ML061510097

FOL Pages Associated with License Transfer

ML061510097
Person / Time
Site:	Hope Creek
Issue date:	05/30/2006
From:	Harold Denton Office of Nuclear Reactor Regulation
To:	Exelon Generation Co
References
NUREG-1201
Download: ML061510097 (15)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-354 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE License No. ?PF-57 1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that: A. The application for a license 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 Hope Creek Generating Station (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-120 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 (except as exempted from compliance in Section 2.D. below);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 (except as exempted from compliance in Section 2.D.below);E. Exelon Generation Company, LLC (Exelon Generation Company) (the licensee) is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I;F. The licensee has 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 license will not be inimical to the common defense and security or to the health and safety of the public;Amendment No- 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 Facility Operating License No. NPF-57, 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; and 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 70.2. Based on the foregoing findings and approval by the Nuclear Regulatory Commission at a meeting on July 21, 1986, the License for Fuel Loading and Low Power Testing, License No. NPF-50, issued on April 11, 1986, is superseded by Facility Operating License NPF-57 hereby issued to Exelon Generation Company, LLC (Exelon Generation Company) (the licensee), to read as follows: A. This license applies to the Hope Creek Generating Station, a boiling water nuclear reactor, and associated equipment (the facility) owned by Exelon Generation Company. The facility is located on the licensee's site on the east bank of the Delaware River in Lower Alloways Creek Township, Salem County, New Jersey. The facility is located approximately eight miles southwest of Salem, New Jersey and is described in the Exelon Generation Company Final Safety Analysis Report, as supplemented and amended, and in the Environmental Report, as supplemented and amended.S. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses: (1) Exelon Generation Company, pursuant to Section 103 of the Act andi 10 CFR Part 50, to possess, use and operate the facility at the above designated location in Salem County, New Jersey, in accordance with the procedures and limitations set forth in this license;(2) Deleted (3) Exelon Generation Company, 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;Amendment No. (4) Exelon Generation Company, 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;(5) Exelon Generation Company, 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 (6) Exelon Generation Company, 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3339 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. , and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.(3) Inservice Testing of Pumps and Valves (Section 3.9.6, SSER No.4)*This License Condition was satisfied as documented in the letter from W. R. Butler (NRC) to C. A. McNeill, Jr. (PSE&G) dated December 7, 1987. Accordingly, this condition has been deleted.*The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment No. (4) Inservice Inspection (Section 6.6, SER; Sections 5.2.4.3 and 6.6.3, SSER No. 5)a. PSE&G shall submit an inservice inspection program in accordance with 10 CFR 50.55a(g)(4) for staff review by October 11, 1986.b. Pursuant to 10 CFR 50.55a(a)(3) and for the reasons set forth in Sections 5.2.4.3 and 6.6.3 of SSER No. 5, the relief identified in the PSE&G submittal dated November 18, 1985, as revised by the submittal dated January 20, 1986, requesting relief from certain requirements of 10 CFR 50.55a(g) for the preservice inspection program, is granted.(5) Solid State Logic Modules Exelon Generation Company shall continue, for the life of the plant, a reliability program to monitor the performance of the Bailey 862 SSLMs installed at Hope Creek Generating Station. This program should obtain reliability data, failure characteristics, and root cause of failure of both safety-related and non-safety-related Bailey 862 SSLMs. The results of the reliability program shall be maintained on-site and made available to the NRC upon request.(6) Fuel Storage and Handling (Section 9.1, SSER No. 5)a. No more than a total of three (3) fuel assemblies shall be out of approved shipping containers or fuel assembly storage racks or the reactor at any one time.b. The above three (3) fuel assemblies as a group shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and the storage rack array.c. Fresh Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three (3)containers high.(7) Fire Protection (Section 9.5.1.8, SSER No. 5; Section 9.5.1, SSER No. 6)Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment No. 15 and as described in its submittal dated May 13, 1986, and as approved in the SER dated October 1984 (and Supplements 1 through 6) subject to the following provision:

Exelon Generation Company 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. (8) Solid Waste Process Control Program (Section 11.4.2, SER;Section 11.4, SSER No. 4)Exelon Generation Company shall obtain NRC approval of the Class B and C solid waste process control program prior to processing Class B and C solid wastes.(9) Emergency Planning (Section 13.3, SSER No. 5)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.(10) Initial Startup Test Program (Section 14, SSER No. 5)Any changes to the Initial Startup Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.(11) Partial Feedwater Heating (Section 15.1, SER; Section 15.1, SSER No. 5; Section 15.1, SSER No. 6)The facility shall not be operated with reduced feedwater temperature for the purpose of extending the normal fuel cycle.After the first operating cycle, the facility shall not be operated with a feedwater heating capacity that would result in a rated power feedwater temperature less than 400'F unless analyses supporting such operation are submitted by the licensee and approved by the staff.(12) Detailed Control Room Design Review (Section 18.1, SSER No. 5)a. PSE&G shall submit for staff review Detailed Control Room Design Review Summary Reports II and III on a schedule consistent with, and with contents as specified in, its letter of January 9, 1986.b. Prior to exceeding five percent power, PSE&G shall provide temporary zone markings on safety-related instruments in the control room.Amendment No. (13) Safety Parameter Display System (Section 18.2, SSER No. 5)Prior to the earlier of 90 days after restart from the first refueling outage or July 12, 1988, PSE&G shall add the following parameters to the SPDS and have them operational:

a. Primary containment radiation b. Primary containment isolation status c. Combustible gas concentration in primary containment

d. Source range neutron flux (14) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. , are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Additional Conditions.

