ML022180607

April 5, 2002 - LIC-02-0042 - Revised Application for Renewed Operating License

ML022180607
Person / Time
Site:	Fort Calhoun
Issue date:	04/05/2003
From:	Clemens R Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Burton W, NRR/DRIP/RLEP, 301-415-2853
Shared Package
ML022180857	List: LIC-02-0042, Ft. Calhoun Station, Unit 1 - LRA Technical Information - Aging Management Review ML022180607 ML022180618
References
LIC-02-0042, NUREG-1801
Download: ML022180607 (13)

Text

upp" Omaha Public Power Distnct 444 South 16th Street Mall Omaha NE 68102-2247 April 5, 2002 LIC-02-0042 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

References:

1. Docket No. 50-285

2. Letter from OPPD (W.G. Gates) to NRC (Document Control Desk) dated January 9, 2002 (LIC-02-0001)

3. Letter from OPPD (W.G. Gates) to NRC (Document Control Desk) dated January 18, 2002 (LIC-02-0009)

4. Letter from NRC (C. I. Grimes) to OPPD (R. T. Ridenoure) dated March 14, 2002

SUBJECT:

Fort Calhoun Station Unit 1 Revised Application for Renewed Operating License In the Reference 2 letter, Omaha Public Power District (OPPD) transmitted the Fort Calhoun Station Unit 1 Application for Renewed Operating License. In the Reference 3 letter, OPPD provided a corrected version of the Application Appendix E, Applicant's Environmental Report.

The purpose of this letter is to transmit revisions to certain portions of the subject Application, as stated in the Reference 4 letter. These revisions are the results of a meeting with the NRC staff on February 14, 2002 and subsequent telephone discussions. The revisions will allow the NRC reviewers to verify that in-scope components in Section 2 are included in the Aging Management Review (AMR) results in Section 3, and to better compare the AMR results to NUREG-1801, Generic Aging Lessons Learned (GALL) Report.

The revised portions of the LRA included in this transmittal are: Section 2, Scoping And Screening Methodology For Identifying Structures And Components Subject To Aging Management Review, and Implementation Results; Section 3, Aging Management Review; Appendix A, USAR Supplement; and Appendix B, Aging Management Activities. Brief summaries of the revisions follow below.

In Section 2, links have been provided between the Section 2 components and the corresponding Section 3 Aging Management Review results. In addition, corrections have been made to some of the "intended functions" listings in the Section 2 tables, and minor editorial changes have been made throughout. Finally, Table 2.4.2.2-1 in Section 2 has been revised to indicate those components located in both the Turbine Building and the Service Building. This is in response to reviewer questions.

Employment with Equal Opportunity 4171

U. S. Nuclear Regulatory Commission LIC-02-0042 Page 2 In Section 3, the Aging Management Review results are now provided in three types of tables:

(1) components reviewed in GALL, (2) components not reviewed in GALL, and (3) components similar to those reviewed in GALL. Also, corrections have been made to the tables in Section 3.5, Aging Management Of Containment, Structures And Component Supports, and minor editorial changes have been made throughout.

In Appendix A, a clarification has been made in section A.2.9 concerning assurance of fuel oil quality. In Appendix B, the descriptions of Aging Management Programs that require enhancement to be consistent with GALL have been revised to identify which program elements require enhancements and to summarize the enhancements.

The paper original and 4 paper copies of this letter are transmitted to Mr. William Burton, the License Renewal Project Manager, for distribution at NRC headquarters. The attachments to this letter only include complete revised versions of Section 2, Section 3, Appendix A, and Appendix B of the Application, and include "Revision 1" in the footer of each page. These versions supersede Section 2, Section 3, Appendix A, and Appendix B of the paper and electronic Application transmitted by Reference 2. An updated Table of Contents is also included.

Also enclosed for NRC reviewers are 10 compact discs containing electronic copies of the complete LRA (including the revised portions previously described, but not including Appendix E), the boundary drawings referenced in the LRA, and the Fort Calhoun Station Updated Safety Analysis Report (USAR). These copies are in Adobe Portable Document Format (PDF) file format. The electronic boundary drawings and USAR are for information only and are not considered part of the LRA. To facilitate review, the compact disc copies include hyperlinks from the LRA text to referenced boundary drawings and USAR sections. Hyperlinks have been re-checked and known discrepancies have been corrected. The USAR file structure has been improved to allow linkage directly to subsections.

