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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML20249C0011997-11-30030 November 1997
Reactor Vessel Fluence Analysis Methodology
ML20148E7091997-05-31031 May 1997
Vols 1 & 2 to Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Ors,Usi A-46, Per GL 87-02
ML18151A7101996-09-30030 September 1996
Supplemental Info for VA Power Nomad Code & Model.
ML20249C4051996-05-16016 May 1996
Rev 0 to CE-0082, Review of Augmented ISI Frequency for Pressurizer Spray Lines
ML20249C4031996-04-23023 April 1996
Rev 0 to CE-0081, Review of Augmented ISI Frequency for Reactor Coolant Bypass Lines
ML20092A2611995-08-31031 August 1995
EDG Preventive Maint Insp Outage Probabilistic Safety Assessment for August 1995
ML20078P9261994-09-26026 September 1994
Service Water System Operational Performance Assessment 940711-29
ML18153B4221993-07-31031 July 1993
Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station.
ML18153B4211993-07-31031 July 1993
Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station.
ML20046D1581993-02-28028 February 1993
Virginia Power Sys Transient Analysis Using Version 1 of North Anna Retran Model.
ML18152A0711993-02-0101 February 1993
NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept.
ML20116A2901992-09-23023 September 1992
Conceptual Engineering Final Rept NP-2653, RG 1.97 Isolation Devices Type 2,North Anna Power Station. W/One Oversize Encl
ML20101B0331992-04-30030 April 1992
Suppl to Update of Settlement Monitoring Points & Graphs NAPS - Supplement to Technical Rept CE-0019,North Anna Settlement Data Oct 1989 - Apr 1992
ML20077A6601991-05-0707 May 1991
Summary Rept on Exam of Steam Generator Tube R11-C14,North Anna Power Station,Unit 1
ML18153C3111990-07-26026 July 1990
Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station.
ML20011F6221990-02-26026 February 1990
Analysis of Small Steamline Break Performance W/O Low Pressurizer Pressure Safety Injection North Anna Units 1 & 2.
ML20248E8641989-09-19019 September 1989
Rev 0 to Evaluation of Settlement Monitoring Program for Main Plant Structures in Support of Proposed Changes to Tech Spec 3/4.7.12. W/One Oversize Figure
ML20246J1391989-08-17017 August 1989
Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding EP-2
ML20246J1581989-08-0909 August 1989
Rev 0 to Safety Sys Outage Mod Insp,Nrc Finding MC-1
ML20246J1261989-07-20020 July 1989
Rev 0 to Coordination of Load Ctr Circuit Breakers,EP-1
ML20246J1191989-07-20020 July 1989
Rev 0 to Response to SSOMI Item IC-8 of NRC
ML20246J0991989-07-18018 July 1989
Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-2
ML20246J1071989-07-18018 July 1989
Rev 0 to Response to NRC Ltr of 890626,Serial 89-485,App C, Finding IC-7
ML20246J1481989-06-30030 June 1989
RCS Leakage Detection Sys
ML20246K3461989-05-0505 May 1989
Technical Evaluation & Safety Analysis:Solid State Protection Sys Slave Relay Testing REA-88-51
ML20245K7311989-04-26026 April 1989
Rev 0 to 890225 Steam Generator Leak Event Rept
ML20056A0341989-04-18018 April 1989
Nonqualified Nuclear Decommissioning Trust Amended & Restated Trust Agreement
ML18151A9661989-04-18018 April 1989
Nuclear Decommissioning Trust Agreement.
ML20245A5311988-09-13013 September 1988
Simulator Certification Submittal
ML20148J6311988-03-16016 March 1988
Generator Tube Fatigue Evaluation & Remedial Actions Rept
ML20147F5621988-03-0202 March 1988
Safety Evaluation in Support of Containment Temp Increase for North Anna Power Station
ML20196J2901988-02-24024 February 1988
Rev 1 to Civil Engineering Technical Rept 0005, Differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House
ML20148J6401988-02-12012 February 1988
Rev 2 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept
ML20091L7041987-10-19019 October 1987
Generator Row 9 Column 51 Tube Failure Analysis
ML20235G2441987-09-25025 September 1987
Steam Generator Downcomer Mods Safety Evaluation for North Anna Units 1 & 2
ML20238F6161987-09-15015 September 1987
Rev 1 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept
ML18151A1351987-08-28028 August 1987
Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations.
