ML070390530

BVPS Operating License

ML070390530
Person / Time
Site:	Beaver Valley
Issue date:	02/21/2007
From:	Boska J NRC/NRR/ADRO/DORL/LPLA
To:	Lash J FirstEnergy Nuclear Operating Co
Morgan N, NRR/DORL, 415-3650
References
TAC MC6285, TAC MC6286, TAC MC6579, TAC MC6612, TAC MC6614, TAC MC6626, TAC MC6783, TAC MC6792
Download: ML070390530 (7)

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transactions shall have no effect on the license for the BVPS Unit 2 facility throughout the term of the license.

(b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the term or conditions of any lease agreements executed as part of these transactions; (ii) the BVPS Operating Agreement, (iii) the existing property insurance coverage for BVPS Unit 2, and (iv) any action by a lessor or others that may have adverse effect on the safe operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations set forth in 10 CFR Chapter 1 and 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 FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 161, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 161

(8) Detailed Control Room Design Review (DCRDR)

Deleted (9) Safety Parameter Display System (SPDS)

Deleted (10) Fire Protection Modifications (Section 9.5.1 of SER Supplement 6)

Deleted (11) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 161, are hereby incorporated into this license. FENOC shall operate the facility in accordance with the Additional Conditions.

(12) Steam Generator Surveillance Interval Extension Deleted D. Exemptions The following exemptions are authorized by law and will not endanger life or property or the common defense and security, and certain special circumstances are present. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

(1) The facility requires an exemption from the requirements of General Design Criterion (GDC) 4, Appendix A to 10 CFR 50. The staff has described in detail in Supplement 4 and Supplement 5 to the Safety Evaluation Report the technical basis and "special circumstances" associated with this exemption. The staff's environmental assessment was published on March 27, 1987 (52 FR 9979).

Therefore, pursuant to 10 CFR 50.12(a)(1), 10 CFR 50.12(a)(2)(ii) and (iv),

Beaver Valley Power Station, Unit 2 is exempt from the requirements of GDC 4, Appendix A to 10 CFR 50 with respect to the dynamic loading effects associated with the postulated pipe breaks described in detail in Section 3.6.3 of Supplement 4 to the Safety Evaluation Report. These dynamic loading effects include pipe whip, jet impingement, and break-associated dynamic transients.

Specifically, this eliminates the need to install jet impingement barriers and pipe whip restraints associated with postulated pipe breaks in the pressurizer surge line, reactor coolant bypass system, Amendment No. 161

APPENDIX D ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-73 FirstEnergy Nuclear Operating Company, FirstEnergy Nuclear Generation Corp., Ohio Edison Company, and The Toledo Edison Company shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation Number Date 161 Schedule for New and Revised Surveillance Requirements (SRs)

The schedule for performing SRs that are new or revised in The Amendment No. 161 shall be as follows: amendment shall be For SRs that are new in this amendment, the first performance implemented is due at the end of the first surveillance interval, which begins within 150 days on the date of implementation of this amendment. from date of issuance For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance subject to the modified acceptance criteria is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

161 Relocation of Certain Technical Specification Requirements License Amendment No. 161 authorizes the relocation of certain The Technical Specifications to other licensee-controlled documents. amendment Implementation of this amendment shall include relocation of the shall be requirements to the specified documents, as described in implemented (1) Sections 4D and 4E of the NRC staff's Safety Evaluation, and within 150 days (2) Table LA, Removed Detail Changes, and Table R, Relocated from date of Specifications, attached to the NRC staff's Safety Evaluation, issuance which is enclosed in this amendment.

4 Amendment No. 161

(3) FENOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, 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; (4) FENOC, 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 or instrument calibration or associated with radioactive apparatus or components; (5) FENOC, 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 operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: 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; and 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 FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 278, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Auxiliary River Water System (Deleted by Amendment No. 8)

Amendment No. 278

(6) Systems Integrity FENOC shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:

1. Provisions establishing preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

(7) Iodine Monitoring FENOC shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

(8) Backup Method for Determining Subcooling Margin FENOC shall implement a program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin. This program shall include the following:

1. Training of personnel, and

2. Procedures for monitoring.

(9) Steam Generator Surveillance Interval Extension Deleted per License Amendment No. 278.

Amendment No. 278

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(10) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 278, are hereby incorporated into this license. FENOC shall operate the facility in accordance with the Additional Conditions.

D. Physical Protection FENOC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21 is entitled: "Beaver Valley Power Station (BVPS) Physical Security Plan" submitted by letter September 9, 2004, and supplemented September 30, 2004, and October 14, 2004.

E. All work and activities in connection with this project shall be performed pursuant to the provisions of the Commonwealth of Pennsylvania Clean Streams Acts of June 24, 1913, as amended and of June 22, 1937, as amended, and in accordance with all permits issued by the Department of Environmental Resources of the Commonwealth of Pennsylvania.

F. This amended license is effective as of the date of issuance and shall expire at midnight on January 29, 2016.

FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY R. S. BOYD Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation Date of Issuance: July 2, 1976 Amendment No. 278

APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-66 FirstEnergy Nuclear Operating Company and FirstEnergy Nuclear Generation Corp. shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation Number Date 278 Schedule for New and Revised Surveillance Requirements (SRs)

The schedule for performing SRs that are new or revised in The Amendment No. 278 shall be as follows: amendment shall be For SRs that are new in this amendment, the first performance implemented is due at the end of the first surveillance interval, which begins within 150 days on the date of implementation of this amendment. from date of issuance For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance subject to the modified acceptance criteria is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

278 Relocation of Certain Technical Specification Requirements License Amendment No. 278 authorizes the relocation of certain The Technical Specifications to other licensee-controlled documents. amendment Implementation of this amendment shall include relocation of the shall be requirements to the specified documents, as described in implemented (1) Sections 4D and 4E of the NRC staff's Safety Evaluation, and within 150 days (2) Table LA, Removed Detail Changes, and Table R, Relocated from date of Specifications, attached to the NRC staff's Safety Evaluation, issuance which is enclosed in this amendment.

4 Amendment No. 278