ML15054A066

Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Conforming Amendment Indirect Transfer of Renewed Facility Operating Licenses to Susquehanna Nuclear, LLC (TAC Nos. MF4426 and MF4427)

ML15054A066
Person / Time
Site:	Susquehanna
Issue date:	06/01/2015
From:	Whited J A Plant Licensing Branch II
To:	Rausch T S Susquehanna
Whited J A, NRR/DORL/LPL2-1, 415-4090
References
TAC MF4426, TAC MF4427
Download: ML15054A066 (45)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 .June 1 , 2015 Mr. Timothy S. Rausch, Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467 SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -ISSUANCE OF CONFORMING AMENDMENT RE: INDIRECT TRANSFER OF RENEWED FACILITY OPERATING LICENSES TO SUSQUEHANNA NUCLEAR, LLC (TAC NOS. MF4426 AND MF4427) Dear Mr. Rausch: By Order dated April 10, 2015, the Nuclear Regulatory Commission (NRC or Commission) approved an indirect license transfer from PPL Corporation to Talen Energy Corporation for Renewed Facility Operating Licenses NPF-14 and NPF-22 for the Susquehanna Steam Electric Station. Units 1 and 2 (SSES), and approved a conforming amendment, pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Sections 50.80 and 50.90 to reflect the change in name of PPL Susquehanna, LLC, to Susquehanna Nuclear, LLC (the licensee). The Order was published in the Federal Register on April 20, 2015 (80 FR 21767). By letter dated May 1, 2015, the licensee notified the NRC of the June 1, 2015, closing date for the license transfer. Accordingly, the Commission has issued the enclosed Amendment Nos. 262 and 243 to Renewed Facility Operating Licenses NPF-14 and NPF-22, respectively, for SSES (Enclosures 1 and 2). This conforming amendment reflects the indirect transfer of the licenses to Talen Energy Corporation and the name change of the licensee. The safety evaluation (SE) supporting the conforming amendment was enclosed with the Order issued on April 10, 2015. Enclosure 3 contains 2 signed originals of Amendment No. 6 to Indemnity Agreement No. B-90, which is required because of the licensee's name change, in connection with the indirect transfer of the licenses. Please sign both copies and keep 1 of these originals for your records. Please send 1 original to the NRC's document control desk for proof of acceptance.

T. Rausch -2 -Notice of Issuance will be included in the Commission's next regular Biweekly Federal Register Notice. Docket Nos. 50-387 and 50-388 Enclosures: 1. Amendment No. 262 to Renewed License No. NPF-14 2. Amendment No. 243 to Renewed License No. NPF-22 3. Amendment No. 6 to Indemnity Agreement No. B-90 cc w/encls: Distribution via Listserv Sincerely, Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC. DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 262 Renewed License No. NPF-14 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for the amendment filed by PPL Susquehanna, LLC, dated July 11, 2014, as supplemented by letters dated October 24, 2014, November 6, 2014, November 25, 2014, December 10, 2014, January 5, 2015, January 13, 2015, March 9, 2015, March 13, 2015, March 18, 2015, March 31, 2015, April 24, 2015, and May 1, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the renewed license is amended as indicated in the attachment to this license amendment. Enclosure 1

-2-3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance. Attachment: FOR THE NUCLEAR REGULATORY COMMISSION A. Louise Lund, Acting Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed Facility Operating License, the Environmental Protection Plan and the Additional Conditions Date of Issuance: June 1 , 2015 ATTACHMENT TO LICENSE AMENDMENT NO. 262 RENEWED FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 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 Page 1 Page 1 Page 2 Page 2 Page 3 Page 3 Page 4 Page 4 Page 5 Page 5 Page 13 Page 13 Page 14 Page 14 Page 15 Page 15 Page 16 Page 16 Page 17 Page 17 Page 18 Page 18 Page 19 Page 19 Page 20 Page 20 Replace the following page of the Appendix B, Environmental Protection Plan, with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change. REMOVE INSERT Page 1 of 1 Page 1 of 1 Replace the following pages of the 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 Page 1 of 2 Page 2 of 2 INSERT Page 1 of 2 Page 2 of 2 Susquehanna Nuclear, LLC Allegheny Electric Cooperative, Inc. Docket No. 50-387 Susquehanna Steam Electric Station. Unit 1 Renewed Facility Operating License 1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that: A. The application for a renewed license filed by the operating licensee and the Allegheny Electric Cooperative, Inc. (the licensees)# complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B. Construction of the Susquehanna Steam Electric Station, Unit 1 (the facility), has been substantially completed in conformity with Construction Permit CPPR-101 and the application, as amended, the provisions of the Act, and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; 0. There is reasonable assurance: (i) that the activities authorized by this operating license 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 set forth in 10 CFR Chapter I; E. Susquehanna Nuclear, LLC* is technically qualified to engage in the activities authorized by this 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 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; # The original applications for the operating license and construction permit were submitted by Pennsylvania Power & Light Company and Allegheny Electric Cooperative, Inc. The application for the renewed license was submitted by PPL Susquehanna, LLC and Allegheny Electric Cooperative, Inc. For purposes of certain historical references contained herein, the term "operating licensee" is used to refer to Susquehanna Nuclear, LLC as well as Pennsylvania Power & Light Company, PP&L, Inc and PPL Susquehanna, LLC, all three of which were previously named in the license with authority to operate the facility. Susquehanna Nuclear, LLC is authorized to act as agent for the Allegheny Electric Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility. Renewed Operating License No. NPF-14 Amendment No. 262

-2 -G. The issuance of this 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. NPF-14 subject to the condition for protection of the environment set forth herein, 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; and J. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1); 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 the 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. NPF-14 is hereby issued to the Susquehanna Nuclear, LLC and the Allegheny Electric Cooperative, Inc. to read as follows: A. This license applies to the Susquehanna Steam Electric Station, Unit 1, a boiling water nuclear reactor and associated equipment (the facility), owned by the licensees. The facility is located in Luzerne County, Pennsylvania, and is described in the licensees' Final Safety Analysis Report as supplemented and amended, and the licensees' 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, "Domestic Licensing of Production and Utilization Facilities," Susquehanna Nuclear, LLC and the Allegheny Electric Cooperative, Inc. to possess, and Susquehanna Nuclear, LLC to use, and operate the facility at the designated location in Luzerne County, Pennsylvania, in accordance with the procedures and limitations set forth in this renewed license; (2) Susquehanna Nuclear, LLC 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 Final Safety Analysis Report, as supplemented and amended; Renewed Operating License No. NPF-14 Amendment No. 262

