L-06-025, Supplemental Information Pertaining to License Amendment Request No. 302

Supplemental Information Pertaining to License Amendment Request No. 302

ML060590252
Person / Time
Site:	Beaver Valley
Issue date:	02/22/2006
From:	Lash J FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-06-025, TAC MC4645
Download: ML060590252 (4)

Text

FENOC FirstEnergy Nuclear Operating Company James H. Lash 724-682-5234 Site Vice President Fax: 724-643-8069 February 22, 2006 L-06-025 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 1 BV-1 Docket No. 50-334, License No. DPR-66 Supplemental Information Pertaining to License Amendment Request No. 302 (TAC No. MC4645)

On February 9, 2006 the NRC issued License Amendment 273 for Beaver Valley Power Station (BVPS) Unit No. 1. The License Amendment approved the Technical Specification changes proposed in FirstEnergy Nuclear Operating Company (FENOC)

License Amendment Request (LAR) 320, Replacement Steam Generators, submitted by FENOC letter L-05-069 and supplemented by FENOC letters L-05-168 and L-05-163.

The Technical Specification changes approved in License Amendment 273 wvere originally submitted as part of FENOC LAR 302, Extended Power Uprate, submitted by FENOC letter L-04-125. This letter withdraws these specific Technical Specification changes from LAR 302. Attachment A provides a complete listing of the Unit No. 1 Technical Specification changes proposed in LAR 302 and identifies those withdrawn.

This letter also documents that the remaining Unit No. 1 Technical Specification changes proposed in LAR 302 will be implemented during power operations. Letter L-04-125 states that an outage is needed to implement the Unit No. 1 changes proposed in LAR 302. However, FENOC has determined that all the remaining Unit No. 1 changes can be implemented during power operations. In all cases the existing Technical Specification requirements are either more conservative or restrictive than the changes proposed in LAR 302. As stated in FENOC letter L-05-168, the Unit No. 1 EPU amendment shall be implemented within 120 days following issuance of the amendment.

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

AC oI

Beaver Valley Power Station, Unit No. 1 Supplemental Information Pertaining to License Amendment Request No. 302 L-06-025 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on February 22 , 2006.

Sincerely,

Attachment:

A. Status of LAR 302 Unit No. 1 changes 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 A of L-06-025 Status of LAR 302 Unit No.1 changes The following table lists the changes originally proposed in License Amendment Request (LAR) 302, Extended Power Uprate (EPUJ). Those with a status of "WITHD'RAWN" have been approved by Unit No. 1 License Amendment 273 and are thus being withdrawn from LAR 302. Those with a status of "REMAINING" are requested to be approved as part of the EPU License Amendment for Unit No. 1.

No. Unit No. 1 Status Title I License page 3 REMAINING Item 2.C(l) Maximum Power Level 2 License page 3 REMAINING Item 2.C(2) Technical Specifications 3 1.0 REMAINING DEFINITIONS -1.3 RATED THERMAL POWER 4 2.1.1.1 WITHDRAWN SAFETY LIMITS - REACTOR CORE 5 3.1.2.8 REMAINING REFUELING WATER STORAGE TANK (RWST) 6 3.3.1.1 REMAINING REACTOR TRIP SYSTEM INSTRUMENTATION (Tables 3.3-1 and 4.3-1, FUNCTIONAL UNIT 4, Power Range, Neutron Flux High Negative Rate Trip) 7 3.3.1.1 WITHDRAWN REACTOR TRIP SYSTEM INSTRUMENTATION (T'able 3.3-1, FUNCTIONAL UNIT 14, Steam Generator Water Level Low-Low) 8 3.3.1.1 WITHDRAWN REACTOR TRIP SYSTEM INSTRUMENTATION (Table Notation, Overtemperature/Overpower AT) 9 3.3.1.1 REMAINING REACTOR TRIP SYSTEM INSTRUMENTATION (Table Notation, Action 8) 10 3.3.2.1 REMAINING ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Table 3.3-3, Footnote to Steamline Pressure - Low) 11 3.3.2.1 WITHDRAWN ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Table 3.3-3, FUNCTIONAL UNIT 5.a, Steam Generator Water Level High-High, and 7.a, Steam Generator Water Level Low-Low) 12 3.4.1.3 WITHDRAWN REACTOR COOLANT SYSTEM - SHUTDOWN (SR 4.4.13.3) 13 3.4.3 REMAINING REACTOR COOLANT SYSTEM - SAFETY VALVES 14 3.4.5 WITHDRAWN STEAM GENERATORS 15 3.4.8 REMAINING REACTOR COOLANT SYSTEM - SPECIFIC ACTIVITY 16 3.5.1 WITHDRAWN ACCUMULATORS 17 3.5.4.1.1 REMAINING BORON INJECTION TANK 2 3500 F

Attachment A of L-06-025 Page 2 of 2 No. Unit No. 1 Status Title 18 3.5.4.1.2 REMAINING BORON INJECTION TANK < 3500 F 3.5.2 REMAINING ECGS SUBSYSTEMS - Tavg 2 3500 F 3.5.3 REMAINING ECCS SUBSYSTEMS - Tavg < 3500 F 19 3.5.5 WITHDRAWN SEAL INJECTION FLOW 20 3.7.1.1 REMAINING TURBINE CYCLE - MAIN STEAM SAFETY VALVES (mSSVs) 21 3.7.1.3 REMAINING PRIMARY PLANT DEMINERALIZED WATER (PPDW) 22 3.7.1.4 REMAINING PLANT SYSTEMS - ACTIVITY 23 6.9.5 WITHDRAWN CORE OPERATING LIMITS REPORT (COLR)