ML101120926

Issuance of Amendments Spray Elimination of Recirculation Spray Pump Response Time Surveillance Requirement

ML101120926
Person / Time
Site:	Beaver Valley
Issue date:	05/20/2010
From:	Nadiyah Morgan Plant Licensing Branch 1
To:	Harden P FirstEnergy Nuclear Operating Co
Morgan Nadiyah, NRR/Dorl, 415-1016
References
TAC ME1501, TAC ME1502
Download: ML101120926 (52)

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Mr. Paul A. Harden Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 20, 2010 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, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: SPRAY ELlIVIINATION OF RECIRCULATION SPRAY PUMP RESPONSE TIME SURVELLIENCE REQUIREMENT (TAC NOS.

ME1501 AND ME1502)

Dear Mr. Harden:

The Commission has issued the enclosed Amendment No. 285 to Renewed Facility Operating License No. DPR-66 for the Beaver Valley Power Station, Unit NO.1 (BVPS-1) and Amendment No. 171 to Renewed Facility Operating License No. NPF-73 for the Beaver Valley Power Station, Unit NO.2 (BVPS-2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 11J 2009.

These amendments revise TSs to eliminate Surveillance Requirement (SR) 3.3.2.9, verification of Engineered Safety Function Actuation System Response Times, for the recirculation spray pumps. TS 1.4 is revised to add clarification to Notes associated with SR in accordance with Technical Specification Task Force Traveler, TSTF-475-A, Revision 1J "Control Rod Notch Testing Frequency and SRIVI [source range monitor] Insert Control Rod Action." The amendment also revises the BVPS-1 operating license to remove a License Condition for recommended inspections of steam generator repairs, and makes several editorial changes to the BVPS-1 and 2 operating license pages.

A copy of the related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, adiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosures:

1. Amendment No. 285 to DPR-66

2. Amendment No. 171 to NPF-73

3. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.

DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 285 License No. DPR-66

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by FirstEnergy Nuclear Operating Company, et al.

(the licensee), dated June 11, 2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2.

Accordingly, the license is amended by changes to the Technical Specifications contained in Appendix A, and changes to Appendix Band C, as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 285, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

~/~

Nancy L. Salgado, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License, Technical Specifications, Appendix B, and Appendix C Date of Issuance:

May 20, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 285 RENEWED FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of the Renewed Facility Operating License with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 2

3 4

5 6

7 8

2 3

4 5

6 7

8 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 1.4-5 1.4-5 3.3.2-9 3.3.2-9 Replace the following page of Appendix 8 Environmental Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert Appendix 8 8-1 Replace the following pages of Appendix C Additional Conditions with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 1

2 3

4 5

C-1 C-2 C-3 C-4 C-5

- 2 G.

The issuance of this renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Renewed Facility Operating License No. OPR-66 is in accordance with 10 CFR Part 51 (formerly Appendix 0 of 10 CFR Part 50) of the Commission's regulations and all applicable requirements have been satisfied; and I.

The receipt, possession, and use of source, by-product, and special nuclear material as authorized by this renewed operating license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70, including 10 CFR Sections 30.33,40.32, 70.23, and 70.31.

J.

Actions have been identified and have been or will be taken with respect to: (1) managing the effects of aging on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1) during the period of extended operation, and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this renewed operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3 for the facility, and that any changes made to the facility's current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commission's regulations;

2.

Renewed Facility Operating License No. OPR-66 is hereby issued to FENOC and FirstEnergy Nuclear Generation Corp. to read as follows:

A.

This renewed license applies to the Beaver Valley Power Station, Unit No.1, a pressurized water nuclear reactor and associated equipment (the facility), owned by FirstEnergy Nuclear Generation Corp., and operated by FENOC. The facility is located in Beaver County, Pennsylvania, on the southern shore of the Ohio River, and is described in the "Updated Final Safety Analysis Report" as supplemented and amended and the Environmental Report as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1)

FENOC, pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess, use, and operate the facility, and FirstEnergy Nuclear Generation Corp. to possess the facility at the designated location in Beaver County, Pennsylvania in accordance with the procedures and limitations set forth in this renewed license; (2)

FENOC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; Amendment No. 285 Beaver Valley Unit 1 Renewed Operating License OPR-66

- 3 (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, 40, 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 renewed operating 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. 285, 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. 285 Beaver Valley Unit 1 Renewed Operating License DPR-66

- 4 (3)

Less Than Three Loop Operation Deleted per License Amendment No. ~.

(4)

Steam Generator Water Rise Rate Deleted per License Amendment No. 24.

(5)

Fire Protection Program FENOC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (UFSAR) for the facility, subject to the following provision: FENOC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 285 Beaver Valley Unit 1 Renewed Operating License DPR-66

- 5 (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. 285 Beaver Valley Unit 1 Renewed Operating License DPR-66

- 6 (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.

(11)

Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders Amendment No. 285 Beaver Valley Unit 1 Renewed Operating License DPR-66

- 7 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, October 14, 2004, and May 12, 2006.

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.

License Renewal Commitments - The UFSAR supplement, as revised, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to and/or during the period of extended operation. FENOC shall complete these activities in accordance with Appendix A of NUREG-1929, Safety Evaluation Report Related to the Beaver Valley Power Station, Units 1 and 2, dated October 2009, and Supplement 1 of NUREG-1929, dated October 2009, and shall notify the NRC in writing when activities to be completed prior to the period of extended operation are complete and can be verified by NRC inspection.

G.

UFSAR Supplement Changes - The information in the UFSAR supplement, as revised, submitted pursuant to 10 CFR54.21 (d), shall be incorporated into the UFSAR as required by 10 CFR 50.71(e) following the issuance of this renewed operating license.

Until that update is complete, FENOC may not make changes to the information in the supplement. Following incorporation into the UFSAR, the need for prior Commission approval of any changes will be governed by 10 CFR 50.59.

H.

Capsule Withdrawal Schedule - For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.

I.

Containment Liner Volumetric Inspection a) If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the non-random areas examined using ultrasonic testing (UT) as described in Supplement 1 of NUREG-1929, UT examinations shall be performed at additional non-random areas, to be selected based on this operating experience. Should additional degradation be identified, additional non-random areas shall be UT examined until no further degradation (greater than 10 percent of the nominal thickness) is identified. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.

