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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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W'!LF CREEKINUCLEAR OPERATING CORPORATION Terry J. Garrett Vice!President, Engineering February 28, 2008 ET 08-0014 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 ET 08-0004, dated January 18, 2008, from T. J. Garrett, WCNOC, to USNRC
- 3) Letter ET 08-0008, dated January 31, 2008, from T. J. Garrett, WCNOC, to USNRC
Subject:
Docket No. 50-482: Additional Information Regarding Main Steam and Feedwater Isolation System (MSFIS) Controls Modification 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 the Main Steam and Feedwater Isolation System (MSFIS) controls.
Reference 2 provided a table identifying additional/revised documentation to be submitted associated with the modification to the MSFIS Controls. Attachment I provides a discussion of the documentation being provided as committed to in Reference 2. Reference 3 provided Revision 2 to the Wolf Creek Nuclear Operating Corporation (WCNOC) System Verification and Validation Report as committed to in Reference 2. On February 22, 2008, the NRC Project Manager provided by electronic mail the NRC staff concerns associated with the WCNOC System Verification and Validation Report and subsequently indicated the staff request for a site visit in March 2008. WCNOC did not clearly communicate that there are four inputs into the 4oo/
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET
ET 08-0014 Page 2 of 4 verification and validation process. The Table in Reference 2 indicated that verification and validation reports on the design, implementation, and test activities would be submitted by February 29, 2008. The WCNOC response for this item is to submit the CS Innovations report 6101-00200, "MSFIS V & V Report." The concerns identified on February 22, 2008 are understandable without having the opportunity to review the CS Innovations report 6101-00200 (see Enclosure II). An additional input into the verification and validation process is the activities performed by Nutherm International during commercial grade survey activities through early December 2007. The various survey activities performed by Nutherm International included verification and validation activities. These activities are being documented in a final report from Nutherm and will be provided to the NRC by March 31, 2008. The Attachment provides some additional details and describes the four inputs. WCNOC believes that an onsite visit in March 2008 is not necessary with the submittal of the information in Enclosure II and the additional documentation to be submitted by March 31, 2008.
Enclosures II, V, and VIII provide proprietary CS Innovations LLC documents. As Enclosures II, V, and VIII contain information proprietary to CS Innovations LLC, it is supported by affidavits signed by CS Innovations LLC, the owner of the information. The affidavits sets forth the basis on 'which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390 of the Commission's regulations. Accordingly, it is respectfully requested that the information, which is proprietary to CS Innovations, be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commission's regulations. The affidavits, along with a CS Innovations LLC authorization letters, 91000-00017, 91000-00018, and 91000-00019, "Application for Withholding Proprietary Information from Public Disclosure," is contained in Enclosures Ill, VI, and IX.
Enclosure XI provides the proprietary WCNOC Report "ALS Architecture Evaluation," Rev. 0.
Enclosure XII provides the non-proprietary WCNOC Report "ALS Architecture Evaluation," Rev.
- 0. Enclosure XIV provides the proprietary WCNOC Report "MSFIS D3 Assessment," Rev. 1.
Enclosure XV provides the non-proprietary WCNOC Report "MSFIS D3 Assessment," Rev. 1.
As Enclosures Xl and XIV contains information proprietary to WCNOC, it is supported by an affidavit signed by WCNOC, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.390 of the Commission's regulations. Accordingly, it is respectfully requested that the information, which is proprietary to WCNOC, be withheld from public disclosure in accordance with 10 CFR 2.390 of the Commission's regulations. This affidavit is contained in Enclosure XVI.
WCNOC is providing only proprietary versions of Enclosures II, V, VIII, and XIII as a non-proprietary version would be of no value to the public due to the extent of the proprietary information.
The documentation provided in the Enclosures 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.
ET 08-0014 Page 3 of 4 If you have any questions concerning this matter, please contact me at (620) 364-4084, or Mr.
Richard D. Flannigan at (620) 364-4117.