-3-(3) Susquehanna Nuclear, LLC pursuant to the Act and 1 O 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 .neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Susquehanna Nuclear, LLC 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; and (5) Susquehanna Nuclear, LLC 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(36), 2.C.(37), 2.C.(38), and 2.C.(39) to this license shall be completed as specified. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 262 and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178. Renewed Operating License No. NPF-14 Amendment No. 262

-4 -(3) Conduct of Work Activities During Fuel Load and Initial Startup The operating licensee shall review by committee all facility construction, Preoperational Testing, and System Demonstration activities performed concurrently with facility initial fuel loading or with the facility Startup Test Program to assure that the activity will not affect the safe performance of the facility fuel loading or the portion of the facility Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security and health physics, with respect to performance of the activity concurrently with the facility fuel loading or the portion of the facility Startup Program being performed. The committee for the review shall be composed of a least three members, knowledgeable in the above areas, and who meet the qualifications for professional-technical personnel specified by section 4.4 of ANSI N18.7-1971. At least one of these three shall be a senior member of the Assistant Superintendent of Plant's staff. (4) Thermal and Hydraulic Design (Section 4.4, SER) (a) Susquehanna Nuclear, LLC is prohibited from power operation under natural circulation conditions. (5) Qualification of Purge Valves Whenever the operational condition is other than cold shutdown or refueling, the operating licensee shall maintain each containment purge and vent isolation valve greater than 2-in. nominal diameter in one of the following conditions: (a) Closed and electrically prohibited from opening, (b) Blocked so as not to permit opening by more than 50 degrees, or (c) Operated to permit opening by more than 50 degrees after demonstrating that the valves are qualified to close from the full open position against peak LOCA pressure, and are also qualified per the criteria of Branch Technical Position CSB 6-4. Purge valve qualification documentation must be approved by the NRC prior to operating valves in this mode. (6) Susquehanna Nuclear, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Review Report for the facility and as approved in Fire Protection Program, Section 9.5, SER, SSER#1, SSER#2, SSER#3, SSER#4, SSER#6, Safety Evaluation of Fire Protection Report dated August 9, 1989, Safety Evaluation of Revision 4 to the Fire Protection Review Report dated March 29, 1993, Safety Evaluation of Fire Protection Program Issues, Safe Shutdown Methodology and Analysis of Associated Circuits dated October 21, 1997, and Safety Evaluation of the licensee's Amendment No. 177, dated June 24, 1998, to relocate the Fire Protection Program subject to the following provision: Renewed Operating License No. NPF-14 Amendment No. 262

-5-The operating licensee 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. (7) Battery Room Area (Section 9.5.4, SER. SSER#1. SSER#3) Prior to exceeding five percent of full power and subject to NRC review and approval, the operating licensee shall either conduct at an approved testing laboratory an ASTM E-119 test of the as-installed one-hour cable wrap configuration or install an automatic fire extinguishing system. (8) Operation with Partial Feedwater Heating at End-of-Cycle (Section 15.1. SER. SSER#1) Prior to operation with partial feedwater heating, Susquehanna Nuclear, LLC shall provide for NRC review and approval, analyses which show a more limiting change does not occur in the minimum critical power ratio than that obtained using normal feedwater heating. (9) Initial Test Program (Section 14. SER. SSER#1) The operating licensee shall conduct the post-fuel-loading initial test program (set forth in Section 14 of the licensee's Final Safety Analysis Report, as amended through Amendment 50 and modified by the operating licensee's letter dated August 26, 1982, (PLA-1257)) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as: (a) Elimination of any test identified as essential in Section 14 of the licensees' Final Safety Analysis Report, as amended through Amendment 50 and modified by The operating licensee's letter dated August 26, 1982, (PLA-1257); (b) Modifications of test objectives, methods or acceptance criteria for any test identified as essential in Section 14 of the licensee's Final Safety Analysis Report, as amended through Amendment 50 and modified by the operating licensee's letter dated August 26, 1982, (PLA-1257); (c) Performance of any test at a power level different from that described in the program; and (d) Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized power level). Renewed Operating License No. NPF-14 Amendment No. 262

-13 -or outside containment, are dynamically qualified or the operating licensee shall provide a basis for continued operation and a program for qualifying such valves. (31) Control Room Design Review (Section 22. SSER #4) Prior to startup following the first refueling outage, the operating licensee shall provide a report discussing the experience, including demonstrated reliability, of the Display Control System. (32) Emergency Service Water System (Section 6.3.4. SSER #4) Prior to startup following the first refueling outage, the operating licensee shall complete design modifications to the emergency service water (ESW) system, approved by the staff, to eliminate single failure in the ESW system which leads to the need for an uncooled residual heat removal (RHR) pump. (33) The Additional Conditions contained in Appendix C, as revised through Amendment No. 262, are hereby incorporated into this license. The operating licensee shall operate the facility in accordance with the Additional Conditions. (34) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions that include the following key areas: (a) Fire fighting response strategy with the followirg 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 Renewed Operating License No. NPF-14 Amendment No. 262

-14 -(35) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate. (36) Potential Adverse Flow Effects These license conditions provide for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power up-ate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer). (a) The following requirements are placed on operation of Susquehanna SES, Unit 1 above the licensed thermal power (CL TP) level of 3489 megawatts thermal (MWt): (1) The operating licensee shall obtain at each 3.5% power ascension step up to 107% of 3489 MWt, dryer strain gauge data and compare it to the acceptance criteria during power ascension above 3489 MWt. The operating licensee shall obtain at each 3.5% power ascension step above 107% of 3489 MWt, main steam line strain gauge data and compare it to the limit curve for the dryer strains during povver ascension. (2) The operating licensee shall monitor the main steam line (MSL) strain gauges during power ascension testing above 3489 MWt for increasing pressure fluctuations in the steam lines. (3) The operating licensee shall hold the facility at each 3.5% ascension step to collect data from License Condition 2.C.(36)(a) and conduct plant inspections and walk-downs, and evaluate steam dryer performance based on the data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC project manager confirms receipt of the transmission. (4) If any steam dryer strains at each 3.5% power ascension step up to 107% of 3489 MWt or frequency peak from the MSL strain gauge data exceeds the level 1 limit curve for the MSL strains above 107% of 3489 MWt, the operating licensee shall return the facility to a power level at which the acceptance criteria is not exceeded. The operating licensee shall resolve the discrepancy, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power. Renewed Operating License No. NPF-14 Amendment No. 262