Amendment No. 285 Beaver Valley Unit 1 Renewed Operating License DPR-66

- 8 b) If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the random samples examined using ultrasonic testing (UT) as described in Supplement 1 of NUREG 1929, UT examinations shall be performed on additional random samples, to ensure a 95 percent confidence that 95 percent of the unexamined accessible containment liner is not degraded. If additional degradation is identified, the sample size for UT examinations shall be further expanded until the statistical sampling has achieved the 95 percent confidence goal described previously. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.

3.

This renewed operating license is effective as of the date of issuance and shall expire at midnight on January 29, 2036.

FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY:

Eric J. Leeds, Director Office of Nuclear Reactor Regulation Attachments:

1.

Appendix A - Technical Specifications

2.

Appendix C - Additional Conditions Date of Issuance: November 05, 2009 Amendment No. 285 Beaver Valley Unit 1 Renewed Operating License DPR-66

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

- NOTE-Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after

~ 25% RTP.

Perform channel adjustment.

17 days The interval continues, whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches ~ 25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (plus the extension allowed by SR 3.0.2) with power

~ 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Beaver Valley Units 1 and 2 1.4 - 5 Amendments 285/171

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 7)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER UNIT 1 UNIT2 SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE VALUE

2. Containment Spray Systems (2) Automatic 1,2,3,4 2 trains C

SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.6 Actuation Relays (3) Contain 1,2,3 4

E SR 3.3.2.1

~ 11.43 psig

~ 11.4 psig ment SR 3.3.2.4(e)(f)

Pressure SR 3.3.2.S(e)(f)

High High SR 3.3.2.9

b. Recirculation Spray (1) Automatic 1,2,3 2 trains F

SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic (2) Refueling 1,2,3 3

D SR 3.3.2.1 z 27' 4" and z 32' S" and Water SR 3.3.2.4(e)(f)

~ 27' 11"

~ 32' 10" Storage SR 3.3.2.S(e)(f)

Tank (RWST)

Level Low Coincident with Contain 1,2,3 4

E SR 3.3.2.1

~ 11.43 psig

~ 11.4 psig ment SR 3.3.2.4(e)(f)

Pressure SR 3.3.2.S(e)(f)

High High (e)

If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

(f)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint, or a value that is more conservative than the Nominal Trip Setpoint; otherwise, the channel shall be declared inoperable.

The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined as-found acceptance criteria band, and the as-left setpoint tolerance band are specified in a document incorporated by reference into the Updated Final Safety Analysis Report.

Beaver Valley Units 1 and 2 3.3.2 - 9 Amendments 285 /171

APPENDIX B ENVIRONIVIENTAL TECHNICAL SPECIFICATIONS OPERATING LICENSE NO. DPR-66 Appendix B to Operating License DPR-66 has been eliminated in its entirety by Amendment 93. See Amendment Nos. 25, 64, 66 and 77.

Beaver Valley Unit 1 B-1 Amendment No. 285

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 Number 202 The licensee is authorized to relocate certain Technical Specification requirements to licensee controlled documents. Implementation of this amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated September 9, 1996, and evaluated in the staffs safety evaluation attached to this amendment.

209 The licensee is authorized to relocate certain Technical Specification requirements to licensee controlled documents. Implementation of this amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated March 14, 1997, as supplemented July 29 and August 13, 1997, and evaluated in the staffs safety evaluation attached to this amendment.

210 The licensee is authorized to relocate certain Technical Specification requirements to licensee controlled documents. Implementation of this amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated September 11, 1997, and evaluated in the staffs safety evaluation attached to this amendment.

Implementation Date The amendment shall be implemented within 60 days from April 14, 1997 The amendment shall be implemented within 60 days from December 10, 1997 The amendment shall be implemented within 30 days from January 20, 1998 Beaver Valley Unit 1 C-1 Amendment No. 285

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 Number 225 The licensee is authorized to relocate certain Technical Specification requirements to licensee controlled documents. Implementation of this amendment shall include the relocation of these Technical Specification requirements to the appropriate documents as described in the licensee's application dated December 24, 1998, as supplemented June 15, June 17, and July 7, 1999, and evaluated in the staff's safety evaluation attached to this amendment.

269 On the closing date(s) of the transfers to FENGenCo of their interests in Beaver Valley Power Station, Unit No.1, Pennsylvania Power Company and Ohio Edison Company shall transfer to FENGenCo all of each transferor's respective accumulated decommissioning funds for Beaver Valley Power Station, Unit No.1, and tender to FENGenCo additional amounts equal to remaining funds expected to be collected in 2005, as represented in the application dated June 1, 2005, but not yet collected by the time of closing. All of the funds shall be deposited in a separate external trust fund for the reactor in the same amount as received with respect to the unit to be segregated from other assets of FENGenCo and outside its administrative control, as required by NRC regulations, and FENGenCo shall take all necessary steps to ensure that this external trust fund is maintained in accordance with the requirements of the order approving the transfer of the license and consistent with the safety evaluation supporting the order and in accordance with the requirements of 10 CFR Section 50.75, "Reporting and recordkeeping for decommissioning planning."

Implementation Date The amendment shall be implemented within 60 days from August 30, 1999 The amendment shall be implemented within 30 days from December 16, 2005 Beaver Valley Unit 1 C-2 Amendment No. 285

269 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 Number By the date of closing of the transfer of the ownership interests in Beaver Valley Power Station, Unit NO.1 from Pennsylvania Power Company to FENGenCo, FENGenCo shall obtain a parent company guarantee from FirstEnergy in an initial amount of at least $80 million (in 2005 dollars) to provide additional decommissioning funding assurance regarding such ownership interests. Required funding levels shall be recalculated annually and, as necessary, FENGenCo shall either obtain appropriate adjustments to the parent company guarantee or otherwise provide any additional decommissioning funding assurance necessary for FENGenCo to meet NRC requirements under 10 CFR 50.75.

The Support Agreements described in the applications dated May 18, 2005 (up to $80 million), and June 1, 2005 (up to $400 million), shall be effective consistent with the representations contained in the applications.

