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Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
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WSL F CREEK'NUCLEAR OPERATING CORPORATION Terry J. Garrett June 19, 2008 Vice President, Engineering ET 08-0035 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter ET 07-0004, dated March 14, 2007, from T. J. Garrett, WCNOC, to USNRC
- 2) Letter dated December 7, 2007, from J. N. Donohew, USNRC, to R. A. Muench, WCNOC
- 3) Letter ET 08-0004, dated January 18, 2008, from T. J. Garrett, WCNOC, to USNRC
- 4) Letter ET 08-0017, dated March 14, 2008, from T. J. Garrett, WCNOC, to USNRC
Subject:
Docket No. 50-482: Main Steam and Feedwater Isolation System (MSFIS) Controls Modification - Electromagnetic Compatibility Tests Gentlemen:
Reference 1 provided a license amendment request that proposed revisions to Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System. (ESFAS)
Instrumentation," TS 3.7.2, "Main Steam Isolation Valves (MSIVs)," and TS 3.7,3, "Main Feedwater Isolation Valves (MFIVs)." Reference 1 proposed changes to these specifications based on a planned modification to replace the-MSIVs and associated actuators, .MFIVs and associated actuators, and replacement of theMain Steam and Feedwater Isolation System (MSFIS) controls.
Reference 3 indicated that to address question, 11 provided in Reference 2, WCNOC would conduct additional electromagnetic compatibility (EMC) tests and the results of the testing would be provided by March 15, 2008. Reference 4 identified that the additional EMC tests would be completed by June 25, 2008. The Attachment provides a response to question 11 and the results of the additional testing.
PRO. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET
ET 08-0035 Page 2 of 3 The information provided in the Attachment does not impact the conclusions of the No Significant Hazards Consideration provided in Reference 1. In accordance with 10 CFR 50.91, a copy of the submittal is being provided to the designated Kansas State official.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4084, or Mr. Richard D. Flannigan at (620) 364-4117.
Sincerely, Terry J. Garrett TJG/rlt Attachment cc: E. E. Collins (NRC), w/a T. A. Conley (KDHE), w/a V. G. Gaddy (NRC), w/a B. K. Singal (NRC), w/a Senior Resident Inspector (NRC), w/a
ý.I ET 08-0035 Page 3 of 3 STATE OF KANSAS )
COUNTY OF COFFEY )
Terry J. Garrett, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Terry J Garrett Vice PMesident Engineering SUBSCRIBED and sworn to before me this I g'i day of 4 vUv ,2008.
CP I U Notary Public Expiration Date avwo' //, Z_/I/)
U U
Attachment to ET 08-0035 Page 1 of 3 Response to Question 11 from NRC Letter of December 7, 2007 Reference 1 provided a request for additional information associated with the license amendment request for the replacement of the Main Steam and, Feedwater Isolation System (MSFIS) controls. Reference 2 indicated that to address question 11, Wolf Creek Nuclear Operating Corporation (WCNOC) would conduct additional!electromagnetic compatibility (EMC) tests and the results of the testing would be provided by. March 15, 2008. Reference 3 identified that the additional EMC tests would be completed by June 25, 2008. Question 11 from Reference 1 and WCNOC's response is provided below.
- 11. Environmental Test Plans: The documents reviewed to determine the acceptability of the environmental test plans were the Nutherm, "Qualification Report for CS Innovations Replacement MSFIS System," Nutherm Document Number WCN-9715R, Rev. 0, dated February 16, 2007, including Appendix 1,11, 111, VI [IV], V, and'VI, provided as Enclosure VI to letter dated April 18, 2007 (ET 07-0008); and Wolf Creek Generation Station Specification J-105A(Q), Revision 2, "Replacement MSFIS System," dated October 3, 2006, and provided as Enclosure 1 to letter dated April .18, 2007 (ET 07-0008). The combined requirements in these documents were compared to the requirements of IEEE Standard 323-1974/1983, IEEE Standard 344 1987, EPRI Report TR-102323, Military Standard MIL-STD-461E, and the International Electrotechnical Commission (IEC) 6100 series endorsed by RG 1.180, Revision 1, as discussed below:
A) EMC Susceptibility Test NRC RG 1.180, Revision 1, specifies two test methods acceptable to the NRC staff in regard to susceptibility testing for safety related instrumentation and controls (I&C) systems in nuclear power plants, and lists the detailed tests of the two methods as Table 6 and Table 7 on page 19. These two methods are the following:
- 1) EMI/RFI test methods in MIL-STD-461E,
- 2) EMI/RFI test methods in IEC 61000-4 RG 1.180, Rev.1, Section 4, page 18, also states: ",Itis intended thateither set of test methods be applied in its entirety, without selective application of individual methods (i.e., no mixing and matching of test methods) for susceptibility testing."
The test methods proposed, however, appear to mix and match test methods, in that.
the licensee provided an incomplete test set of IEC 6100-4 susceptibility tests, did not perform the tests of IEC 61000-4-9, 61000-4-10, and 61000-4-13, and did perform two additional MIL-STD-461E susceptibility tests, CS101 and RS101, from the other set. Provide justification for this. As stated above, the licensee can choose either test method MIL-STD-461E or IEC 61000-4, but it is requested.that the licensee provide the entire set of test results of the. selected method.