-15 -(5) In addition to evaluating the dryer instrumentation data and MSL strain gauge data, the operating licensee shall monitor reactor pressure vessel water level instrumentation and MSL piping accelerometers during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, the operating licensee shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power. (6) Following CPPU start-up testing, the operating licensee shall resolve any discrepancies in the steam dryer analysis and provide that resolution to the NRC staff by facsimile or electronic transmission to the NRC project manager. If the discrepancies are not resolved within 90 days of identification, the operating licensee shall return the facility to a power level at which the discrepancy does not exist. (b) The operating licensee shall implement the following actions: (1) The operating licensee shall provide to NRC the as-built dryer stress reconciliation and load limit curves 45 days prior to operation above 3489 MWt. (2) After the dryer stress analysis is benchmarked to the Unit 1 startup test data (Unit 1 data taken up to 107 % of 3489 MWt), the benchmark results and updated MSL limit curves shall be provided to the NRC 90 days prior to operation above 107% of 3489 MWt. (3) In the event that acoustic signals are identified that challenge the limit curve during power ascension above 107%, the operating licensee shall evak.Jate dryer loads and re-establish the acceptance criteria based on the new data, and shall perform an assessment of ACM uncertainty at the acoustic signal frequency. (4) After reaching 107% of CL TP, the operating licensee shall obtain measurements from the steam dryer instrumentation and establish the steam dryer flow-induced vibration load titigue margin for the facility, update the dryer stress report, and re-establish the limit curve with the updated ACM load definition and revised instrument uncertainty, which will be provided to the NRC staff. (5) During power ascension above 107 % CLTP, if an engineering evaluation for the steam dryer is required because a Level 1 acceptance criteria is exceeded, the operating licensee shall perform the structural analysis to address frequency uncertainties up to +/-10 % and assure that peak responses that fall within this uncertainty band are addressed. Renewed Operating License No. NPF-14 Amendment No. 262

-16 -(6) The operating licensee shall revise the Post Constant Pressure Power Uprate (CPPU) Monitoring & Inspection Program to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facility's steam dryer inspection program with General Electric Service Information Letter (SIL) 644, "BWR/3 Steam Dryer Failure," Revision 2; and to identify the NRC Project Manager for the facility as the point of contact for providing Power Ascension Test Plan (PATP) information during power ascension. (7) The operating licensee shall submit CPPU steam dryer reports to the NRC. Two written reports will be provided to the NRC. These reports will be issued follo\Ning completion of testing of Unit 1 power ascension to 107% CLTP and 114% CLTP. Each report will include evaluations or corrective actions that were required to assure steam dryer structural integrity. Additionally, they will include relevant data collected at each power step, comparisons to performance criteria (design predictions), and evaluations performed in conjunction with steam dryer structural integrity monitoring. (8) The operating licensee shall submit the flow-induced vibration related portions of the CPPU startup test procedure to the NRC, including methodology for updating the limit curve, prior to initial power ascension above 3489 Mvvt. (c) The operating licensee shall prepare the CPPU startup test procedure to include the: (1) steam dryer strain gauge acceptance criteria to be used up to 107% of CL TP and the main steam line strain gauge limit curves to be applied for evaluating steam dryer performance above 107% CL TP; (2) specific hold points and their duration during CPPU power ascension; (3) activities to be accomplished during hold points; (4) plant parameters to be monitored; (5) inspections and walk-downs to be conducted for steam, feedwater, and condensate systems and components during the hold points; (6) methods to be used to trend plant parameters; (7) acceptance criteria for monitoring and trending plant parameters, and conducting the walk-downs and inspections; (8) actions to be taken if acceptance criteria are not satisfied; and Renewed Operating License No. NPF-14 Amendment No. 262

-17 -(9) verification of the completion of commitments and planned actions specified in its application and all supplements to the application in support of the CPPU license amendment request pertaining to the steam dryer prior to power increase above 3489 Mwt. The operating licensee shall provide the related CPPU startup test procedure sections to the NRC by facsimile or electronic transmission to the NRC project manager prior to increasing power above 3489 MWt. ( d) The following key attributes of the PA TP shall not be made less restrictive without prior NRC approval: (1) During initial power ascension testing above 3489 MWt, each test plateau increment shall be approximately 3.5% of 3489 MWt; (2) Level 1 performance criteria; and (3) The methodology for establishing the stress criteria used for the Level 1 and Level 2 performance criteria. Changes to other aspects of the PATP may be made in accordance with the guidance of Nuclear Energy Institute (NEI) 99-04, "Guidelines for Managing NRC Commitments," issued July 1999. (e) During each scheduled refueling outage until at least two full operating cycles at full CPPU conditions have been achieved, a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer in accordance with BVVRVIP-139 and General Electric inspection guidelines. (f) The results of the visual inspections of the steam dryer shall be reported to the NRC staff within 60 days following startup. The results of the PATP shall be submitted to the NRC staff in a report within 60 days following the completion of all CPPU power ascension testing. (g) This license condition shall expire upon satisfaction of the requirements in License Conditions 2.C.(36)(e) and 2.C.(36)(f) provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is due to fatigue. (37) Transient Testing (a) The operating licensee will demonstrate through performance of transient testing on each SSES unit that the loss of one condensate pump will not result in a complete loss of reactor feedwater. The test shall be performed on each unit during the unifs CPPU power ascension test program within 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> of achieving and prior to exceeding a nominal power level of 3733 MWt with feedwater and condensate flow rates stabilized. The operating licensee shall confirm that the plant response to the transient is as expected in accordance with the acceptance criteria that are established. If a loss of all reactor feedwater occurs as a Renewed Operating License No. NPF-14 Amendment No. 262