FENGenCo shall take no action to cause FirstEnergy, or its successors and assigns, to void, cancel, or modify the Support Agreements without the prior written consent of the NRC staff, except, however, the $80 million Support Agreement in connection with the transfer of the Pennsylvania Power Company interests may be revoked or rescinded if and when the $400 million support agreement described in the June 1, 2005, application becomes effective. FENGenCo shall inform the Director of the Office of Nuclear Reactor Regulation, in writing, no later than ten days after any funds are provided to FENGenCo by FirstEnergy under either Support Agreement.

Implementation Date The amendment shall be implemented within 30 days from December 16, 2005 Beaver Valley Unit 1 C-3 Amendment No. 285

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 Number 278 Schedule for New and Revised Surveillance Requirements (SRs)

The schedule for performing SRs that are new or revised in Amendment No. 278 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.

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 Technical Specifications to other licensee-controlled documents.

Implementation of this amendment shall include relocation of the requirements to the specified documents, as described in (1) Sections 40 and 4E of the NRC staffs Safety Evaluation, and (2) Table LA, Removed Detail Changes, and Table R, Relocated Specifications, attached to the NRC staffs Safety Evaluation, which is enclosed in this amendment.

Implementation Date The amendment shall be implemented within 150 days from date of issuance The amendment shall be implemented within 150 days from date of issuance Beaver Valley Unit 1 C-4 Amendment No. 285

281 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 Number Initial Performance of New Surveillance and Assessment Requirements Upon implementation of Amendment No. 281 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by Surveillance Requirement (SR) 3.7.10.4, in accordance with Specification 5.5.14.c(i), the assessment of CRE habitability as required by Specification 5.5.14.c(ii), and the measurement of CRE pressure as required by Specification 5.5.14.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.14.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.14.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.

Implementation Date The amendment shall be implemented within 120 days from date of issuance Beaver Valley Unit 1 C-5 Amendment No. 285

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.

OHIO EDISON COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 License No. NPF-73

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by FirstEnergy Nuclear Operating Company, et al.

(the licensee), dated June 11,2009, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2.

Accordingly, the license is amended by changes to the Technical Specifications contained in Appendix A, and changes to Appendix Band D, as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 171, 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.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License, Technical Specifications, Appendix B, and Appendix D Date of Issuance:

May 20, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 171 RENEWED FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50~412 Replace the following pages of the Renewed Facility Operating License with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 2

3 4

5 6

2 3

4 5

6 7

7 8

9 8

9 10 10 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 1.4-6 1.4-5 3.3.2-10 3.3.2-9 Replace the following pages of Appendix 8 Environmental Protection Plan with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert Appendix 8 8-i Table of Contents 8-ii 1

2 3

4 5

8-1 8-2 8-3 8-4 8-5 Replace the following pages of Appendix 0 Additional Conditions with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 1

0-1 2

3 4

5 0-2 0-3 0-4 0-5

- 2 E.

FENOC is technically qualified to engage in the activities authorized by this renewed operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.

The licensees have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.

The issuance of this renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Renewed Operating License No. NPF-73 is subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations, and all applicable requirements have been satisfied; I.

The receipt, possession and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.

J.

Actions have been identified and have been or will be taken with respect to: (1) managing the effects of aging on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1) during the period of extended operation, and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this renewed operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3 for the facility, and that any changes made to the facility's current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commission's regulations;

2.

Renewed Facility Operating License NPF-73 is hereby issued to FENOC, FirstEnergy Nuclear Generation Corp., Ohio Edison Company, and The Toledo Edison Company (the licensees) to read as follows:

A.

This renewed license applies to the Beaver Valley Power Station, Unit 2, a pressurized water reactor and associated equipment (the facility), owned by FirstEnergy Nuclear Generation Corp. (owner), leased to Ohio Edison Company (lessee), and The Toledo Edison Company (lessee) and operated by FENOC (collectively the licensees). The facility is located on the licensees' site on the southern shore of the Ohio River in Beaver County, Pennsylvania, approximately 22 miles northwest of Pittsburgh and 5 miles east of East Liverpool, Ohio, and is described in FENOC's Updated Final Safety Analysis Report, as supplemented and amended, and in its Environmental Report, as supplemented and amended; B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1)

Pursuant to Section 103 of the Act and 10 CFR Part 50, FENOC to possess, use, and operate the facility at the designated location in Beaver County, Pennsylvania, in accordance with the procedures and limitations set forth in this license; Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 3 (2)

(3)

(4)

(5)

(6)

(7)

Beaver Valley Unit 2 Pursuant to the Act and 10 CFR Part 50, FirstEnergy Nuclear Generation Corp., Ohio Edison Company, and The Toledo Edison Company to possess the facility at the designated location in Beaver County, Pennsylvania, in accordance with the procedures and limitations set forth in the license; Pursuant to the Act and 10 CFR Part 70, FENOC, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FENOC to receive, possess, and use at any time any byproduct, source, and special nuclear material such 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; Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FENOC 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 other activity associated with radioactive apparatus or components; Pursuant to the Act and 10 CFR Parts 30, 40, and 70, FENOC to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.

(a)

Ohio Edison Company and The Toledo Edison Company are authorized to transfer any portion of their respective leased interests in BVPS Unit 2 and a proportionate share of their leased interests in the BVPS common facilities to certain potential investors identified in their submittals of July 14, 16, 22 and 31, and September 14, 17 and 18, 1987, and at the same time to lease back from such purchasers such interest transferred in the BVPS Unit 2 facility. The term of the lease is for approximately 29-1/2 years subject to a right of renewal. Such sale and leaseback transactions are subject to the representations and conditions set forth in the aforementioned submittals. Specifically, a lessor and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over the license of BVPS Unit 2. For purposes of this condition the limitations in 10 CFR 50.81, as now in effect and as may be subsequently amended, are fully applicable to the lessor and any successor in interest to that lessor as long as the license for BVPS Unit 2 remains in effect; these financial transactions shall have no effect on the license for the BVPS Unit 2 facility throughout the term of the license.

Amendment No. 171 Renewed Operating License NPF-73

- 4 (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 renewed operating 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. 171, 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. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 5 (3)

Initial Startup Test Program (Section 14 of the SER, and Supplements 3 and 5)

Deleted (4)

Fresh Fuel Storage The following criteria apply to the storage and handling of new fuel assemblies in the fuel handling building:

(a)

No more than two fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks at anyone time.