(15) At the time of the closing of the transfer of this license from PSEG Nuclear LLC, to Exelon Generation Company, PSEG Nuclear LLC shall transfer to Exelon Generation Company all of PSEG Nuclear LLC's decommissioning funds for Hope Creek Generating Station accumulated as of such time, and Exelon Generation Company shall deposit such funds in an external decommissioning trust established by Exelon Generation Company for Hope Creek Generating Station.Amendment No. D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the SER. This previously granted exemption is continued in this operating license. An exemption from certain requirements of Appendix A to 10 CFR Part 50, is described in Supplement No. 5 to the SER. This exemption is a schedular exemption to the requirements of General Design Criterion 64, permitting delaying functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent power for local indication, and until 120 days after fuel load for control room indication (Appendix R of SSER 5). Exemptions from certain requirements of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include an exemption from the requirement of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and an exemption from Appendix J, exempting Type C testing of thermal relief valves (Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security.

These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With 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.

Amendment No. E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard 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 plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

'Salem-Hope Creek Nuclear Generating Station Security Plan, with revisions submitted through December 17, 2001;"Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan, with revisions submitted through December 17, 2001; and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan," with revisions submitted through June 2, 1998.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Exelon Generation Company shall report any violations of the requirements contained in Section 2-C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).G. 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.H. This license is effective as of the date of issuance and shall expire at midnight on April 11, 2026.FOR THE NUCLEAR REGULATORY COMMISSION original signed by H.R. Denton Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Appendix A -Technical Specifications (NUREG-1201)

2. Appendix B -Environmental Protection Plan Date of Issuance:

July 25, 1986 Amendment No.

PLANT SYSTEMS ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.1.3 The ultimate heat sink (Delaware River) shall be OPERABLE with: a. A minimum river water level at or above elevation

-9'0 Mean Sea Level, USGS datum (80'0 Exelon Generation Company, LLC datum), and b. An average river water temperature of less than or equal to 85.OaF.APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *.ACTION: With the river water temperature in excess of 85.0OF, continued plant operation is permitted provided that both emergency discharge valves are open and emergency discharge pathways are available.

With the river water temperature in excess of 88.0 0 F, continued plant operation is permitted provided that all of the following additional conditions are satisfied:

ultimate heat sink temperature is at or below 89.0 0 F, all SSWS pumps are OPERABLE, all SACS pumps are OPERABLE, all EDGs are OPERABLE and the SACS loops have no cross-connected loads (unless they are automatically isolated during a LOP and/or LOCA); otherwise, with the requirements of the above specification not satisfied:

a. In OPERATIONAL CONDITIONS 1, 2 or 3, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.b. In OPERATIONAL CONDITIONS 4 or 5, declare the SACS system and the station service water system inoperable and take the ACTION required by Specification 3.7.1.1 and 3.7.1.2.c. In Operational Condition

• , declare the plant service water system inoperable and take the ACTION required by Specification 3.7.1.2.The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.3 The ultimate heat sink shall be determined OPERABLE: a. By verifying the river water level to be greater than or equal to the minimum limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.b. By verifying river water temperature to be within its limit: 1) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the river water temperature is less than or equal to 82 0 F.2) at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the river water temperature is greater than 82 0 F.* When handling recently irradiated fuel in the secondary containment.

HOPE CREEK 3 /4 7-5 Amendment No.

PLANT SYSTEMS 3/4.7.3 FLOOD PROTECTION LIMITING CONDITION FOR OPERATION 3.7.3 Flood protection shall be provided for all safety related systems, components and structures when the water level of the Delaware River reaches 6.0 feet Mean Sea Level (MSL) USGS datum (95.0 feet Exelon Generation Company, LLC datum) at the Service Water Intake Structure.