-18-result of the test, the test failure shall be addressed in accordance with corrective action program requirements and the provisions of the power ascension test program prior to continued operation of the SSES Unit above 3489 MWt. (b) Unless the NRC issues a letter notifying the licensee that the tests specified by License Condition 2.C.(37)(a) adequately demonstrate that a single condensate pump trip will not result in a loss of all feedwater while operating at the full CPPU power level of 3952 MWt, the operating licensee shall perform the transient test on either SSES unit (whichever unit is first to achieve the following specified operating conditions) specified by License Condition 2.C.(37)(a) during the power ascension test program while operating at 3872 MWt to 3952 (98% to 100% of the full CPPU power level) with feedwater and condensate flow rates stabilized. The test shall be performed within 90 days of operating at greater than 3733 MWt and within 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> of achieving a nominal power level of 3872 MWt with feedwater and condensate flow rates stabilized. The operating licensee will demonstrate through performance of transient testing on either Susquehanna Unit 1 or Unit 2 (whichever unit is first to achieve the specified conditions) that the loss of one condensate pump will not result in a complete loss of reactor feedwater. The operating licensee shall confirm that the plant response to the transient is as expected in accordance with the acceptance criteria that are established. If a loss of all feedwater occurs as a result of the test, the test failure shall be addressed in accordance with corrective action program requirements and the provisions of the power ascension test program prior to continued operation of either SSES Unit above 3733 MWt. (38) Neutronic Methods (a) An OPRM amplitude setpoint penalty will be applied to account for a reduction in thermal neutrons around the LPRM detectors caused by transients that increase voiding. This penalty will reduce the OPRM scram setpoint according to the methodology described in Response No. 3 of the operating licensee's letter, PLA-6306, dated November 30, 2007. This penalty will be applied until NRC evaluation determines that a penalty to account for this phenomenon is not warranted. (b) For SSES SLMCPR, a conservatively adjusted pin power distribution uncertainty and bundle power correlation roefficient will be applied as stated in Response No. 4 of the operating licensee's letter, PLA-6306, dated November 30, 2007, when performing the analyses in accordance with ANF-524(P)(A), "Critical Power Methodology for Boiling Water Reactors," using the uncertainty parameters associated with EMF-2158(P)(A) "Siemens Power Corporations Methodology for Boiling Water Reactors: Evaluation and Validation of CASM0-4/MICROBURN-B2. II Renewed Operating License No. NPF-14 Amendment No. 262

-19 -(39) Containment Operability for EPU The operating licensee shall ensure that the CPPU containment analysis is consistent with the SSES 1 and 2 operating and emergency procedures. Prior to operation above CL TP, for each respective unit, the operating licensee shall notify the NRC project manager that all appropriate actions have been completed. (40) Primarv Containment Leakage Rate Testing Program Those primary containment local leak rate program tests (Type B -boundary and Type C -containment isolation val\es) as modified by approved exemptions, required by 10 CFR Part 50, AppendixJ, Option B and Technical Specification 5.5.12, are not required to be performed at the CPPU peak calculated containment internal pressure of 48.6 psig (Amendment No. 246 to this Operating License) until their next required performance. D. The operating licensee 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 of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and Security and Contingency Plan for Independent Spent Fuel Storage Facility," and was submitted October 8, 2004. The operating licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Susquehanna Nuclear, LLC CSP was approved by License Amendment No. 258. E. Exemptions from certain requirements of Appendices G and H to 10 CFR Part 50 are described in the Safety Evaluation Report and Supplements 1 and 2 to the Safety Evaluation Report. In addition, an exemption was requested until receipt of new fuel for first refueling from the requirements for criticality monitors in the spent fuel pool area, 1 O CFR Part 70.24. Also, an exemption was requested from the requirements of Appendix J of 1 O CFR Part 50 for the first fuel cycle when performing local leak rate testing of Residual Heat Removal (RHR) relief valves in accordance with Technical Specification 4.6.1.2. This latter exemption is described in the safety evaluation of License Amendment No. 13. These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest and have been granted pursuant to 1OCFR50.12. Except as here exempted, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, and the rules and regulations of the Commission and the provisions of the Act. Renewed Operating License No. NPF-14 Amendment -268, 262 Corrected by letter dated July 28, 2011

-20 -F. This license is subject to the following additional condition for the protection of the environment: Before engaging in additional construction or operational activities which may result in a significant adverse environmental impact that was not evaluated or that is significantly greater than that evaluated in the Final Environmental Statement and its Addendum, Susquehanna Nuclear, LLC shall provide a written notification to the Director of the Office of Nuclear Reactor Regulation and receive written approval from that office before proceeding with such activities. G. DELETED H. Susquehanna Nuclear, LLC 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 daims. I. In accordance with the Commission's direction in its Statement of Policy, Licensing and Regulatory Policy and Procedures for Environmental Protection; Uranium Fuel Cycle Impacts, October 29, 1982, this license is subject to the final resolution of the pending litigation involving Table S-3. See, Natural Resources Defense Council v. NRC, No. 74-1586 (April 27, 1982). J. The information in the Updated Final Safety Analysis Report (USFAR) supplement, as revised, submitted pursuant to 10 CFR 54.21(d}, shall be incorporated into the UFSAR no later than the next scheduled update required by 10 CFR 50. 71 (e) following the issuance of this renewed operating license. Until this update is complete, the operating licensee 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. The USFAR 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. The licensee shall complete these activities in accordance with Appendix A of NUREG-1931, "Safety Evaluation Report Related to the Susquehanna Steam Electric Station, Units 1 and 2," dated November, 2009. The licensee 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. L. All capsules in the reactor vessel that are removed and tested must meet the 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 withdraw schedule, including spare capsules, must be approved by the staff prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the staff, as required by 10 CFR Part 50, Appendix H. Renewed Operating License No. NPF-14 Amendment No. 26&, 262 Corrected by letter dated July 28, 2011 APPENDIXB TO FACILITY OPERATING LICENSE NO. NPF-14 SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 Susquehanna Nuclear, LLC DOCKET NOS. 50-387 AND 50-388 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL) July 17, 1982 Amendment No. 262 I Page 1 of 1 Amendment 178 188 188 188 AppendixC Additional Conditions Facility Operating License No. NPF-14 Docket No. 50-387 Additional Conditions The operating licensee is authorized to relocate certain requirements included in Appendix A to operating licensee-controlled documents. Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the operating licensee's letters dated August 1, 1996, as supplemented by letters dated November 26, 1997, January 6, March 2, April 24, and June 18, 1998, evaluated in the NRC staff's Safety Evaluation enclosed with this amendment. Deleted Deleted Deleted Susquehanna Nuclear, LLC shall not take any action that would cause Talen Energy Corporation or any other direct or indirect parent of Susquehanna Nuclear, LLC or other entity, to void, cancel, or diminish the commitment to fund an extended plant shutdown, as represented in the application for approval of the indirect transfer of the license for Susquehanna SES, Unit 1. The decommissioning trust agreement for Susquehanna SES, Unit 1, is subject to the following: a) The trust agreement must be in a form acceptable to the NRC. b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Talen Energy Corporation or its affiliates, successors, or assigns shall be prohibited. Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited. c) The decommissioning trust agreement for Susquehanna SES, Unit 1, must provide that Implementation Date This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment. Dated: July 30, 1998 This amendment shall be issued and made effective at the time the indirect transfer of control to Talen Energy is completed and shall be implemented within 30 days of issuance. This amendment shall be issued and made effective at the time the indirect transfer of control to Talen Energy is completed and shall be implemented within 30 days of issuance. Amendment No. 262 Page 1of2 Amendment d) e) Additional Conditions no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the NRC 30-days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation. The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30-days prior written notification to the Director, Office of Nuclear Reactor Regulation. The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations. Implementation Date Amendment No. 262 Page 2 of 2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC. DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. NPF-22 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that: A. The application for the amendment filed by PPL Susquehanna, LLC, dated July 11, 2014, as supplemented by letters dated October 24, 2014, November 6, 2014, November 25, 2014, December 10, 2014, January 5, 2015, January 13, 2015, March 9, 2015, March 13, 2015, March 18, 2015, March 31, 2015, April 24, 2015, and May 1, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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. Accordingly, the renewed license is amended as indicated in the attachment to this license amendment. Enclosure 2

