ML063620382

(BVPS-1 and 2) - Draft Safety Evaluation for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues

ML063620382
Person / Time
Site:	Beaver Valley
Issue date:	01/04/2007
From:	Nadiyah Morgan NRC/NRR/ADRO/DORL/LPLI-1
To:	Lash J FirstEnergy Nuclear Operating Co
Colburn T, NRR/DORL/LPLI-1, 415-1402
References
TAC MC6285, TAC MC6286, TAC MC6579, TAC MC6612, TAC MC6614, TAC MC6626, TAC MC6783, TAC MC6792
Download: ML063620382 (20)

Text

January 4, 2007 Mr. James H. Lash Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 (BVPS-1 AND 2) -

DRAFT SAFETY EVALUATION FOR THE CONVERSION TO THE IMPROVED TECHNICAL SPECIFICATIONS WITH BEYOND-SCOPE ISSUES (TAC NOS.

MC6285, MC6286, MC6579 - MC6612, MC6614 - MC6626, AND MC6783 -

MC6792)

Dear Mr. Lash:

Enclosed are (1) a draft amendment with license conditions and an implementation date for BVPS-1, and (2) a draft amendment with license conditions and an implementation date for BVPS-2, and (3) a draft Safety Evaluation (SE), including tables describing the changes from current Technical Specifications to improved Technical Specifications (ITSs) for BVPS-1 and 2.

The enclosed documents are based on (1) your application dated February 25, 2005, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML050610339), as supplemented by letters dated November 11, 2005 (ADAMS Accession No. ML053290071), April 19, 2006 (ADAMS Accession No. ML061140093), July 10, 2006 (ADAMS Accession No. ML061940177), September 1, 2006 (ADAMS Accession No. ML062490197),

October 24, 2006 (ADAMS Accession No. ML063000086), and December 7, 2006 (ADAMS Accession No. ML063450214), and (2) the information provided to the Nuclear Regulatory Commission (NRC) staff through the joint NRC/BVPS ITS Conversion web page. To expedite review of the application, the NRC staff agreed to place its requests for additional information (RAIs) on the web page. Your staff agreed to then provide responses to the RAIs on the web page. To document the information contained on the web page, the licensee submitted a copy of the complete database to the NRC (ADAMS Accession No. ML063000089) as an attachment to its October 24, 2006, supplement.

The enclosed draft amendment and draft SE are being provided for your review. These draft documents are not yet in final form. The issuance of these drafts permits you an early opportunity to start you review. Please review the enclosed draft amendment and SE for technical accuracy and provide your comments in writing within 30 days of the date of this letter.

J. Lash If you have any questions concerning this letter and the draft SE, contact me at 301-415-1016 or email nsm@nrc.gov.

Sincerely,

/RA/

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

Enclosures:

1. Draft Amendment to DPR-66

2. Draft Amendment to NPF-73

3. Draft Safety Evaluation cc w/encls: See next page

J. Lash If you have any questions concerning this letter and the draft SE, contact me at 301-415-1016 or email nsm@nrc.gov.

Sincerely,

/RA/

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

Enclosures:

1. Draft Amendment to DPR-66

2. Draft Amendment to NPF-73

3. Draft Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC LPLI-1 R/F RidsNrrDorlLpl1-1 NMorgan RidsNrrLASLittle RidsNrrDirsItsb ADAMS Accession Number: ML063620382 OFFICE NRR/LPLI-1/PM NRR/LPLI-1/LA NRR/LPLI-1/BC NAME NMorgan SLittle RLaufer DATE 01/04/07 01/04/07 01/04/07 OFFICIAL RECORD COPY

Beaver Valley Power Station, Unit Nos. 1 and 2 cc:

Gary R. Leidich James H. Lash President and Chief Nuclear Officer Site Vice President FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 Beaver Valley Power Station 76 South Main Street Mail Stop A-BV-SEB1 Akron, OH 44308 P.O. Box 4, Route 168 Shippingport, PA 15077 Joseph J. Hagan Senior Vice President of Operations Director, Fleet Regulatory Affairs and Chief Operating Officer FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GHE-315 Mail Stop A-GO-14 395 Ghent Road 76 South Main Street Akron, Ohio 44333 Akron, OH 44308 Manager, Site Regulatory Compliance Danny L. Pace FirstEnergy Nuclear Operating Company Senior Vice President, Fleet Engineering Beaver Valley Power Station FirstEnergy Nuclear Operating Company Mail Stop A-BV-A Mail Stop A-GO-14 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Richard Anderson Jeannie M. Rinckel Vice President, Nuclear Support Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 Mail Stop A-GO-14 Akron, Ohio 44308 76 South Main Street Akron, OH 44308 Commissioner James R. Lewis West Virginia Division of Labor David W. Jenkins, Attorney 749-B, Building No. 6 FirstEnergy Corporation Capitol Complex Mail Stop A-GO-18 Charleston, WV 25305 76 South Main Street Akron, OH 44308 Director, Utilities Department Public Utilities Commission Manager, Fleet Licensing 180 East Broad Street FirstEnergy Nuclear Operating Company Columbus, OH 43266-0573 Mail Stop A-GHE-115 395 Ghent Road Director, Pennsylvania Emergency Akron, OH 44333 Management Agency 2605 Interstate Dr.