ML20235U6701987-08-0707 August 1987
Loss of Inventory Event 870617-21
ML20235Q0661987-08-0505 August 1987
Metallurgical Svcs Rept FAL-00050
ML20237G9791987-07-29029 July 1987
Rev 0 to North Anna Unit 1 870715 Steam Generator Tube Rupture Event Rept. W/Pages from Facility Updated FSAR
ML20235U3431987-07-20020 July 1987
Rev 0 to Chronology Steam Generator Tube Rupture Event North Anna Power Station Unit 1 870715. Related Info Encl
ML20238E1611987-07-15015 July 1987
Rept of Emergency Preparedness Events Re Unit 1 Steam Generator Tube Rupture
ML20215G5471987-06-17017 June 1987
Safety Evaluation for Change in Methodology & Supporting Analyses
ML20235Q0551987-05-21021 May 1987
Investigation Rept FAL-00024, Emergency Diesel Generator Floating Busing Failure
ML20206D6721987-03-31031 March 1987
Engineering Analysis Svc & Maint North Anna Power Station Fairbanks-Morse 38 TD8-1/8 Diesel Engines Phase II
ML20207B5231986-11-30030 November 1986
Reactor Vessel Fluence & Rt/Pts Evaluations Suppl to WCAP 11016
ML20213D7771986-10-31031 October 1986
RCS Leakage Detection Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices
ML20213D7601986-10-31031 October 1986
RCS Loads & Component Support Margins Evaluation for Elimination of Rcs,Main Loop Pipe Break Protective Devices
ML20210F6821986-10-17017 October 1986
Reactor Protection Sys Trip Setpoint Drift Characterization
1999-10-12
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999
Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised
ML20217H3631999-10-14014 October 1999
Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su
ML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML20212J9251999-10-0101 October 1999
Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant
ML20217D6851999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With
ML20211N2611999-09-0808 September 1999
Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable
ML20211J2561999-08-31031 August 1999
Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2
ML20216E5011999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with
ML20211J2421999-08-31031 August 1999
Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2
ML20210T0791999-08-13013 August 1999
Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable
ML20210S1411999-07-31031 July 1999
Monthly Operating Repts for July 1999 for North Anna Power Station.With
ML20210Q9931999-07-31031 July 1999
Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud
ML20209E5641999-06-30030 June 1999
Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With
ML20195G1901999-05-31031 May 1999
Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with
ML20206L4831999-05-10010 May 1999
SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping
ML20206Q6671999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With
ML20205S0391999-04-21021 April 1999
SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii)
ML20205K3041999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With
ML20207K5921999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With
ML20207E1731999-02-18018 February 1999
Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year
ML20205A0241998-12-31031 December 1998
Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With
ML20199C8781998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With
ML20198H9541998-12-0303 December 1998
Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant
ML20198J5561998-12-0303 December 1998
ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps
ML20197G8551998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With
ML20196G1381998-11-0303 November 1998
Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit
ML20195D0571998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With
ML20154L0691998-10-14014 October 1998
COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy
ML20155J6911998-10-0909 October 1998
Staff Response to Tasking Memorandum & Stakeholder Concerns
ML20154H4001998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With
ML20151X8011998-09-10010 September 1998
Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section
ML20151W4711998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With
ML20237A4341998-07-31031 July 1998
Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2
ML20236V1251998-07-14014 July 1998
ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis
ML20236K5531998-07-0707 July 1998
SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment
ML20236M3381998-06-30030 June 1998
Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2
ML20248M1011998-05-31031 May 1998
Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2
ML20248C8831998-05-29029 May 1998
SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program