-2 -3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance. Attachment: FOR THE NUCLEAR REGULATORY COMMISSION A. Louise Lund, Acting Director Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Changes to the Renewed Facility Operating License, the Environmental Protection Plan and the Additional Conditions Date of Issuance: June 1 , 2015 ATTACHMENT TO LICENSE AMENDMENT NO. 243 RENEWED FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 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 Page 1 Page 1 Page 2 Page 2 Page 3 Page 3 Page4 Page4 Page 8 Page 8 Page 9 Page 9 Page 10 Page 10 Page 11 Page 11 Page 12 Page 12 Page 13 Page 13 Page 14 Page 14 Page 15 Page 15 Replace the following page of the Appendix B, Environmental Protection Plan, with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the areas of change. REMOVE INSERT Page 1 of 1 Page 1 of 1 Replace the following pages of the 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 Page 1 of 2 Page 2 of 2 INSERT Page 1 of 2 Page 2 of 2 Susquehanna Nuclear. LLC Allegheny Electric Cooperative. Inc. Docket No. 50-388 Susquehanna Steam Electric Station. Unit 2 Renewed Facility Operating License 1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that: A. The application for a renewed lirense filed by the operating licensee and the Allegheny Electric Cooperative, Inc. (the licensees)# complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B. Construction of the Susquehanna Steam Electric Station, Unit 2 (the facility), has been substantially completed in conformity with Construction Permit No. CPPR-102 and the application, as amended, the provisions of the Act, and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license 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 set forth in 10 CFR Chapter I; E. Susquehanna Nuclear, LLC* is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 1 O CFR Chapter I; F. The licensees have satisfied the applicable provisions of 10 CFR 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; #The original applications for the operating license and construction permit were submitted by Pennsylvania Power & Light Company and Allegheny Electric Cooperative, Inc. The application for the renewed license was submitted by PPL Susquehanna, LLC and Allegheny Electric Cooperative, Inc. For purposes of certain historical references contained herein, the term "operating licensee" is used to refer to Susquehanna Nuclear, LLC, as well as Pennsylvania Power & Light Company, PP&L, Inc. and PPL Susquehanna, LLC, all three of which were previously named in the license with authority to operate the facility. Susquehanna Nuclear, LLC is authorized to act as agent for the Allegheny Electric Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility. Renewed Operating License No. NPF-22 Amendment No. 243

-2 -G. The issuance of this 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. NPF-22 subject to the condition for protection of the environment set forth herein, is in accordance with 1 O 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; and J. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1); 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 the 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 1 O CFR 54.29(a) are in accordance with the Act and the Commission's regulations. 2. Renewed Facility Operating License No. NPF-22 is hereby issued to the Susquehanna Nuclear, LLC and the Allegheny Electric Cooperative, Inc. to read as follows: A. This license applies to the Susquehanna Steam Electric Station, Unit 2, a boiling water nuclear reactor and associated equipment (the facility}, owned by the licensees. The facility is located in Luzerne County, Pennsylvania, and is described in the licensees' Final Safety Analysis Report, as supplemented and amended, and the licensees' 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, "Domestic Licensing of Production and Utilization Facilities," Susquehanna Nuclear, LLC and the Allegheny Electric Cooperative, Inc. to possess, and Susquehanna Nuclear, LLC to use, and operate the facility at the designated location in Luzerne County, Pennsylvania, in accordance with the procedures and limitations set forth in this license; (2) Susquehanna Nuclear, LLC 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 Final Safety Analysis Report, as supplemented and amended; Renewed Operating License No. NPF-22 Amendment No. 243

-3 -(3) Susquehanna Nuclear, LLC 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 neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Susquehanna Nuclear, LLC 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; and (5) Susquehanna Nuclear, LLC 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational test, startup tests and other items identified in License Conditions 2.C.(20), 2.C.(21), 2.C.(22), and 2.C.(23) to this license shall be completed as specified. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 243, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 151. Renewed Operating License No. NPF-22 Amendment No. 244, 243

-4-(3) Susquehanna Nuclear, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Fire Protection Review Report for the facility and as approved in Fire Protection Program, Section 9.5, SER, SSER#1, SSER#2, SSER#3, SSER#4, SSER#6, Safety Evaluation of Fire Protection dated August 9, 1989, Safety Evaluation of Revision 4 to the Fire Protection Review Report dated March 29, 1993, Safety Evaluation of Fire Protection Program Issues, Safe Shutdown Methodology and Analysis of Associated Circuits dated October 21, 1997, and Safety Evaluation of the licensee's Amendment No. 150, dated June 24, 1998, to relocate the Fire Protection Program subject to the following provision: The operating licensee 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. (4) Operation with Partial Feedwater Heating at End-of-Cycle (Section 15.1 SER, SSER#1) Susquehanna Nuclear, LLC shall not operate with partial feedwater heating for the purpose of extending the normal fuel cycle unless acceptable justification is provided to and approved by the NRC staff prior to such operation. (5) Initial Test Program (Section 14. SER, SSER #1) The operating licensee shall conduct the post-fuel-loading initial test program described in Section 14 of the Final Safety Analysis Report, as amended without making any major modifications unless such modifications have prior NRC approval. Major modifications are defined as: (a) Elimination of any safety-related test;"-(b) Modifications of objective, test methods or acceptance criteria for any safety-related test; (c) Performance of any safety-related test at a power level different from that stated in the licensees' Final Safety Analysis Report by more than 5 percent of rated power; (d) Failure to satisfactorily complete the entire test program by the time core burnup equals 120 effective full power days; Safety-related tests are those tests which verify the design, construction, and operation of safety-related systems, structures, and equipment. Renewed Operating License No. NPF-22 Amendment No. 243