(b)

The minimum edge-to-edge distance between the above two new assemblies, the shipping container array, and the storage rack arrays shall be at least 12 inches.

(c)

New fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and subsequent draining of the fuel storage area.

(5)

Inservice Inspection (Section 6:6 of SER Supplement 5)

Deleted (6)

Formal Federal Emergency Management Agency Finding In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.

(7)

Plant Safety Monitoring System (PSMS)

Deleted Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 6 (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. 163, are hereby incorporated into this license. FENOC shall operate the facility in accordance with the Additional Conditions.

(12)

Steam Generator Surveillance Interval Extension Deleted (13)

Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 7 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, safety injection system, and residual heat removal system. This exemption will expire when the current GDC 4 rulemaking changes have been completed.

Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 8 (2)

The facility requires an exemption from the requirements of 10 CFR 50, Appendix J, Section IIID.2(b)(ii). The justification of this exemption is contained in Section 6.2.6 of Supplement 5 to the Safety Evaluation Report and rnodlfled by a letter dated July 26, 1995. The staff's environmental assessment was published on May 12, 1987 (52 FR 17651) and on June 9, 1995 (60 FR 30611). Therefore, pursuant to 10 CFR 50.12(a)(1) and 10 CFR 50.12(a)(2)(ii) and (iii), Beaver Valley Power Station, Unit 2 is exempt from the quoted requirements and instead, is required to perform the overall air lock leak test at pressure Pa before establishing containment integrity if air lock maintenance has been performed that could affect the air lock sealing capability. Local leak rate testing at a pressure of not less than Pa may be substituted for an overall air lock test where the design permits.

E.

Physical Security 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, October 14, 2004, and May 12, 2006.

F.

Fire Protection Program (Section 9.5.1 of SER Supplement 3)

FENOC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report through Amendment No. 17, and submittals dated May 18, May 20, May 21, June 24 and July 6, 1987, and as described in the Safety Evaluation Report dated October 1985, and Supplements 1 through 6, subject to the following provision:

FENOC may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 9 G.

Reporting to the Commission DELETED H.

Financial Protection The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I.

License Renewal Commitments - The UFSAR supplement, as revised, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to and/or during the period of extended operation. FENOC shall complete these activities in accordance with Appendix A of NUREG-1929, Safety Evaluation Report Related to the Beaver Valley Power Station, Units 1 and 2, dated October 2009, and Supplement 1 of NUREG-1929, dated October 2009, and shall notify the NRC in writing when activities to be completed prior to the period of extended operation are complete and can be verified by NRC inspection.

J.

UFSAR Supplement Changes - The information in the UFSAR supplement, as revised, submitted pursuant to 10 CFR 54.21(d), shall be incorporated into the UFSAR as required by 10 CFR 50.71(e) following the issuance of this renewed operating license. Until that update is complete, FENOC may not make changes to the information in the supplement. Following incorporation into the UFSAR, the need for prior Commission approval of any changes will be governed by 10 CFR 50.59.

K.

Capsule Withdrawal Schedule - For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.

L.

Containment Liner Volumetric Inspection a) If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the non-random areas examined using ultrasonic testing (UT) as described in Supplement 1 of NUREG-1929, UT examinations shall be performed at additional non random areas, to be selected based on this operating experience. Should additional degradation be identified, additional non-random areas shall be UT examined until no further degradation (greater than 10 percent of the nominal thickness) is identified. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.

b) If degradation (greater than 10 percent of the nominal thickness not attributable to fabrication/erection practices) is identified in the random samples examined using ultrasonic testing (UT) as described in Supplement 1 of NUREG-1929, UT examinations shall be performed on additional random Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

- 10 samples, to ensure a 95 percent confidence that 95 percent of the unexamined accessible containment liner is not degraded. If additional degradation is identified, the sample size for UT examinations shall be further expanded until the statistical sampling has achieved the 95 percent confidence goal described previously. All areas with degradation shall be reexamined over at least the next three successive inspection periods to ensure that progression of the degradation is not occurring.

3.

Expiration This renewed operating license is effective as of the date of issuance and shall expire at midnight on May 27,2047.

FOR THE NUCLEAR REGULATORY COMMISSION ORIGINAL SIGNED BY:

Eric J. Leeds, Director Office of Nuclear Reactor Regulation Attachments:

1.

Appendix A - Technical Specifications

2.

Appendix B - Environmental Protection Plan

3.

Appendix D - Additional Conditions Date of Issuance: November 05, 2009 Amendment No. 171 Beaver Valley Unit 2 Renewed Operating License NPF-73

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

- NOTE-Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after

~ 25% RTP.

Perform channel adjustment.

7 days The interval continues, whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after power reaches ~ 25% RTP to perform the Surveillance.

The Surveillance is still considered to be performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was

< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (plus the extension allowed by SR 3.0.2) with power

~ 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval (plus the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Beaver Valley Units 1 and 2 1.4 - 5 Amendments 285/171

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 7)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER UNIT 1 UNIT2 SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE VALUE

2. Containment Spray Systems (2) Automatic 1,2,3,4 2 trains C

SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.6 Actuation Relays (3) Contain 1,2,3 4

E SR 33.2.1

~ 11.43 psig

~ 11.4 psig ment SR 3.3.2.4(e)(f)

Pressure -

SR 3.3.2.8(e)(f)

High High SR 3.3.2.9

b. Recirculation Spray (1) Automatic 1,2,3 2 trains F

SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic (2) Refueling 1,2,3 3

D SR 3.3.2.1

~ 27' 4" and

~ 32' 8" and Water SR 3.3.2.4(e)(f)

~ 27' 11"

~ 32' 10" Storage SR 3.3.2.8(e)(f)

Tank (RWST)

Level Low Coincident with Contain 1,2,3 4

E SR 3.3.2.1

~ 11.43 psig

~ 11.4 psig ment SR 3.3.2.4(e)(f)

Pressure SR 3.3.2.a(e)(f)

High High (e)

If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

(f)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Nominal Trip Setpoint, or a value that is more conservative than the Nominal Trip Setpoint; otherwise, the channel shall be declared inoperable.

The Nominal Trip Setpoint and the methodology used to determine the Nominal Trip Setpoint, the predefined as-found acceptance criteria band, and the as-left setpoint tolerance band are specified in a document incorporated by reference into the Updated Final Safety Analysis Report.