ML20247K9281998-05-15015 May 1998
Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary
ML20216A8971998-05-0606 May 1998
Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2
ML20247F4441998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2
ML20217B5321998-04-20020 April 1998
Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs
ML20217H9611998-04-0707 April 1998
Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed
ML20216B1891998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2
ML20216E8801998-03-0606 March 1998
Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii)
ML20216E2561998-02-28028 February 1998
Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2
ML20199J6431998-02-0202 February 1998
Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218
ML20202D5811998-01-31031 January 1998
Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2
ML20198S7571998-01-15015 January 1998
Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping
ML20198P1351997-12-31031 December 1997
Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2
1999-09-08
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Text
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REPORT OF EFFECT OF OUTDATED AMPLIFIED RESPONSE SPECTRUM CURVES ON SERVICE WATER PUMPHOUSE SETTLEMENT NORTH ANNA UNITS 1 AND 2 During the review of the seismic analysis of Category I piping, as required by Inspection and Enforcement Bulletin No. 79-14, an inconsistency was discovered in the way in which certain of the seismic amplified response spectrum (ARS) curves were used as input data to the stress analysis (Information about aplified response spectra can be found in section 3. 7. 2 of the North Anna 1 & 2 FSAR) . An investigation showed there to be three typ,es of inconsistencies in the ARS data. The first inconsistency was that certain curves had two or more values of accelera-tion for the same period (i.e. , multiple periods) . The second was that the peak-spreading (the technique used to develop a conservative envelope) of some curves was not exactly +15 percent of the peak's period as described in FSAR Section 3,7.3. The third discrepancy was that a few of the ARS curves were not the most current. It has been determined by a complete review of the ARS input to pipe stress calculations that there are no inconsistencies other than those described above.
The piping systems af fected by the above findings are located in the Service Water Pump House, the Auxiliary Building, the Safeguards Buildings, the Fuel Building, the Auxiliary Feedwater Pump Houses , and the Main Steam Valve houses. Curves having multiple periods were used in the Main Steam Valve Houses, the Fuel Building, and the Safeguards Buildings.
The peak spreading problem affects only those analyses using the ARS data for the Unit I Main Steam Valve House. Outdated curves were used for analyses in the Service Water Pump House, the Auxiliary Building and the Auxiliary Feedwater Pump Houses.
These discrepancies af fect only the dynamic analysis of piping systems. The static analysis involving seismic building movements is not af fected. In addition, the ARS inconsistencies apply only to analyses using the SHOCK III program and not those using the NUPIPE program.
The only portion of the piping in the Service Water Pump House (SWPH) that is affected by the use of outdated ARS curves is that which extends from the point at which the two 36-inch discharge headers are embedded in the north wall of the SWPH to the pumps inside the structure.
The two 36-inch return headers and the service water spray piping to the south of the SWPH are not affected. The stress analysis of the affected piping is not affected by the pump house settlement, nor is it related to the motion of the short section of pipe that extends from the north face of the SWPH to the expansion joints. The motion of that short section of pipe is a direct result of pump house seismic motion. The seismic input information used to calculate the SRPH motion has been reviewed and is current.
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2.
The analysis of the buried piping and the expansion joint outside of the SWPH is completely unaffected by SHOCK III because that analysis was conducted using the NUPIPE program. Since NUPIPE requires input data in a format that is different from the data for the SHOCK III program, a separate file of digitized ARS curves is maintained for NUPIPE analyses. The ARS curves that were used with NUPIPE for the SWPH buried piping and expansion joint analysis are current, as has been verified by a recent detailed check. Therefore, the existing analysis is valid and not affected by the SHOCK III format inconsistencies described above.