Terry J. Garrett TJG/rlt Attachment Il Submittal of Additional/Revised Documentation List of Regulatory Commitments Enclosure I WCNOC MSFIS V & V Report, Rev. 2.1 II CS Innovations Report 6101-00200, "MSFIS V & V Report," Rev. 2 III CS Innovations Letter 9100-00017, "Application for Withholding Proprietary Information from Public Disclosure" IV WCNOC Configuration Management Plan, Rev. 2 V CS Innovations Report 6002-00002, "ALS Configuration Management Plan," Rev. 1 VI CS Innovations Letter 9100-00019, "Application for Withholding Proprietary Information from Public Disclosure" VII WCNOC Quality Assurance Plan, Rev. 1 VIII CS Innovations Report 6002-00001, "ALS Quality Assurance Plan, Rev. 1 IX CS Innovations Letter 9100-00018, "Application for Withholding Proprietary Information from Public Disclosure" X WCNOC Maintenance Plan, Rev. 1 Xl WCNOC ALS Architecture Evaluation, Rev.0, Proprietary XII WCNOC ALS Architecture Evaluation, Rev.0, Non-Proprietary XIII WCNOC Operation Plan, Rev. 1 XIV WCNOC MSFIS D3 Assessment, Rev. 1, Proprietary XV WCNOC MSFIS D3 Assessment, Rev. 1, Non-Proprietary XVI WCNOC Affidavit for Withholding Proprietary Information from Public Disclosure cc: E. E. Collins (NRC), w/a J. N. Donohew (NRC), w/a V. G. Gaddy (NRC), w/a B. K. Singal (NRC), w/a Senior Resident Inspector (NRC), w/a
ET 08-0014 Page 4 of 4 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//arrett Vice P, esident Engineering SUBSCRIBED and sworn to before me this day of 2008.
GA AYLE SHEPHEARDi Notary PJblic RIM Notay Public - tate of KansasI My Appt. Exire", ?11 LI/d_ I Expiration Date ,/, qP l
Attachment I to ET 08-0014 Page 1 of 3 Submittal of Additional/Revised Documentation 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 the Main Steam and Feedwater Isolation System (MSFIS) controls. The Enclosures to this letter provides documentation committed to be submitted by February 29, 2008 in Reference 2.
WCNOC MSFIS V & V Report, Rev. 2.1 Revision 2.1 of this report includes as revised Requirements Traceability Matrix as discussed in Reference 3 and addresses Staff comments provided in Reference 4.
Reference 3 provided Revision 2 to the Wolf Creek Nuclear Operating Corporation (WCNOC)
System Verification and Validation Report as committed to in Reference 2. On February 22, 2008, the NRC Project Manager provided by electronic mail the NRC staff concerns associated with the WCNOC System Verification and Validation Report and subsequently indicated the staff request for a site visit in March 2008. WCNOC did not clearly communicate that there are four inputs into the Verification and Validation (V & V) Process. The Table in Reference 2 indicated that verification and validation reports on the design, implementation, and test activities would be submitted by February 29, 2008. The WCNOC response for this item is to submit the CS Innovations report 6101-00200, "MSFIS V & V Report." The concerns identified on February 22, 2008 are understandable without having the opportunity to review the CS Innovations report 6101-00200 (see Enclosure II). An additional input into the V & V Process is the activities performed by Nutherm International during commercial grade survey activities through early December 2007. The various survey activities performed by Nutherm International included verification and validation activities. These activities are being documented in a final report from Nutherm and will be provided to the NRC by March 31, 2008.
WCNOC believes that an onsite visit in March 2008 is not necessary with the submittal of the information in Enclosure II and the additional documentation to be submitted by March 31, 2008.
The V&V Process for the MSFIS controls project consists of four input levels (see Figure 1 in Enclosure I).