Beaver Valley Units 1 and 2 3.3.2 - 9 Amendments 285 / 171

APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-73 BEAVER VALLEY POWER STATION UNIT 2 FIRSTENERGY NUCLEAR OPERATING COMPANY, ET AL DOCKET NO. 50-412 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)

AUGUST 1987 Beaver Valley Unit 2 B-i Amendment No. 171

APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-73 BEAVER VALLEY POWER STATION UNIT2 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)

TABLE OF CONTENTS Section Page 1.0 Objectives of the Environmental Protection Plan B-1 2.0 Environmental Protection Issues B-1 3.0 Consistency Requirements B-1 3.1 Plant Design and Operation B-1 3.2 Reporting Related to the NPDES Permit and State Certifications B-2 3.3 Changes Required for Compliance with Other Environmental Regulations B-2 4.0 Environmental Conditions B-2 4.1 Unusual or Important Environmental Events B-2 4.2 Environmental Monitoring B-3 5.0 Administrative Procedures B-3 5.1 Review and Audit B-3 5.2 Records Retention B-3 5.3 Changes in Environmental Protection Plan B-4 5.4 Plant Reporting Requirements B-4 Beaver Valley Unit 2 B-ii Amendment No. 171

1.0 Objectives of the Environmental Protection Plan The Environmental Protection Plan (EPP) is to provide for protection of nonradiological environmental values during operation of the Beaver Valley Power Station, Unit 2 (facility). The principal objectives of the EPP are as follows:

(1)

Verify that the facility is operated in an environmentally acceptable manner, as established by the Final Environmental Statement - Operating License Stage (FES-OL) and other NRC environmental impact assessments.

(2)

Coordinate NRC requirements and maintain consistency with other Federal, State, and local requirements for environmental protection.

(3)

Keep NRC informed of the environmental effects of facility construction and operation and of actions taken to control those effects.

Environmental concerns identified in the FES-OL (September 1985, NUREG-1094) which relate to water quality matters are regulated by way of the licensee's* NPDES permit.

2.0 Environmental Protection Issues In the FES-OL (f\\JUREG-1 094, September 1985), the staff considered the environmental impacts associated with the operation of the Beaver Valley Power Station, Unit 2. No aquatic/water quality, terrestrial, or noise issues were identified.

3.0 Consistency Requirements 3.1 Plant Design and Operation The licensee may make changes in station design or operation or perform tests or experiments affecting the environment provided such activities do not involve an unreviewed environmental question and do not involve a change in the EPP*. Changes in station design or operation or performance of tests or experiments which do not affect the environment are not subject to the requirements of this EPP. Activities governed by Section 3.3 are not subject to the requirements of this Section.

Before engaging in additional construction or operational activities which may significantly affect the environment, the licensee shall prepare and record an environmental evaluation of such activity. Activities are excluded from this requirement if all measurable nonradiological environmental effects are confined to the on-site areas previously disturbed during site preparation and plant construction. When the evaluation indicates that such activity involves an unreviewed environmental question, the licensee shall provide a written evaluation of such activity and obtain prior NRC approval. Such activity and change to the EPP may be implemented only in accordance with an appropriate license amendment as set forth in Section 5.3 of this EPP.

• "Licensee" refers to FirstEnergy Nuclear Operating Company, operator of the facility, and acting as agent for FirstEnergy Nuclear Generation Corp., Ohio Edison Company, and The Toledo Edison Company, owners or lessees of the facility.

Beaver Valley Unit 2 B-1 Amendment No. 171

A proposed change, test, or experiment shall be deemed to involve an unreviewed environmental question if it concerns: (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level; or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact.

The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection. These records shall include written evaluations which provide bases for the determination that the change, test, or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0. The licensee shall include as part of the Annual Environmental Operating Report (per Subsection 5.4.1) brief descriptions, analyses, interpretations, and evaluations of such changes, tests, and experiments.

3.2 Reporting Related to the NPDES Permit and State Certification Changes to, or renewals of, the NPDES Permit or the State certification shall be reported to the NRC within 30 days following the date the change or renewal is approved. If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days following the date the stay is granted.

The licensee shall notify the NRC of changes to the effective NPDES Permit proposed by the licensee by providing NRC with a copy of the proposed change at the same time it is submitted to the permitting agency. The licensee shall provide the NRC a copy of the application for renewal of the NPDES Permit at the same time the application is submitted to the permitting agency.

3.3 Changes Required for Compliance with Other Environmental Regulators Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, State, and local environmental regulations are not subject to the requirements of Section 3.1.

4.0 Environmental Conditions 4.1 Unusual or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and reported to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by a written report per Subsection 5.4.2 of the EPP.

This provision does not relieve the licensee of the requirements of 10 CFR 50.59.

Beaver Valley Unit 2 B-2 Amendment No. 171

No routine monitoring programs are required to implement this condition.

4.2 Environmental Monitoring 4.2.1 Aguatic Monitoring The certifications and permits required under the Clean Water Act provide mechanisms for protecting water quality and, indirectly, aquatic biota. The NRC will rely on the decisions made by the Commonwealth of Pennsylvania under the authority of the Clean Water Act for any requirements for aquatic monitoring.

4.2.2 Terrestrial Monitoring DELETED.

4.2.3 Noise Monitoring Noise monitoring program during first year of plant operation (Section 5.14.4 of FES).

5.0 Administrative Procedures 5.1 Review and Audit The licensee shall provide for review and audit of compliance with the EPP. The audits shall be conducted independently of the individual or groups responsible for performing the specific activity. A description of the organization structure used to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.

5.2 Records Retention Records and logs relative to the environmental aspects of station operation shall be made and retained in a manner convenient for review and inspection. These records and logs shall be made available to !\\IRC on request.

Records of modifications to station structures, systems and components determined to potentially affect the continued protection of the environment shall be retained for the life of the station. All other records, data and logs relating to this EPP shall be retained for five years or, where applicable, in accordance with the requirements of other agencies.

Beaver Valley Unit 2 B-3 Amendment No. 171

5.3 Changes in Environmental Protection Plan Requests for changes in the EPP shall include an assessment of the environmental impact of the proposed change and a supporting justification. Implementation of such changes in the EPP shall not commence prior to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision to the EPP.