-8-(ii) Propose Technical Specifications for the bypass timer setting and surveillance requirements for the bypass timer. (2) Prior to September 1, 1985, the operating licensee shall: (i) Incorporate into the Plant Emergency Procedures the usage of the manual inhibit swrrch, and (ii) Propose the Technical Specifications for the manual inhibit swrrch. (3) The operating licensee shall maintain the manual inhibit switch disabled until license condition 2.C.(12) (f) (2) above is satisfied. (13) Emergency Service Water System (Section 9.2.1. SSER #6) Prior to September 1, 1985, the operating licensee shall complete modifications to the emergency service water (ESW) system described in the operating licensee's letter dated May 16, 1983. (14) Control of Heavy Loads (Section 9.1.4. SSER#6) DELETED (15) Radon (ASLB Initial Decision. Paragraph 223) This license will be subject to the ultimate outcome of the consolidated radon proceeding currently underway in Docket Nos. 50-277, 50-278, 50-320, 50-354 and 50-355. (16) Formal Federal Emergency Management Agency Finding In the event the NRG finds that lack of progress in completion of procedures in Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that major substantial problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply. (17) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 243, are hereby incorporated into this license. The operating licensee shall operate the facility in accordance with the Additional Conditions. (18) Mitigation Strategy License Condition Renewed Operating License No. NPF-22 Amendment No. 243

-9-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 (19) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate. (20) Potential Adverse Flow Effects These license conditions provide for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer). (a) The following requirements are placed on operation of Susquehanna SES, Unit 2 above the licensed thermal power (CL TP) level of 3489 megawatts thermal (MWt): (1) The operating licensee shall obtain at each 3.5% power ascension step, main steam line strain gauge data and compare it to the limit curve for the dryer strains during power ascension. (2) The operating licensee shall monitor the main steam line (MSL) strain gauges during power ascension above 3489 MWt for increasing pressure fluctuations in the steam lines. Renewed Operating License No. NPF-22 Amendment No. 243

-10-(3) The operating licensee shall hold the facility at each 3.5% ascension step to collect data from License Condition 2.C.(20)(a) and conduct plant inspections and walk-downs, and evaluate steam dryer performance based on the data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC project manager confirms receipt of transmission. (4) If any frequency peak from the MSL strain gauge data exceeds the 1 limit curve for dryer strains above 3489 MWt, the operating licensee shall return the facility to a power level at which the acceptance criteria is not exceeded. The operating licensee shall resolve the discrepancy, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power. (5) In addition to evaluating the dryer strain and MSL strain gauge data, the operating licensee shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, the operating licensee shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power. (6) Following CPPU start-up testing, the operating licensee shall resolve the discrepancies in the steam dryer analysis and provide that resolution to the NRC staff by facsimile or electronic transmission to the NRC project manager. If the discrepancies are not resolved within 90 days of identification, the operating licensee shall return the facility to a power level at which the discrepancy does not exist. (b) The operating licensee shall implement the following actions: (1) The operating licensee shall provide to NRC the as-built dryer stress analysis and load lmit curves 45 days prior to operation above 3489 MWt. (2) After the dryer stress analysis is benchmarked to the Unit 1 startup test data (Unit 1 data taken up to 107 % of 3489 MWt), the benchmarked PATP and MSL limit curves shall be provided to the NRC 90 days prior to operation above 107% of 3489 MWt. Renewed Operating License No. NPF-22 Amendment No. 243

-11 -(3) In the event that acoustic signals are identified that challenge the limit curves during power ascension above 3489 MWt, the operating licensee shall evaluate dryer loads and re-establish the acceptance criteria based on the new data, and shall perform an assessment of ACM uncertainty at the acoustic signal frequency. (4) After reaching full CPPU, the operating licensee shall obtain measurements from the MSL strain gauges and establish the steam dryer flow-induced vibration load fctigue margin for the facility, update the dryer stress report, if required, and establish the limit curve with the updated ACM load definition and revised instrument uncertainty, which will be provided to the NRC staff. (5) During power ascension above 3489 MWt, if an engineering evaluation for the steam dryer is required because a Level 1 acceptance criteria is exceeded, the operating licensee shall perform the structural analysis to address frequency uncertainties up to +/-10% and assure that peak responses that fall within this uncertainty band are addressed. (6) The operating licensee shall revise the Post Constant Pressure Power Uprate (CPPU) Monitoring & Inspection Program to reflect long-term monitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facility's steam dryer inspection program with General Electric Service Information Letter (SIL) 644, "BWR/3 Steam Dryer Failure," Revision 2; and to identify the NRC Project Manager for the facility as the point of contact for providing PATP information during po111.er ascension. (7) The operating licensee shall submit a CPPU steam dryer report to the NRC. The report will be issued following completion of Unit 2 ascension to 114 % CLTP. The report shall indude evaluations or corrective actions that were required to assure steam dryer structural integrity. Additionally, it shall include relevant data collected at each power step, comparisons to performance criteria (design predictions}, and evaluations performed in conjunction with steam dryer structural integrity monitoring. (8) The operating licensee shall submit the flow-induced vibration related portions of the CPPU startup test procedure to the NRC, including methodology for updating the limit curve, prior to initial power ascension above 3489 MWt. (c) The operating licensee shall prepare the CPPU startup test procedure to include the: ( 1) main steam line strain gauge limit curves to be used up to 114% of CLTP; Renewed Operating License No. NPF-22 Amendment No. 243

-12 -(2) specific hold points and their duration during CPPU power ascension; (3) activities to be accomplished during hold points; (4) plant parameters to be monitored; (5) inspections and walk-downs to be conducted for steam, feedwater, and condensate systems and components during the hold points; (6) methods to be used to trend plant parameters; (7) acceptance criteria for monitoring and trending plant parameters, and conducting the walk-downs and inspections; (8) actions to be taken if acceptance criteria are not satisfied; and (9) verification of the completion of commitments and planned actions specified in its application and all supplements to the application in support of the CPPU license amendment request pertaining to the steam dryer prior to power increase above 3489 MWt. The operating licensee shall provide the related CPPU startup test procedure sections to the NRC by facsimile or electronic transmission to the NRC project manager prior to increasing power above 3489 Mwt. (d) The following key attributes of the PATP shall not be made less restrictive without prior NRC approval: (1) During initial power ascension testing above 3489 MWt, each test plateau increment shall be approximately 3.5 % of 3489 MWt; (2) Level 1 performance criteria; and (3) The methodology for establishing the stress criteria used for the Level 1 and Level 2 performance criteria. Changes to other aspects of the PATP may be made in accordance with the guidance of Nuclear Energy Institute (NEI) 99-04, "Guidelines for Managing NRC Commitments," issued July 1999. (e) During the first two scheduled refueling outages after reaching full CPPU conditions, a visual inspection shal be conducted of all accessible, susceptible locations of the steam dryer in accordance with BWRVIP-139 and General Electric inspection guidelines. Renewed Operating License No. NPF-22 Amendment No. 243