Please contact T.C. Matthews at 402-533-6938 if you have any questions. I declare under penalty of perjury that the foregoing is true and correct. (Executed on April 5, 2002)

Sinc Division Manager Nuclear Assessments TCM/tcm

U. S. Nuclear Regulatory Commission LIC-02-0042 Page 3 Attachments: Revised Table of Contents, Section 2, Section 3, Appendix A,and Appendix B of the Fort Calhoun Station Unit 1 Application for Renewed Operating License

Enclosure:

Revised Electronic Copy of the Fort Calhoun Station Unit 1 Application for Renewed Operating License (except for Appendix E) c:

E.W. Merschoff, NRC Regional Administrator, Region IV (w/o Attachments or Enclosure)

C.E. Johnson, NRC Region IV, DRP Branch Chief (w/o Enclosure)

A. B. Wang, NRC Project Manager (w/o Attachments or Enclosure)

T.J. Kenyon, NRC License Renewal Project Manager (w/o Attachments or Enclosure)

W.F. Burton, NRC License Renewal Project Manager S.K. Mitra, NRC License Renewal Project Manager (w/o Attachments or Enclosure)

W.C. Walker, NRC Senior Resident Inspector (w/o Enclosure)

Division Administrator - Public Health Assurance, State of Nebraska (w/o Enclosure)

Winston & Strawn (w/o Enclosure)

LIC-02-0042 Updated Table of Contents for the Fort Calhoun Station Unit 1 Application for Renewed Operating License

FORT CALHOUN STATION UNIT I LICENSE RENEWAL APPLICATION TABLE OF CONTENTS P R E FA C E..........................................................................................................

1 1.0 ADMINISTRATIVE INFORMATION....................................................................

1 1.1 Purpose And General Information.......................................................

1 1.2 N am e O f A pplicant................................................................................

1 1.3 Address Of Applicant...........................................................................

1 1.4 Description Of Business Or Occupation Of Applicant........................... 1 1.5 Organization And Management Of Applicant.....................................

2 1.6 Class And Period Of License Sought.................................................. 4 1.7 A lteration Schedule..............................................................................

4 1.8 Regulatory Agencies Having Jurisdiction And Appropriate News Publications............................................................

4 1.9 Conforming Changes To The Standard Indemnity Agreement............................................................................

5 1.10 Restricted Data Agreement................................................................

5 1.11 Description Of Fort Calhoun Station.....................................................

5 2.0 SCOPING AND SCREENING METHODOLOGY FOR IDENTIFYING STRUCTURES AND COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW, AND IMPLEMENTATION RESULTS..............................................

1 2.1 Scoping And Screening Methodology...................................................

1 2.2 Plant Level Scoping Results..............................................................

17 2.4 Scoping And Screening Results: Structures.....................................

75 2.5 Scoping And Screening Results: Electrical........................................ 98 2.6 R efe rences...........................................................................................

114 3.0 AGING MANAGEMENT REVIEW......................................................................

1 3.1 Aging Management Of Reactor Coolant Systems............................... 4 3.2 Aging Management Of Engineered Safety Features Systems.......

30 3.3 Aging Management Of Auxiliary Systems.......................................... 39 3.4 Aging Management Of Steam And Power Conversion Systems......

74 3.5 Aging Management Of Containment, Structures And Component Supports.........................................................................

86 3.6 Aging Management Of Electrical And Instrumentation And Controls... 116 4.0 TIME-LIMITED AGING ANALYSES..............................................................

1 4.1 Identification Of Time Limited Aging Analyses......................................

2 4.2 Reactor Vessel Neutron Embrittlement.................................................

5 4.3 M etal Fatigue......................................................................................

8 4.4 Environmental Qualification (EQ).......................................................

18 4.5 Concrete Containment Tendon Pre-stress..........................................

21 4.6 Containment Liner Plate And Penetration Sleeve Fatigue................ 22 4.7 O ther TLAA s......................................................................................

23 4.8 R eferences........................................................................................

26 APPENDIX A - UPDATED SAFETY ANALYSIS REPORT (USAR) SUPPLEMENT A.1 Introd uction....................................................................................

1 A.2 Programs And Activities For Managing The Effects Of Aging....... 1 A.2.1 Alloy 600 Program..............................................................

1 TABLE OF CONTENTS i

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TABLE OF CONTENTS A.2.2 Bolting Integrity Program....................................................

1 A.2.3 Boric Acid Corrosion Prevention Program......................... 2 A.2.4 Buried Surfaces External Corrosion Program..................... 2 A.2.5 Chemistry Program............................................................

2 A.2.6 Containment Inservice Inspection Program....................... 2 A.2.7 Containment Leak Rate Program........................................

3 A.2.8 Cooling Water Corrosion Program...................................... 3 A.2.9 Diesel Fuel Monitoring And Storage Program.................... 3 A.2.10 Fatigue Monitoring Program...............................................