5.4 Plant Reporting Requirements 5.4.1 Routine Reports An Annual Environmental Operating Report describing implementation of this EPP for the previous year shall be submitted to the NRC prior to May 1 of each year. The period of the first report shall begin with the date of issuance of the operating license, and the initial report shall be submitted prior to May 1 of the year following issuance of the operating license.

The report shall include summaries and analyses of the results of the environmental protection activities required by Subsection 4.2 (if any) of this EPP for the report period, including a comparison with related preoperational studies, operational controls (as appropriate), and previous nonradiological environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment. If harmful effects or evidence of trends toward irreversible damage to the environment are observed, the licensee shall provide a detailed analysis of the data and a proposed course of mitigating action.

The Annual Environmental Operating Report shall also include:

(1)

A list of EPP noncompliances and the corrective actions taken to remedy them.

(2)

A list of all changes in station design or operation, tests, and experiments made in accordance with Subsection 3.1 which involved a potentially significant unreviewed environmental question.

(3)

A list of nonroutine reports submitted in accordance with Subsection 5.4.2.

In the event that some results are not available by the report due date, the report shall be submitted, noting and explaining the missing results. The missing results shall be submitted as soon as possible in a supplementary report.

5.4.2 A written report shall be submitted to the NRC within 30 days of occurrence of a nonroutine event. The report shall: (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact, and plant operating characteristics; (b) describe the probable cause of the event; (c) indicate the action taken to correct the reported event; (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems; and (e) indicate the agencies notified and their preliminary responses.

Beaver Valley Unit 2 B-4 Amendment No. 171

Events reportable under this subsection which also require reports to others Federal, State, or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection. The !\\IRC shall be provided with a copy of such reports at the same time it is submitted to the other agency.

Beaver Valley Unit 2 B-5 Amendment No. 171

APPENDIX 0 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 Number 83 The licensee is authorized to relocate certain Technical Specification requirements to licensee controlled documents. Implementation of this amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated September 9, 1996, and evaluated in the staffs safety evaluation attached to this amendment.

87 The licensee is authorized to relocate certain Technical Specification requirements to licensee controlled documents. Implementation of this amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated March 14, 1997, as supplemented July 29 and August 13, 1997, and evaluated in the staffs safety evaluation attached to this amendment.

88 The licensee is authorized to relocate certain Technical Specification requirements to Iicensee controlled documents. Implementation of this amendment shall include the relocation of these technical specification requirements to the appropriate documents, as described in the licensee's application dated September 11, 1997, and evaluated in the staffs safety evaluation attached to this amendment.

98 The licensee commits to perform visual acceptance examinations of sleeve welds; post weld heat treatment of sleeve welds; and the NRC-recommended inspections of repaired tubes as described in the licensee's application dated March 10, 1997, as supplemented July 28,1997, September 17,1997, April 30, 1998, and January 29, 1999, and evaluated in the staffs safety evaluation attached to this amendment.

Implementation Date The amendment shall be implemented within 60 days from April 14, 1997 The amendment shall be implemented within 60 days from December 10, 1997 The amendment shall be implemented within 30 days from January 20, 1998 The amendment shall be implemented within 60 days from March 26, 1999 Beaver Valley Unit 2 0-1 Amendment No. 171

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 Number 102 151 Additional Condition The licensee is authorized to relocate certain Technical Specification requirements to Iicensee controlled documents. Implementation of this amendment shall include the relocation of these Technical Specification requirements to the appropriate documents as described in the licensee's application dated December 24, 1998, as supplemented June 15, June 17, and JUly 7,1999, and evaluated in the staffs evaluation attached to this amendment.

On the closing date(s) of the transfers to FENGenCo of their interests in Beaver Valley Power Station, Unit No.2, Pennsylvania Power Company, The Cleveland Electric Illuminating Company, Ohio Edison Company, and The Toledo Edison Company shall transfer to FENGenCo all of each transferor's respective accumulated decommissioning funds for Beaver Valley Power Station, Unit No.2, except for funds associated with the leased portions of Beaver Valley Power Station, Unit No.2, and tender to FENGenCo additional amounts equal to remaining funds expected to be collected in 2005, as represented in the application dated June 1, 2005, but not yet collected by the time of closing. All of the funds shall be deposited in a separate external trust fund for the reactor in the same amount as received with respect to the unit to be segregated from other assets of FENGenCo and outside its administrative control, as required by NRC regulations, and FENGenCo shall take all necessary steps to ensure that this external trust fund is maintained in accordance with the requirements of the order approving the transfer of the license and consistent with the safety evaluation supporting the order and in accordance with the requirements of 10 CFR Section 50.75, "Reporting and recordkeeping for decommissioning planning."

Implementation Date The amendment shall be implemented within 60 days from August 30, 1999 The amendment shall be implemented within 30 days from December 16, 2005 Beaver Valley Unit 2 D-2 Amendment No. 171

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 151 By the date of closing of the transfer of the ownership The amendment interests in Beaver Valley Power Station, Unit NO.2 shall be implemented from Pennsylvania Power Company to FENGenCo, within 30 days from FENGenCo shall obtain a parent company guarantee December 16, 2005 from FirstEnergy in an initial amount of at least $80 million (in 2005 dollars) to provide additional decommissioning funding assurance regarding such ownership interests. Required funding levels shall be recalculated annually and, as necessary, FENGenCo shall either obtain appropriate adjustments to the parent company guarantee or otherwise provide any additional decommissioning funding assurance necessary for FENGenCo to meet NRC requirements under 10 CFR 50.75.

The Support Agreements described in the applications dated May 18, 2005 (up to $80 million), and June 1, 2005 (up to $400 million), shall be effective consistent with the representations contained in the applications.

FENGenCo shall take no action to cause FirstEnergy, or its successors and assigns, to void, cancel, or modify the Support Agreements without the prior written consent of the NRC staff, except, however, the $80 million Support Agreement in connection with the transfer of the Pennsylvania Power Company interests may be revoked or rescinded if and when the $400 million support agreement described in the June 1, 2005, application becomes effective. FENGenCo shall inform the Director of the Office of Nuclear Reactor Regulation, in writing, no later than ten days after any funds are provided to FENGenCo by FirstEnergy under either Support Agreement.