B) The licensee quoted an excerpt of EPRI TR-1.0323 [102323], Rev. 2, Appendix D,:
"NRC Safety Evaluation Report," page D-16, as stated below:
The staff also disagreed with the Working Group not recommending a low frequency range (30 Hz to 50 kHz) radiated susceptibility test for. equipment, qualification because low frequency magnetic-field in the equipment location can attenuate rapidly within a short distance. The staff. believes that such a test would provide increased assurance that -equipment is not susceptible to
Attachment to ET 08-0035 Page 2 of 3 radiated magnetic fields in the frequency range of 30 Hz to 50 kHz. In response, the Working Group agreed to revise TR-102323 to recommend a low frequency radiated susceptibility test limit consistent with Figure 5-4 of TR-102323. Licensees' could, however, justify a less restrictive test limit under certain circumstances such as the presence of an equipment shield of ferrous metal or installing the new equipment at a substantial distance from potential sources. 9 The licensee then indicated that IEC 61000-4-9 and IEC 61000-4-10 were not included based on this evaluation. Since the waiver of these two EMC susceptibility tests is only allowed under special conditions, provide the justification why the tested equipment satisfied these special conditions.
C) Nutherm, on page 13 of WCN-9715R, stated that "The MSFIS system contains only DC power and signal lines, therefore susceptibility test 61000-4-13 is not applicable and will not be performed." Since the area in which the equipment will be located has AC power, and the DC power supply for the MSFIS is contained in the base of the cabinet, provide justification of why this test was not performed. This justification should include the distance to the nearest AC power lines and the expected signal strength.
Response: Reference 4 included the Nutherm Qualification Report, WCN-9715R. This report documents the results of the electromagnetic compatibility (EMC) testing of CS Innovations replacement MSFIS controls. As noted above the testing included a combination of IEC 61000-4 and MIL-STD-461E test methods. Provided below is the test methods conducted on the controls.
IEC 61000-4 Test Methods Conducted:
61000-4-3 Radiated, Radio-Rrequency, Electromagnetic Rield Immunity Test 61000-4-4 Electrically Fast Transient/Burst Immunity test 61000-4-5 Surge Immunity Test 61000-4-6 Immunity to Conducted Disturbances, Induced by Radio-Frequency Fields 61000-4-8 Power Frequency Magnetic Field Immunity Test 61000-4-12 Oscillatory Waves Immunity Test 61000-4-16 Test for Immunity to Conducted, Common Mode Disturbances in the Frequency Range 0 Hz to 150 kHz MIL-STD-461E Test Methods conducted:
CE101 Conducted emissions, power leads, 30 Hz to 10 kHz CE102 Conducted emissions, power leads, 10 kHz to 10 MHz CS101 Conducted susceptibility, power leads, 30 Hz to 50kHz RE101 Radiated emissions, magnetic field, 30 Hz to 100 kHz RE102 Radiated emissions, electric field, 10 kHz to 1 GHz RS101 Radiated susceptibility, magnetic field, 30 Hz to 100 kHz As a result of the RAI question, Reference 2 indicated that WCNOC would conduct the additional IEC tests that were not performed (specifically IEC 61000-4-9, IEC 61000-4-10, and IEC 61000-4-13).
Attachment to ET 08-0035 Page 3 of 3 On March 25, 2008, a teleconference between NRC, WCNOC, and CS Innovations personnel was held to discuss why IEC 61000-4-13, Immunity to Harmonics and Interharmonics, is not an applicable test for the MSFIS controls. IEC 61000-4-13 was developed to assess the performance of covering electrical 'and electronic equipment when it is subjected to conducted, differential-mode disturbances (harmonics and interharmonics) on low-voltage power mains.
As described in NUREG/CR-6782, "Comparison of U. S. Military and International Electromagnetic Compatibility Guidance," this test doesý not apply to equipment operating on dc power. IEC 61000-4-13 was not performed on the equipment since the MSFIS controls are dc powered controls. This test involves applying a clipped AC power sinewave to the item. under test to provide the desired harmonic content and distortion spectrum. As such, this test cannot be performed on dc powered equipment.
IEC 61000-4-9, Pulse Magnetic Field Immunity:Test, and IEC 61000-4-10, Damped Oscillatory Magnetic Field Immunity Test, were performed on the MSFIS controls (Advanced Logic System (ALS) rack) equipment on March 28, 2008 .by Elite Engineering and observed by CS Innovations.
Testing to IEC 61000-4-10 was done first with the multi turn Helmholtz coil (Elite Equipment ID NCEO). Two oscillation frequencies of 100kHz and 1MHz were done. The 100kHz magnetic oscillation was tested first to each axis with a.function check of the ALS rack done before and after the test of each axis. The Elite Engineering test equipment was then recalibrated to perform IEC 61000-4-10 testing at 1MHz. Each axis was then tested. A functional check of the ALS rack was done before and after the test of each axis. The ALS rack worked through the test with no interruption or failure. IEC 61000-4-9 pulse testing applied 5 magnetic pulses to each axis in 20 second intervals using the single turn Helmholtz coil (Elite Equipment ID NCE1).
Functional testing of the ALS rack was done before and after the pulse test of each axis. The ALS rack successfully passed pulse testing with no interruptions or failures.
The detailed test results were made available to the NRC technical branch reviewer at the CS Innovations offices during the week of May 12, 2008.
References:
- 1. Letter dated December 7, 2007, from J. N. Donohew, USNRC, to R. A. Muench, WCNOC
- 2. Letter ET 08-0004, dated January 18, 2008, from T. J. Garrett, WCNOC, to USNRC
- 3. Letter ET 08-0017, dated March 14, 2008, from T. J. Garrett, WCNOC, to USNRC
- 4. Letter ET 07-0008, dated April 18, 2007, from T. J. Garrett, WCNOC, to USNRC