In order to verify our piping seismic design, we are revising all computerized analyses which had inconsistencies in the SHOCK III format ARS input. As explained above, however, the analyses performed on the expansion joints and the buried lines north of the SWPH and on the service water spray piping south of the SWPH are not affected by the inconsistencies. Therefore, our design analysis and consequently, our testimony before the Appeal Board
- Hearing of June 18-20, 1979, 1684 107
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of ) Doc. Nos. 50-338 OL
) 50-339 OL VIRGINIA ELECTRIC AND POWER COMPANY)
) (Pumphouse Settlement and (North anna Power Station, Units ) Turbine Missiles) 1 and 2)
AFFIDAVIT OF ROBERT B. BRADBURY My name is Robert B. Bradbury. My business address is 245 Summer St.,
Boston, Mass. I am the Project Engineer for North Anna Unit 2 with the Stone & Webster Engineering Corporation. A statement of my professional qualifications was entered into the record of this proceeding at the hearing June 18-20, 1979. I am responsible for the execution of all engineering on the project, including pipe stress analysis. I am familiar with the overall conduct of these analyses.
Some of my colleagues and I at Stone & Webster Engineering Corporation-have prepared a report from the Atomic Safety and Licensing Appeal Board entitled " Report on Effect of Outdated Amplified Response Spectrum Curves on Service Water Pumphouse Settlement - liorth Anna Units 1 and 2." A copy of that report is attached to and made a part of this affidavit. I assisted in and supervised the preparation of the report.
Because of my involvement in North Anna 1 and 2. I am satisfied that the report attached as this affidavit is true and correct to the best of my knowledge and belief.
( / '
Commonwealth of Massachusetts Suffolk County, ss.
The foregoing instrument was acknowledged before me this M th of December, 1979.
Nota'ry Public My Commission Expwes Seotember 21.1984 1684 108
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of ) Doc. Nos. 50-338 OL
) 50-339 CL VIRGINIA ELECTRIC AND POWER COMPANY)
) (Pumphouse Settlement and (North Anna Power Station, Units ) Turbine Missiles) 1 and 2)
AFFIDAVIT OF Glenn P. Milley My name is Glenn P. Milley. My business address is 245 Summer Street, Boston, Massachusetts. I am a Lead Engineering Mechanics Engineer with the Stone & Webster Engineering Corporation. An accurate statement of my professional qualifications is attached as a part of this affidavit.,
I have worked on and supervised pipe stress analysis work for safety-related piping systems throughout the last seven years. I have worked exclusively on the North Anna Units 1 and 2 for four years.
Some of my colleagues and I at Stone & Webster Engineering Corporation have prepared a report for the Atomic Safety and Licensing appeals Board entitled " Report on Effect of Outdated Amplified Response Spectrum Curves on Service Water Pumphouse Settlement - North Anna Units 1 and 2." A copy of that report is attached to and made a part of this affidavit. I supervised and directed the preparation of this report.
Because of my involvement in the pipe stress analyses at North Anna 1 and 2, I am satisfied that the report attached to this affidavit is true and correct, to the bo t of my knowledge and belief.
Y k /
e Commonwealth of Massachusetts Suffolk County, ss.
The foregoing instrument was acknowledged before me this /f th day of December 1979.
' Notary Public my commuon ue.r., s :me., u, a 1684 109
PROFESSIONAL QUALIFICATIONS GLENN P. MILLEY LEAD ENGLNEER - NORTH ANNA UNIT 1&2 STONE & WEBSTER ENGINEERING CORPORATION My name is Glenn P. Milley. My business address is 245 Summer Street, Boston, Massachusetts. I am a Lead Engineer assigned to the North Anna Units 1 and 2 Power Plant Projects. My present responsibilities are the review and supervision of all work and personnel assigned to pipe stress and pipe support analysis, structural mechanics and mechanical design and analysis.
I received a B.S. degree in Mechanical Engineering from Lowell Technological Institute in 1971 where I minored in stress analysis. I also received a Master's degree in Mechanical Engineering from Northeastern University in 1976.
I have been ecployed by Stone & Webster in the Pipe Stress and Supports Section since 1973. I have worked on and supervised pipe stress analysis of Class 1, 2, 3 and non Q piping systems on both fossil and nuclear power stations. I have worked on the Vepco project exclusively since March of 1976.
I am a registered Professional Engineer in the state of Massachusetts.
1684 110