Beaver Valley Unit 2 D-3 Amendment No. 171

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

The schedule for performing SRs that are new or revised in Amendment No. 161 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.

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.

Relocation of Certain Technical Specification Requirements License Amendment No. 161 authorizes the relocation of certain Technical Specifications to other licensee-controlled documents.

Implementation of this amendment shall include relocation of the requirements to the specified documents, as described in (1) Sections 4D and 4E of the NRC staffs Safety Evaluation, and (2) Table LA, Removed Detail Changes, and Table R, Relocated Specifications, attached to the NRC staffs Safety Evaluation, which is enclosed in this amendment.

Implementation Date The amendment shall be implemented within 150 days from date of issuance The amendment shall be implemented within 150 days from date of issuance Beaver Valley Unit 2 D-4 Amendment No. 171

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 Number Additional Condition Implementation Date 163 Initial Performance of New Surveillance and Assessment Requirements Upon implementation of Amendment No. 163 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by Surveillance Requirement (SR) 3.7.10.4, in accordance with Specification 5.5.14.c(i), the assessment of CRE habitability as required by Specification 5.5.14.c(ii), and the measurement of CRE pressure as required by Specification 5.5.14.d, shall be considered met. Following implementation:

The amendment shall be implemented within 120 days from date of issuance (a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.14.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.14.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.

Beaver Valley Unit 2 D-5 Amendment No. 171

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT I\\IOS. 285 AND 171 TO FACILITY OPERATING LICENSE NOS. DPR-66 AND NPF-73 FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.

OHIO EDISON COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412

1.0 INTRODUCTION

By application dated June 11, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091660601), FirstEnergy Nuclear Operating Company (licensee),

requested changes to the Technical Specifications (TSs) for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2).

The proposed changes would: (1) revise TSs to eliminate Surveillance Requirement (SR) 3.3.2.9, which verifies that the Engineered Safety Feature (ESF) Actuation System Response Times are within the limits for the recirculation spray pumps, (2) revise Section 1.4 of the TSs to add clarification to Notes associated with SRs in accordance with Technical Specification Task Force Traveler, TSTF 475-A, Revision 1, "Control Rod Notch Testing Frequency and SRM

[Source Range Monitor] Insert Control Rod Action," which was approved for use by the Nuclear Regulatory Commission (NRC) on November 5,2007 (ADAMS Accession No. ML073050017),

(3) revise the BVPS-1 operating license to remove a License Condition for recommended inspections of steam generator (SG) repairs, and (4) makes several editorial changes to the operating license (OL) pages.

- 2

2.0 REGULATORY EVALUATION

2.1 Description of Systems Recirculation Spray System (RSS)

The RSS provides two primary functions. These functions are to provide containment spray in conjunction with the quench spray system to reduce containment temperature and pressure and to provide long term heat removal via the recirculation spray heat exchangers following a design basis accident (DBA). The recirculation spray pumps are started following receipt of a Refueling Water Storage Tank Level Low signal coincident with a Containment Pressure High-High signal.

This ensures that adequate water is contained in the containment sump to submerge the sump strainers and provide adequate net positive suction head to the recirculation spray pumps.

Steam Generators SG tubes function as an integral part of the reactor coolant pressure boundary and serve to isolate radiological fission products in the primary coolant from the secondary coolant and the environment. The original Model 51 SGs at BVPS-1 were replaced with Model54F SGs in 2006. Prior to the replacement of the Model 51 SGs, the licensee was authorized by TSs to repair flawed tubes by a method referred to as sleeving.

2.2 Proposed TSs Changes SR 3.3.2.9 for TS 3.3.2, Table 3.3.2-1, Function 2.b(2) would be eliminated for BVPS-1 and 2.

TS Example 1.4-3 in Section 1.4 "Frequency," would clarify that the 1.25 surveillance test interval extension in SR 3.0.2 is also applicable to time periods, specified in the Notes of the "Surveillance" column.

Deletion of the License Condition in Appendix C of the BVSP-1 OL regarding steam generator tubes inspection, issued in Amendment No. 208.

2.3 Regulatory Requirements and Guidance Part 50 of Title 10 of the Code of Federal Regulations (10 CFR), "Domestic Licensing of Production and Utilization Facilities," establishes the fundamental regulatory requirements with respect to the domestic licensing of nuclear production and utilization facilities. Specifically, Appendix A, "General Design Criteria (GDC) for Nuclear Power Plants," to 10 CFR Part 50 provides, in part, the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety.

10 CFR 50.36(c)(3), "Surveillance requirements," requires that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation (LCOs) will be met.

- 3 GDC - 13, "Instrumentation and Control," requires that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety, including those variables and systems that can affect the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems. Appropriate controls shall be provided to maintain these variables and systems within prescribed operating ranges.

GDC - 20, "Protective System Functions," requires the protection system to be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety.

3.0 TECHNICAL EVALUATION

3.1 Deletion of SR 3.3.2.9 from TS Table 3.3.2-1! Function 2.b(2)

The licensee proposed the elimination of SR 3.3.2.9 for TS 3.3.2, Table 3.3.2-1, Function 2.b(2).

The response time being verified by SR 3.3.2.9 for Function 2.b(2) is the time associated with starting the recirculation spray pumps.

The TS defined the ESF response time as that time interval from when the monitored parameter exceeds its actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function. For the RSS, the time interval is from when the Refueling Water Storage Tank level and the containment pressure exceed their setpoints to when the recirculation spray flow begins exiting the spray nozzles.

In the license amendment request (LAR), the licensee stated that based on the containment analysis, the earliest time that the recirculation spray initiation conditions would be reached is approximately 19 minutes for BVPS-1 and 39 minutes for BVPS-2, following the initiating event.

Upon initiation, the estimated response time of the system is 65 seconds for BVPS-1 and 77 seconds for BVPS-2.

The licensee performed a sensitivity evaluation for BVPS-1, in which the recirculation spray response time was varied. The evaluation demonstrated that the measurable system response time could be greatly increased before results would be significantly affected. A substantial increase in signal delay and/or pump start time would be evident during other currently required SR testing, such as channel operation tests (SR 3.3.2.4), channel calibrations (SR 3.3.2.8) and recirculation spray pump testing (SR 3.6.7.2 and SR 3.6.7.3). For BVPS-2, potential response time variations would have an even less significant effect since the initiation time would be longer.