- 1) The first input level was performed by CS Innovations. The first input level is a detailed level of verification and validation. CS Innovations Report 6002-00002, "MSFIS V & V Report," Rev. 2, is provided in Enclosure I1. The CS Innovations verification and validation activities included the following:
- a. Analyzing system requirements to determine if they are consistent with, and within the scope of the system
- b. Assuring that the requirements are testable and capable of being satisfied
- c. Development of test beds and test vectors
Attachment I to ET 08-0014 Page 2 of 3
- d. Prepare Acceptance Test Plans and verification matrixes, including test specifications and unit test plans
- e. Conducting informal reviews and walkthroughs and inspections of the design
- f. Conducting Code inspections and/or walkthroughs
- g. Conducting Unit testing software and data structures
- h. Development of detailed test procedures for the next two phases
- i. Conducting tests per test procedures
- j. Documenting test performance, test completion, and conformance of test results versus expected results
- k. Providing a test report that includes a summary of non-conformances found during testing I. Locating, recording, correcting, and retesting non-conformances
- m. By test, analysis, and inspection, demonstrating that the developed system meets its functional, performance, and interface requirements
- 2) The second input level was performed by Nutherm International. As discussed in Reference 2, WCNOC initially contracted with Nutherm for Commercial Grade Dedication activities and subsequently procured the equipment from CS Innovations as safety related. However, the activities Nutherm International has performed are valid verification and validation activities. These activities include the following:
- a. Analyzing system requirements to determine if they are consistent with, and within the scope of the system
- b. Assuring that the requirements are testable and capable of being satisfied
- c. Prepare Final Acceptance Test Procedure
- d. Conduct Final Acceptance Test
- e. Conducting surveys and audits of CS Innovations, including thread audits of the FPGA development
- f. Verification of all documentation vs. the actual equipment
Attachment I to ET 08-0014 Page 3 of 3
- 3) The third input level was performed by the V & V Engineer. The third input level of verification and validation is a periphery level review where the verification and validation activities involve the verification of the outputs from CS Innovations and Nutherm International as well as the final results of the Final Acceptance Test, Site Acceptance Test, and Post Installation Test. As noted in the Staffs concerns (provided by electronic mail on February 22, 2008) the V & V Engineers efforts have been hardware focused.
The V & V Engineer performed VHDL code reviews early in the project, but has not performed detailed "software based" activities in the later stages of the project. WCNOC has relied on CS Innovations for the detailed verification and validation of these activities, as CS Innovations has employed an independent team to perform these activities. The V & V Engineer's activities are provided below.
- a. Analyzing system requirements to determine if they are consistent with, and within the scope of the system
- b. Assuring that the requirements are testable and capable of being satisfied
- c. Analyzing verification and validation activities performed by CS Innovations
- d. Analyzing verification and validation activities performed by Nutherm International
- e. Verification and validation of final design products
- f. Conduct Post Installation Test
- 4) The fourth level is to be performed by WCNOC Engineering during the final review of the Design Change Package. During this level of V&V the final output documents, drawings, and equipment are verified for correctness as it applies to the installation at WCGS.
This is the traditional verification and validation for design changes at WCGS.
References
- 1. WCNOC letter ET 07-0004, "Revision 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),"
March 14, 2007.
- 2. WCNOC letter ET 08-0004, "Additional Information Regarding Main Steam and Feedwater Isolation System (MSFIS) Controls Modification," January 18, 2008.
- 3. WCNOC letter ET 08-0008, "Additional Information Regarding Main Steam and Feedwater Isolation System (MSFIS) Controls Modification," January 31, 2008.
- 4. NRC letter, "Wolf Creek Generating Station - Request for Additional Information for the Main Steam and Feedwater Isolation System Modification (TAC NO. MD4839), December 7, 2007.
Attachment II to ET 08-0014 Page 1 of I LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by WCNOC in this document. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr. Richard Flannigan at (620) 364-4117.
COMMITMENT Due DatelEvent An additional input into the verification and validation process March 31, 2008 is the activities performed by Nutherm International during the initial commercial grade survey activities. The various survey activities performed by Nutherm International included verification and validation activities. These activities are being documented in a final report from Nutherm and will be provided to the NRC by March 31, 2008.