-13 -(f) The results of the visual inspections of the steam dryer shall be reported to the NRC staff within 60 days following startup. The results of the PATP shall be submitted to the NRC staff in a report within 60 days following the completion of all CPPU power ascension testing. (g} This license condition shall expire upon satisfaction of the requirements in License Conditions 2.C.(20)(e) and 2.C.(20)(f) provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is due to fatigue. (21) Transient Testing (a) The operating licensee will demonstrate through performance of transient testing on each SSES unit that the loss of one condensate pump will not result in a complete loss of reactor feedwater. The test shall be performed on each unit during the unit's CPPU power ascension test program within 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> of achieving and prior to exceeding a nominal power level of 3733 MWt with feedwater and condensate flow rates stabilized. The operating licensee shall confirm that the plant response to the transient is as expected in accordance with the acceptance criteria that are established. If a loss of all reactor feedwater occurs as a result of the test, the test failure shall be addressed in accordance with corrective action program requirements and the provisions of the power ascension test program prior to continued operation of the SSES Unit above 3489 MWt. (b) Unless the NRC issues a letter notifying the licensee that the tests specified by License Condition 2.C.(21 )(a) adequately demonstrate that a single condensate pump trip will not result in a loss of all feedwater while operating at the full CPPU power level of 3952 MWt, the operating licensee shall perform the transient test on either SSES unit (whichever unit is first to achieve the following specified operating conditions) specified by License Condition 2.C.(21)(a) during the power ascension test program while operating at 3872 MWt to 3952 (98% to 100% of the full CPPU power level) with feedwater and condensate flow rates stabilized. The test shall be performed within 90 days of operating at greater than 3733 MWt and within 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> of achieving a nominal power level of 3872 MWt with feedwater and condensate flow rates stabilized. The operating licensee will demonstrate through performance of transient testing on either Susquehanna Unit 1 or Unit 2 (whichever unit is first to achieve the specified conditions) that the loss of one condensate pump will not result in a complete loss of reactor feedwater. The operating licensee shall confirm that the plant response to the transient is as expected in accordance with the acceptance criteria that are established. If a loss of all feedwater occurs as a result of the test, the test failure shall be addressed in accordance with corrective action program requirements and the provisions of the power ascension test program prior to continued operation of either SSES Unit above 3733 MWt. Renewed Operating License No. NPF-22 Amendment No. 243

-14 -(22) Neutronic Methods (a) An OPRM amplitude setpoint penalty will be applied 1D account for a reduction in thermal neutrons around the LPRM detectors caused by transients that increase voiding. This penalty will reduce the OPRM scram setpoint according to the methodology described in Response No. 3 of the operating licensee's letter, PLA-6306, dated November 30, 2007. This penalty will be applied until NRC evaluation determines that a penalty to account for this phenomenon is not warranted. (b) For SSES SLMCPR, a conservatively adjusted pin power distribution uncertainty and bundle power correlation ooefficient will be applied as stated in Response No. 4 of the operating licensee's letter, PLA-6306, dated November 30, 2007, when performing the analyses in accordance with ANF-524(P)(A), "Critical Power Methodology for Boiling Water Reactors," using the uncertainty parameters associated with EMF-2158(P)(A) "Siemens Power Corporations Methodology for Boiling Water Reactors: Evaluation and Validation of CASM0-4/MICROBURN-B2." (23) Containment Operability for EPU The operating licensee shall ensure that the CPPU containment analysis is consistent with the SSES 1 and 2 operating and emergency procedures. Prior to operation above CL TP, for each respective unit, the operating licensee shall notify the NRC project manager that all approl'.J'iate actions have been completed. (24) Primary Containment Leakage Rate Testing Program Those primary containment local leak rate program tests (Type B -boundary and Type C -containment isolation valves) as modified by approved exemptions, required by 10 CFR Part 50, Appendix J, Option Band Technical Specification 5.5.12, are not required to be performed at the CPPU peak calculated containment internal pressure of 48.6 psig (Amendment No. 224 to this Operating License) until their next required performance. (25) Critical Power Correlation Additive Constants AREVA NP has submitted EMF-2209(P), Revision 2, Addendum 1 (ML081260442) for NRC review to correct the critical power correlation additive constants due to a prior Part 21 notification (ML072830334). The report is currently under NRC review. The license shall apply additional margin to the cycle specific OLMCPR, consistent in magnitude with the non-conservatism reported in the Part 21 report, thus imposing the appropriate MCPR penalty on the OLMCPR. This compensatory measure is to be applied until the approved version of Renewed Operating License No. NPF-22 Amendment No. 243