Ohio EPA-DERR Harrisburg, PA 17110-9364 ATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149

Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:

Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077

DRAFT FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.

DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 278 License No. DPR-66

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

A. The application for amendment by FirstEnergy Nuclear Operating Company, et al. (the licensee), dated February 25, 2005, as supplemented November 11, 2005, April 19, July 10, September 1, October 24, and December 7, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

DRAFT

DRAFT

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

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

3. This amendment authorizes the relocation of certain current Technical Specification requirements and operating license conditions to other licensee-controlled documents.

Implementation of this amendment shall include the relocation of these requirements to the other documents, as described in (1) Section 6.0 of the NRC staff's Safety Evaluation, and (2) Table LA of Removed Details and Table R of Relocated Specifications attached to the NRC staff's Safety Evaluation, which is enclosed with this amendment. A new License Condition has been added to Appendix C to address the relocation.

Relocation of Certain Technical Specification Requirements License Amendment No. 278 authorizes the relocation of certain Technical Specifications to other licensee-controlled documents. Implementation of this amendment shall include relocation of the requirements to the specified documents, as described in (1) Sections 4D and 4E of the NRC's staff's Safety Evaluation, and (2)

Table LA, Removed Detail Changes, and Table R, Relocated Specifications, attached to the NRC staff's Safety Evaluation, which is enclosed in this amendment.

4. License condition, 2.C.(9), is deleted.

5. New license conditions are added in Appendix C to address performance of new and revised Surveillance Requirements (SRs):

Schedule for New and Revised Surveillance Requirements (SRs)

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

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

DRAFT

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

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

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

6. This license amendment is effective as of the date of its issuance and shall be implemented within 150 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard J. Laufer, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: January 4, 2007 DRAFT

DRAFT ATTACHMENT TO LICENSE AMENDMENT NO. 278 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of the 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 3 3 6 6 6a 6a

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Page 4 of Appendix C Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert All All DRAFT

DRAFT (3) FENOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) FENOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) FENOC, pursuant to the Act and 10 CFR Parts 30, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

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

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

Amendment No. 278 DRAFT

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

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

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

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

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

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

1. Training of personnel, and

2. Procedures for monitoring.

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

Amendment No. 278 DRAFT

DRAFT

- 6a -

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

2.D. Physical Protection FENOC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21 is entitled: "Beaver Valley Power Station (BVPS) Physical Security Plan" submitted by letter September 9, 2004, and supplemented September 20, 2004, and October 14, 2004.

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

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

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

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

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

The schedule for performing SRs that are new or revised in The amendment Amendment No. 278 shall be as follows: shall be implemented For SRs that are new in this amendment, the first performance within 150 days is due at the end of the first surveillance interval, which begins from on the date of implementation of this amendment.

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

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

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

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

4 Amendment No. 278 DRAFT

DRAFT FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.

OHIO EDISON COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 161 License No. NPF-73

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

A. The application for amendment by FirstEnergy Nuclear Operating Company, et al. (the licensee), dated February 25, 2005, as supplemented November 11, 2005, April 19, July 10, September 1, October 24, and December 7, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

DRAFT

DRAFT

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

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

3. This amendment authorizes the relocation of certain current Technical Specification requirements and operating license conditions to other licensee-controlled documents.

Implementation of this amendment shall include the relocation of these requirements to the other documents, as described in (1) Section 6.0 of the NRC staff's Safety Evaluation, and (2) Table LA of Removed Details and Table R of Relocated Specifications attached to the NRC staff's Safety Evaluation, which is enclosed with this amendment. A new License Condition has been added to Appendix D to address the relocation.

Relocation of Certain Technical Specification Requirements License Amendment No. 161 authorizes the relocation of certain Technical Specifications to other licensee-controlled documents. Implementation of this amendment shall include relocation of the requirements to the specified documents, as described in (1) Sections 4D and 4E of the NRC's staff's Safety Evaluation, and (2)

Table LA, Removed Detail Changes, and Table R, Relocated Specifications, attached to the NRC staff's Safety Evaluation, which is enclosed in this amendment.

4. License condition, 2.C.(12), is deleted.

5. New license conditions are added in Appendix D to address performance of new and revised Surveillance Requirements (SRs):

Schedule for New and Revised Surveillance Requirements (SRs)

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

DRAFT

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

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

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

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

6. This license amendment is effective as of the date of its issuance and shall be implemented within 150 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard J. Laufer, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: January 4, 2007 DRAFT

DRAFT ATTACHMENT TO LICENSE AMENDMENT NO. 161 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of the 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 3a 3a 5 5

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Page 4 of Appendix D Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert All All DRAFT

DRAFT

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

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

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

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

Amendment No. 161 DRAFT

DRAFT (8) Detailed Control Room Design Review (DCRDR)

Deleted (9) Safety Parameter Display System (SPDS)

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

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

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

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

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

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

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

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

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

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

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

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

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

4 Amendment No. 161 DRAFT