APPLICABILITY:

At all times.ACTION: a. With severe storm warnings from the National Weather Service which may impact Artificial Island in effect or with the water level at the service water intake structure above elevation 6.0 feet MSL USGS datum (95.0 feet Exelon Generation Company, LLC datum), initiate and complete: 1. The closing of all service water intake structure watertight perimeter flood doors identified in Table 3.7.3-1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or declare affected service water system components inoperable and take the actions required by LCO 3.7.1.2;-and -2. The closing of all power block watertight perimeter flood doors identified in Table 3.7.3-1 within 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Once closed, all access through the doors shall be administratively controlled.

b. With the water level at the service water intake structure above elevation 10.5 feet MSL USGS datum (99.5 feet Exelon Generation Company, LLC datum), be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.SURVEILLANCE REQUIREMENTS 4.7.3 The water level at the service water intake structure shall be determined to be within the limit by: a. Measurement at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the water level is below elevation 6.0 MSL USGS datum (95.0 feet Exelon Generation Company, LLC datum), and b. Measurement at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when severe storm warnings from the National Weather Service which may impact Artificial Island are in effect.c. Measurement at least once per hour when the water level is equal to or above elevation 6.0 MSL USGS datum (95.0 feet Exelon Generation Company, LLC datum).HOPE CREEK 3 /4 7-9 Amendment No.

ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)

The minimum voltage and frequency stated in the Surveillance Requirements (SRs) are those necessary to ensure the EDG can accept Design Basis Accident loading while maintaining acceptable voltage and frequency levels. Stable operation at the nominal voltage and frequency values is also essential to establishing EDG OPERABILITY, but a time constraint is not imposed. This is because a typical EDG will experience a period of voltage and frequency oscillations prior to reaching steady state operation if these oscillations are not dampened out by load application.

This period may extend beyond the 10 second acceptance criteria and could be a cause for failing the SR (for example if a significant negative trend develops).

In lieu of a time constraint in the SR, Exelon Generation Company, LLC will monitor and trend the actual time to reach steady state operation as a means of ensuring there is no voltage regulator or governor degradation which could cause an EDG to become inoperable.

The surveillance requirements for demonstrating the OPERABILITY of the unit batteries are in accordance with the recommendations of Regulatory Guide 1.129 Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978 and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations." Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.Table 4.8.2.1-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and .015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity.

The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than .020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than .010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.HOPE CREEK B 3/4 8-2 Amendment No.

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS 6.9.1.8 Deleted CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the Exelon Generation Company, LLC generated CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technical Specifications:

3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3/4.2.3 MINIMUM CRITICAL POWER RATIO 3/4.2.4 LINEAR HEAT GENERATION RATE 3/4.3.11 OSCILLATION POWER RANGE MONITOR (OPRM)The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC as applicable in the following documents:

1. NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel (GESTAR-II)" 2. CENPD-397-P-A, Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology" 3. NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, August 1996 The CORE OPERATING LIMITS REPORT will contain the complete identification for each of the TS referenced topical reports used to prepare the CORE OPERATING LIMITS REPORT (i.e., report'number title, revision, date, and any supplements).

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

HOPE CREEK 6-20 Amendment No.

ADMINISTRATIVE CONTROLS 6.15 TECHNICAL SPECIFICATION (TS) BASES CONTROL PROGRAM This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.b. Exelon Generation Company, LLC may make changes to the Bases without priolr NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the License, or 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.c. Proposed changes to the Bases that require either condition of Specification 6.15.b above shall be reviewed and approved by the NRC prior to implementation.

d. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).e. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.HOPE CREEK 6-26 Amendment No.

APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-57 HOPE CREEK GENERATING STATION EXELON GENERATION COMPANY, LLC I DOCKET NO. 50-354 ENVIRONMENTAL PROTECTION PLAN (NONRADIOLOGICAL)

Amendment No.

APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-57 Exelon Generation Company, LLC shall comply with the following conditions on the schedules noted below: I Amendment Number Additional Condition Implementation Date 97 103 105 110 114 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 January 11, 1996, as supplemented by letters dated February 26, May 22, June 27, July 12, December 23, 1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

The licensee shall relocate the list of "Motor Operated Valves -Thermal Overload Protection (BYPASSED)" from the Technical Specifications (Table 3.8.4.2-1) to the Updated Final Safety Analysis Report, as described in the licensee's application dated July 7, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

The licensee shall use the Banked Pattern Withdrawal System or an improved version such as the Reduced Notch Worth-Procedure as described in the licensee's application dated June 19, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

The licensee shall relocate the suppression chamber water volume, as contained in Technical Specifications 3.4.3.a, 3.5.3.b, 3.6.2.1.a.1 and 5.2.1 to the Updated Final Safety Analysis Report, as described in the licensee's application dated August 20, 1997, and evaluated in the staff's safety evaluation attached to this amendment.

The licensee is authorized to perform single cell charging of connected cells in OPERABLE class lE batteries as described in the licensee's application dated September 8, 1998, as supplemented by letter dated December 8, 1998, and evaluated in the staff's safety evaluation attached to this amendment.

The amendment shall be implemented within 60 days from March 21, 1997 The amendment shall be implemented within 60 days from September 16, 1977.The amendment shall be implemented within 60 days from September 30, 1997.The amendment shall be implemented within 60 days from November 6, 1977 The amendment shall be implemented within 60 days from February 9, 1999 I Amendment No.