4 A.2. 11 Fire Protection Program.....................................................

4 A.2.12 Flow Accelerated Corrosion Program................................ 4 A.2.13 General Corrosion Of External Surfaces Program.............. 4 A.2.14 Inservice Inspection Program.............................................

5 A.2.15 Non-EQ Cable Aging Management Program..................... 5 A.2.16 One-time Inspection Program............................................ 5 A.2.17 Overhead Load Handling Systems Inspection Program......... 5 A.2.1 8 Periodic Surveillance And Preventive Maintenance Program.6 A.2.19 Reactor Vessel Integrity Program......................................

6 A.2.20 Reactor Vessel Internals Inspection Program.................... 6 A.2.21 Selective Leaching Program...............................................

6 A.2.22 Steam Generator Program.................................................

6 A.2.23 Structures Monitoring Program..........................................

7 A.2.24 Thermal Aging Embrittlement Of Cast Austenitic Stainless Steel Program....................................................................

7 A.3 Evaluation Of Time-limited Aging Analyses...............................

7 A.3.1 Reactor Vessel Neutron Embrittlement.............................. 7 A.3.2 M etal Fatigue.....................................................................

9 A.3.3 Environmental Qualification Of Electrical Equipment.......

9 A.3.4 Concrete Containment Tendon Pre-stress.......................... 9 A.3.5 Containment Liner Plate And Penetration Sleeve Fatigue.... 10 A.3.6 Plant-specific Time-limited Aging Analyses....................... 10 APPENDIX B - AGING MANAGEMENT ACTIVITIES B.1 Existing Aging Management Activities........................................ 7 B. 1.1 Chemistry Program............................................................

7 B. 1.2 Containment Inservice Inspection Program......................... 8 B.1.3 Containment Leak Rate Program........................................ 9 B. 1.4 Flow Accelerated Corrosion Program................................ 10 B.1.5 Inservice Inspection Program............................................

11 B.1.6 Reactor Vessel Integrity Program...................................... 12 B.1.7 Steam Generator Program...............................................

13 B.2 Enhanced Aging Management Activities................................... 14 B.2.1 Bolting Integrity Program...................................................

14 B.2.2 Boric Acid Corrosion Prevention Program......................... 15 B.2.3 Cooling Water Corrosion Program...................................

16 TABLE OF CONTENTS ii

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION TABLE OF CONTENTS B.2.4 Diesel Fuel Monitoring And Storage Program................... 18 B.2.5 Fatigue Monitoring Program.............................................

19 B.2.6 Fire Protection Program...................................................

21 B.2.7 Overhead Load Handling Systems Inspection Program........ 22 B.2.8 Periodic Surveillance And Preventive Maintenance (PM)

P rogram............................................................................

23 B.2.9 Reactor Vessel Internals Inspection Program.................. 27 B.2.10 Structures Monitoring Program........................................

30 B.2. 11 Thermal Aging Embrittlement Of Cast Austenitic Stainless Steel..................................................................

31 B.3 New Aging Management Activities............................................

32 B.3.1 Alloy 600 Program............................................................

32 B.3.2 Buried Surfaces External Corrosion Program.................. 34 B.3.3 General Corrosion Of External Surfaces Program........

35 B.3.4 Non-EQ Cable Aging Management Program................... 38 B.3.5 One-time Inspection Program..........................................

41 B.3.6 Selective Leaching Program............................................

42 APPENDIX C - (NOT USED)

APPENDIX D - TECHNICAL SPECIFICATION CHANGES APPENDIX E - ENVIRONMENTAL INFORMATION TABLE OF CONTENTS iii TABLE OF CONTENTS oo,

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION LIST OF TABLES Table P.1 Table 2.2-1 Table 2.3.1.1-1 Table 2.3.1.2-1 Table 2.3.1.3-1 Table 2.3.2.1-1 Table 2.3.2.2-1 Table 2.3.3.1-1 Table 2.3.3.2-1 Table 2.3.3.3-1 Table 2.3.3.4-1 Table 2.3.3.5-1 Table 2.3.3.6-1 Table 2.3.3.7-1 Table 2.3.3.8-1 Table 2.3.3.9-1 Table 2.3.3.10-1 Table 2.3.3.11-1 Table 2.3.3.12-1 Table 2.3.3.13-1 Table 2.3.3.14-1 Table 2.3.3.15-1 Table 2.3.3.16-1 Table 2.3.3.17-1 Table 2.3.3.18-1 Table 2.3.3.19-1 Table 2.3.3.20-1 Table 2.3.4.1-1 Table 2.3.4.2-1 Table 2.3.4.3-1 Table 2.4.1-1 Table 2.4.2.1-1 Table 2.4.2.2-1 Table 2.4.2.3-1 Table 2.4.2.4-1 Table 2.4.2.5-1 Table 2.4.2.6-1 Table 2.4.2.7-1 Table 2.5.1-1 Table 2.5.2-1 Table 2.5.20-1 Table 3.1-1 List Of Acronyms, Symbols, Etc.............................................

