Low Leakage (L4P) 9 95.47 2000-2002 23 Low Low Leakage (L4P) 10 97.46 2002-2003 29 Low Low Leakage (L4P) 11 97.71 2003-2005 25 Low Low Leakage (L4P) 12 2005-2006 Low Low Leakage (L4P)

1-1 of L-06-083 Page 5 of 6 Table 3 Projected Fluence Values for Future Operating Cycles (BVPS-1)

BVPS-1 Capacity Date Outage Effective Full Fluence Factor Duration Power Years E19 n/cm2 18 98 2006-2007 22 21.02 2.48 19 98 2007-2009 22 22.41 2.64 20 98 2009-2010 22 23.81 2.81 21 98 2010-2012 22 25.20 2.97 22 98 2012-2013 22 26.60 3.13 23 98 2013-2015 22 27.99 3.30 24 98 2015-2016 22 29.39 3.46 Note: These projections are based on a variety of assumptions, which include a cycle fluence profile similar to that experienced in Cycle 10 with linear increase due to power increases, maintaining a bounding fluence of 3.54 E19 n/cm 2, and no extension of the existing license period based upon the potential for crediting the first outage duration as non-operational.

S. of L-06-083 Page 6 of 6 Table 4 WCAP's Associated with Capsule Evaluations and Projected Fluence Values (BVPS-1 & 2)

BVPS-1 WCAP Capsule Date EOL Fluence (n/cm 2) RTpts 9860 V January, 1981 32 10867 U November, 1985 32 12005 W January, 1989 - 32 4.07 E19 289 14543 W August, 1996 27.1 2.82 E19 264.5 SER October 7, 1997 28 3.02 E19 267.8 15571 Y March, 2001 28 3.54 E19 259 BVPS-2 WCAP Capsule Date EOL Fluence (n/cm2 ) RTpts 12406 U February, 1990 32 6.33 E19 14484 V March, 1996 32 3.85 E19 15675 W September, 2001 32 3.85 E19 149 16527 X April, 2006 36 4.11 E19 149