-15-EMF-2209(P), Revision 2, Addendum 1 is published and the operating licensee verifies that the additive constants from the approved report have been incorporated in the cycle specific analyses. D. The operating licensee 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 of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and Security and Contingency Plan for Independent Spent Fuel Storage Facility," and was sul:mitted October 8, 2004. The operating licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Susquehanna Nuclear, LLC CSP was approved by License Amendment No. 239. E. DELETED F. Susquehanna Nuclear, LLC 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. G. The information in the Updated Final Safety Analysis Report (UFSAR) supplement, as revised, submitted pursuant to 10 CFR 54.21(d), shall be incorporaed into the UFSAR no later than the next scheduled updae required by 1 O CFR 50.71 (e) following the issuance of this renewed operating license. Until this update is complete, the operating licensee 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. 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. The licensee shall complete these activities in accordance with Appendix A of NUREG-1931, "Safety Evaluation Report Related to the Susquehanna Steam Electric Station, Units 1 and 2," dated November, 2009. The licensee 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. I. All capsules in the reactor vessel that are removed and tested must meet the 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 staff prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the staff, as required by 10 CFR Part 50, Appendix H. Renewed Operating License No. NPF-22 Amendment No. 235-239-, 243 Corrected by letter dated July 28, 2011 APPENDIXB TO FACILITY OPERATING LICENSE NO. NPF-22 SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 Susquehanna Nuclear, LLC DOCKET NOS. 50-387 AND 50-388 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL) March, 1984 Amendment No. 243 I Page 1 of 1 Amendment Number 151 162 162 162 AppendixC Additional Conditions Facility Operating License No. NPF-22 Docket No. 50-388 Additional Conditions The operating licensee is authorized to relocate certain requirements included in Appendix A to operating licensee-controlled documents. Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the operating licensee's letters dated August 1, 1996, as supplemented by letters dated November 26, 1997, January 6, March 2, April 24, and June 18, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment. Deleted Deleted Deleted Susquehanna Nuclear, LLC shall not take any action that would cause Talen Energy Corporation or any other direct or indirect parent of Susquehanna Nuclear, LLC or other entity, to void, cancel, or diminish the commitment to fund an extended plant shutdown, as represented in the application for approval of the indirect transfer of the license for Susquehanna SES, Unit 2. The decommissioning trust agreement for Susquehanna SES, Unit 2, is subject to the following: a) The trust agreement must be in a form acceptable to the NRC. b) With respect to the decommissioning trust fund, investments in the securities or other obligations of T alen Energy Corporation or its affiliates, successors, or assigns shall be prohibited. Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity ownina one or more nuclear power plants Implementation Date This amendment is effective immediately and shall be implemented within 90 days of the date of this amendment. Dated: July 30, 1998 This amendment shall be issued and made effective a1 the time the indirect transfer of control to Talen Energy is completed and shall be implemented within 30 days of issuance. This amendment shall be issued and made effective a1 the time the indirect transfer of control to Talen Energy is completed and shall be implemented within 30 days of issuance. Amendment No. 243 Page 1of2 Amendment Number c) d) e) Additional Conditions are prohibited. The decommissioning trust agreement for Susquehanna SES, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the NRC 30-days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation. The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30-days prior written notification to the Director, Office of Nuclear Reactor Regulation. The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a "prudent investor" standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations. Implementation Date Amendment No. 243 Page 2 of 2 Enclosure 3 Amendment No. 6 to Indemnity Agreement No. B-90 Docket Nos. 50-387 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AMENDMENT TO INDEMNITY AGREEMENT NO. B-90 AMENDMENT NO. 6 Effective June 1, 2015, Indemnity Agreement No. B-90, between Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc., and the United States Nuclear Regulatory Commission, dated September 10, 1981, as amended, is hereby further amended as follows: The name "PPL Susquehanna, LLC" is deleted wherever it appears in the agreement and substituted in lieu thereof by the name: "Susquehanna Nuclear, LLC" Item 1 of the Attachment to the indemnity agreement is modified by deleting the name "PPL Susquehanna, LLC," wherever it appears in the agreement and substituted in lieu thereof by the name: Item 1 -Licensee Address Susquehanna Nuclear, LLC 835 Hamilton Street, Suite 150 Allentown, PA 18101-2426 In light of the above amendments, Indemnity Agreement No. B-90 is between Susquehanna Nuclear, LLC, Allegheny Electric Cooperative, Inc., and the United States Nuclear Regulatory Commission. Historical licensee name changes to the original indemnity agreement and attachments thereof were not previously recorded. Therefore, the following name changes are listed here as a matter of record: 1) Pennsylvania Power & Light Company changed to PP&L, Inc. on -September 12, 1997. 2) PP&L, Inc. changed to PPL Electric Utilities Corporation on February 14, 2000.

-2-3) PPL Electric Utilities Corporation changed to PPL Susquehanna, LLC on July 1, 2000. FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION Anthony Bowers, Chief Financial Analysis and International Projects Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation Accepted _________ 20_ Accepted _________ 20_ By _____________ _ By _____________ _ Susquehanna Nuclear, LLC Allegheny Electric Cooperative, Inc.

Docket Nos. 50-387 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AMENDMENT TO INDEMNITY AGREEMENT NO. 8-90 AMENDMENT NO. 6 Effective June 1, 2015, Indemnity Agreement No. 8-90, between Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc., and the United States Nuclear Regulatory Commission, dated September 10, 1981, as amended, is hereby further amended as follows: The name "PPL Susquehanna, LLC" is deleted wherever it appears in the agreement and substituted in lieu thereof by the name: "Susquehanna Nuclear, LLC" Item 1 of the Attachment to the indemnity agreement is modified by deleting the name "PPL Susquehanna, LLC," wherever it appears in the agreement and substituted in lieu thereof by the name: Item 1 -Licensee Address Susquehanna Nuclear, LLC 835 Hamilton Street, Suite 150 Allentown, PA 18101-2426 In light of the above amendments, Indemnity Agreement No. 8-90 is between Susquehanna Nuclear, LLC, Allegheny Electric Cooperative, Inc., and the United States Nuclear Regulatory Commission. Historical licensee name changes to the original indemnity agreement and attachments thereof were not previously recorded. Therefore, the following name changes are listed here as a matter of record: 1) Pennsylvania Power & Light Company changed to PP&L, Inc. on September 12, 1997. 2) PP&L, Inc. changed to PPL Electric Utilities Corporation on February 14, 2000.

-2-3) PPL Electric Utilities Corporation changed to PPL Susquehanna, LLC on July 1, 2000. FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION > Anthony Bowers, Chief Financial Analysis and International Projects Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation Accepted _________ 20_ Accepted _________ 20_ By _____________ _ By _____________ _ Susquehanna Nuclear, LLC Allegheny Electric Cooperative, Inc.

T. Rausch -2-Notice of Issuance will be included in the Commission's next regular Biweekly Federal Register Notice. Sincerely, IRA/ Jeffrey A. Whited, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 Enclosures: 1. Amendment No. 262 to Renewed License No. NPF-14 2. Amendment No. 243 to Renewed License No. NPF-22 3. Amendment No. 6 to Indemnity Agreement No. B-90 cc w/encls: Distribution via Listserv DISTRIBUTION: PUBLIC LPL 1-2 Reading File RidsNrrLAABaxter Resource RidsNrrDirslfib Resource RidsAcrsAcnwMailCenter Resource RidsSecyMailCenter Resource RidsNrrDorl LPL 1-2 Resource RidsNrrPMSusquehanna Resource RidsNrrOd Resource RidsNrrDoriDpr Resource D. Mcintyre, OPA N. Sheehan, R1 Package No.: ML 15057 A230 Amendment: ML 15054A066 OFFICE LPL 1-2/PM LPL 1-2/LA DIRS/IFIB/BC NAME JWhited ABaxter ABowers DATE 05/13/2015 05/13/2015 05/15/2015 OFFICE LPL 1-2/BC DORUD (A) LPL 1-2/PM NAME DBroaddus LLund JWhited (J. Lamb for) DATE 05/22/2015 06/01/2015 06/01/2015 OFFICIAL RECORD COPY RidsRgn1 MailCenter RidsOgcRp Resource RidsOpaMailCenter Resource R. Turtil, NRR S. Williams, EDO C. Parker, NRR OGC (NLO) SUttal (wt comment) 05/22/2015