3 Plant Level Scoping Results................................................

17 Reactor Vessel Internals.....................................................

25 Reactor Coolant..................................................................

29 Reactor Vessel.....................................................................

34 Safety Injection And Containment Spray............................. 37 Review And Intended Functions.......................................... 37 Containment Penetrations, And System Interface............... 38 Chemical And Volume Control System............................... 40 Spent Fuel Pool Cooling Component Types Subject To Aging Management Review And Intended Functions.......

42 Emergency Diesel Generators Component Types Subject To Aging Management Review And Intended Functions......... 44 Emergency Diesel Generator Lube Oil And Fuel Oil............... 46 Auxiliary Boiler Fuel Oil And Fire Protection Fuel Oil........... 48 Emergency Diesel Generator Jacket Water......................... 49 Starting Air...........................................................................

50 Instrument Air.......................................................................

52 Nitrogen Gas.......................................................................

53 Containment Ventilation.....................................................

54 Auxiliary Building HVAC.....................................................

56 Control Room HVAC And Toxic Gas Monitoring................. 58 Ventilating Air.......................................................................

59 Fire Protection.....................................................................

61 Raw W ater...........................................................................

63 Component Cooling...........................................................

65 Liquid W aste Disposal.........................................................

67 Gaseous Waste Disposal...................................................

68 Primary Sampling................................................................

69 Radiation Monitoring - Mechanical...................................... 70 Feedwater...........................................................................

71 Auxiliary Feedwater...........................................................

73 Main Steam And Turbine Steam Extraction........................ 74 Containment.......................................................................

77 Auxiliary Building................................................................

80 Turbine Building And Service Building................................ 85 Intake Structure...................................................................

86 Building Piles......................................................................

90 Fuel Handling Equipment And Heavy Load Cranes........

91 Component Supports.........................................................

94 Duct Banks.........................................................................

97 Cables And Connectors.....................................................

99 Containment Electrical Penetrations......................................

100 B u s B a rs................................................................................

1 1 3 Summary Of Aging Management Programs For Reactor Vessel, Internals, And Reactor Coolant System Evaluated LIST OF TABLES iv LIST OF TABLES iv

FORT CALHOUN STATION UNIT 1 LICENSE RENEWAL APPLICATION LIST OF TABLES Table 3.2-1 Table 3.2-2 Table 3.3-1 Table 3.3-2 Table 3.4-2 Table 3.5-1 Table 3.5-2 Table 4.1-1 Table 4.3-1 Figure 4.3.2-1 In NUREG-1801 That Are Relied On For FCS License Renewal 6 Summary Of Aging Management Programs For Engineered Safety Features Evaluated In NUREG-1 801 That Are Relied On For FCS License Renewal............................................

32 FCS Engineered Safety Features Component Types Subject To Aging Management Review Not Evaluated In N U R EG -1801..................................................................

38 Summary Of Aging Management Programs For Auxiliary Systems Evaluated In NUREG-1801 That Are Relied On For FCS License Renewal................................. 44 FCS Auxiliary Systems Component Types Subject To Aging Management Not Evaluated In NUREG-1801............... 57 FCS Steam And Power Conversion Systems Component Types Subject To Aging Management Review Not Evaluated In N U R EG -1801..................................................................

84 Summary Of Aging Management Programs For Structures And Component Supports Evaluated In NUREG-1801 That Are Relied On For FCS License Renewal.......................... 88 Aging Management Programs For Containment, Structures And Components That Are Not Addressed In NUREG-1801 109 Time-limited Aging Analyses Applicable To FCS.................. 3 FCS Reactor Coolant System Code Requirements............... 8 GSI-190 Evaluation Process...............................................

16 LIST OF TABLES V

LIST OF TABLES V

LIC-02-0042 Revised Section 2, Scoping and Screening Methodology For Identifying Structures and Components Subject To Aging Management Review, and Implementation Results, of the Fort Calhoun Station Unit 1 Application for Renewed Operating License

LIC-02-0042 Revised Section 3, Aging Management Results, of the Fort Calhoun Station Unit 1 Application for Renewed Operating License

LIC-02-0042 Revised Appendix A, USAR Supplement, of the Fort Calhoun Station Unit 1 Application for Renewed Operating License

LIC-02-0042 Revised Appendix B, Aging Management Activities, of the Fort Calhoun Station Unit 1 Application for Renewed Operating License