Response time tests are typically required when the system response times are critical to mitigation of an event. Since the RSS does not actuate until late in a DBA, and the estimated response time of the system is relatively small when compared to the entire event timeline, the response time of the RSS is not critical to mitigation of a DBA. Since other required SRs assure that the necessary quality of systems and components is maintained and that facility operation will be within safety limits, and the LCOs will be met, the NRC staff finds that the elimination of

- 4 the response time test associated with the recirculation spray pumps is acceptable for BVPS-1 and 2.

3.2 Clarification of TS Example 1.4-3 The NRC staff has reviewed the licensee's proposed change to Example 1.4-3 in Section 1.4 "Frequency," which is to clarify that the 1.25 surveillance test interval extension in SR 3.0.2 is also applicable to time periods specified in the Notes of the "Surveillance" column. The clarification to the example makes it consistent with the definition of specified "Frequency" provided in the second paragraph of Section 1.4 which states that:

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, SR Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements."

Therefore, NRC staff finds this change acceptable for BVPS-1 and 2.

3.3 Elimination of License Condition for BVPS-1 Prior to the replacement of the Model 51 SGs, the licensee was authorized by TSs to repair flawed tubes by a method referred to as sleeving. The authorization for sleeving was accompanied by a license condition which stated:

The licensee commits to perform the post weld heat treatment of sleeve welds and the NRC recommended inspections for repaired tubes as described in the licensee's application dated March 10, 1997, as supplemented July 28 and September 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

The use of sleeving as a repair method at BVPS-1 was removed in Amendment No. 273 (ADAMS Accession No. Ml060240146). Since sleeving is no longer permitted for the replacement SGs at BVPS-1, the license condition is no longer necessary and can be removed. The NRC staff finds that this is acceptable.

3.4 Administrative Changes to Operating License (OL) Pages In the LAR, the license requested to make several editorial changes to the Ol pages, Appendix Band C for BVPS-1, and Appendix Band D for BVPS-2.

3.4.1 Changes to BVPS-1 Ol Pages On page 2 of the Ol, a period was added after "G" on the first line of the page.

Also, the words "Beaver Valley Unit 1" were added to the bottom of the left-hand corner of the page.

- 5 On page 3 of the Ol, the amendment number was changed to "285" in section C (2). Also, the words "Beaver Valley Unit 1" were added to the bottom of the left hand corner of the page.

On pages 4 - 8, the words "Beaver Valley Unit 1" were added to the bottom of the left-hand corner of the page.

The title of the title page of Appendix B was changed to "Appendix B, Environmental Technical Specifications Operating License No. OPR-66." Also, the words "Beaver Valley Unit 1" were added to the bottom of the left-hand corner of the page.

Pages 1 - 5 of Appendix C were renumbered as C-1, C-2, C-3, C-4, and C-5.

Also, the words "Beaver Valley Unit 1" were added to the bottom of the left-hand corner of the page.

On page 1 of Appendix C, the license condition issued by Amendment No. 208 was removed as discussed in Section 3.3 of the safety evaluation.

On page 5 of Appendix C, the implementation date of "February 15, 2008" was removed.

3.4.2 Changes to BVPS-2 Ol Pages On pages 2 - 10, the words "Beaver Valley Unit 2" were added to the bottom of the left-hand corner of the pages.

On page 4 of the Ol, the amendment number was changed to "171" in section C.(2).

On page 8 of the Ol, section 0.(3) was removed because the exemption to 10 CFR 70.24 was no longer required.

The title page for Appendix B was given the number B-i.

At the top of the table of contents page for Appendix B, the words "To Facility Operating License No. NPF-73" were added. Page number B-ii was added and the page numbers were revised for each section listed on the page.

Pages 1 - 5 of Appendix B were renumbered as B-1, B-2, B-3, B-4, and B-5.

On pages B-i, B-ii, B-1, B-2, B-3, B-4, and B-5, the words "Beaver Valley Unit 2" were added to the bottom of the left-hand corner of the pages.

On pages 2 and 3 of Appendix B, "NPF-73" was removed from the top of the page.

- 6 Also, the words "Beaver Valley Unit 2" were added to the bottom of the left-hand corner of the page.

On page 5 of Appendix D, the implementation date of "February 15, 2008" was removed.

All of these changes are administrative in nature, and therefore, the NRC staff finds the changes to be acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (74 FR 66385). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: M. Barry A. Lewin A. Obodoako Date: May 20, 2010

May 20,2010 Mr. Paul A. Harden 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, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: SPRAY ELIMINATION OF RECIRCULATION SPRAY PUMP RESPONSE TIME SURVELLIENCE REQUIREMENT (TAC NOS.

ME1501 AND ME1502)

Dear Mr. Harden:

The Commission has issued the enclosed Amendment No. 285 to Renewed Facility Operating License 1\\10. DPR-66 for the Beaver Valley Power Station, Unit NO.1 (BVPS-1) and Amendment No. 171 to Renewed Facility Operating License No. NPF-73 for the Beaver Valley Power Station, Unit NO.2 (BVPS-2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated June 11, 2009.

These amendments revise TSs to eliminate Surveillance Requirement (SR) 3.3.2.9, Verification of Engineered Safety Function Actuation System Response Times, for the recirculation spray pumps. TS 1.4 is revised to add clarification to Notes associated with SR in accordance with Technical Specification Task Force Traveler, TSTF-475-A, Revision 1, "Control Rod Notch Testing Frequency and SRM [source range monitor] Insert Control Rod Action." The amendment also revises the BVPS-1 operating license to remove a License Condition for recommended inspections of steam generator repairs, and makes several editorial changes to the BVPS-1 and 2 operating license pages.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Ira!

Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412

Enclosures:

1. Amendment No. 285 to DPR-66

2. Amendment No. 171 to NPF-73

3. Safety Evaluation cc w/encls: Distribution via Listserv N

npu receive N

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Amendment 0.: ML101120926

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MSpencer NSalgado DATE 5/6/10 5/3/10 1211/2009 31412010 8/12/2009 5/12/10 5/19/10 OFFICIAL RECORD COPY