|
---|
Category:License-Operator Examination Report
MONTHYEARIR 05000390/20223012022-09-30030 September 2022 NRC Operator License Examination Report 05000390/2022301 and 050000391/2022301 IR 05000390/20203012021-01-19019 January 2021 Reissue - Watts Bar Nuclear Plant - NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 ML20281A5622020-10-0606 October 2020 NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 IR 05000390/20193012019-10-24024 October 2019 NRC Operator License Examination Report 05000390/2019301 and 05000391/2019-301 ML18044A9892018-02-13013 February 2018 Notification of Licensed Operator Initial Examination 05000390/2018301, 05000391/2018301 IR 05000390/20163012016-09-16016 September 2016 NRC Operator License Examination Report 05000390/2016301 and 05000391/2016301 IR 05000390/20153012015-09-0303 September 2015 Er 05000390/2015301; 07/20-22/2015 & July 29, 2015, Written Examination, July 29, 2015; Watts Bar Nuclear Power Plant; Operator License Examinations IR 05000390/20133022013-12-11011 December 2013 Er 05000390-13-302; Operating Test, October 22 - 25, 2013, & Written Examination, October 30, 2013; Watts Bar Nuclear Power Plant; Operator License Examinations IR 05000390/20113022012-01-19019 January 2012 Er 05000390/11-302, on December 19-22, 2011, Watts Bar Nuclear Plant - NRC Operator Licensing Examination Report IR 05000390/20113012011-08-10010 August 2011 Er 05000390-11-301, on June 6 - 16, 2011, and June 22, 2011, Watts Bar Nuclear Plant Unit 1, Licensed Operator Examinations IR 05000390/20103012010-11-0909 November 2010 NRC Operator License Examination Report 05000390-10-301 IR 05000390/20093022010-01-20020 January 2010 Operator License Examinations Report 05000390-09-302 on 11/30/09 - 12/02/09 for Watts Bar IR 05000390/20093012009-07-0606 July 2009 Er 05000390-09301, Operating Test, May 18-21, 2009 & Written Exam, May 27, 2009, Watts Bar, Operator License Examinations IR 05000390/20063012006-10-24024 October 2006 Er 05000390-06-301; 09/05-13/2006 & 09/18/2006; Watts Bar, Unit 1, Licensed Operator Examinations IR 05000390/20023012003-01-17017 January 2003 NRC Examination Report 05000390/02-301, on 11/26/2002 & 12/09-12/2002, Licensed Operator Examinations 2022-09-30
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] |
Text
November 9, 2010
Mr. R. Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT: WATTS BAR NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000390/2010301
Dear Mr. Krich:
During the period of August 23 - 31, 2010, the Nuclear Regulatory Commission (NRC) administered operating tests to employees of your company who had applied for licenses to operate the Watts Bar Nuclear Plant. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests and the written examination submittal with those members of your staff identified in the enclosed report. The written examination was administered by your staff on September 22, 2010.
Four Reactor Operator (RO) and eight Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. Three SRO applicants failed the written examination. There were no post-examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2.
The initial written SRO examination submitted by your staff failed to meet the guidelines for quality contained in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1, as described in the enclosed report.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room).
TVA 2 If you have any questions concerning this letter, please contact me at (404) 997-4550.
Sincerely,/RA/
Malcolm T. Widmann, Chief Operations Branch Division of Reactor Safety
Docket No: 50-390 License No: NPF-90
Enclosures:
1. Report Details. 2. Simulator Fidelity Report.
cc w/encl: (See page 3)
ML ________________ X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII: DRP SIGNATURE EXL /RA/ KDS /RA/ PGC /RA/MTW /RA/EG/R A NAME Glaska ELea MRiches MWidmann EGuthrie DATE 11/4/2010 11/5/2010 11/09/2010 11/09/2010 11/9/2010 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO TVA 3 cc w/encl: D. E. Grissette Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 G. A. Boerschig Plant Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381 M. K. Brandon Manager Licensing and Industry Affairs Watts Bar Nuclear Plant Electronic Mail Distribution
E. J. Vigluicci Assistant General Counsel Tennessee Valley Authority 6A West Tower 400 West Summit Hill Drive Knoxville, TN 37902 County Mayor P.O. Box 156 Decatur, TN 37322
Division of Radiological Health TN Dept. of Environment & Conservation 401 Church Street Nashville, TN 37243-1532
William Thompson Training Manager Watts Bar Nuclear Plant Electronic Mail Distribution Ann Harris 341 Swing Loop Rockwood, TN 37854
Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II Docket No.: 50-390 License No.: NPF-90
Report No.: 05000390/2010301 Licensee: Tennessee Valley Authority Facility: Watts Bar Location: Spring City, Tennessee
Dates: Operating Test - August 23-31, 2010 Written Examination - September 22, 2010 Examiners: G. Laska, Chief Examiner, Senior Operations Examiner E. Lea, Senior Operations Engineer M. Riches, Operations Engineer Approved by: Malcolm T. Widmann, Chief Operations Branch Division of Reactor Safety Enclosure 1 SUMMARY OF FINDINGS
ER 05000390/2010301; operating test, August 23 - 31 2010, & written exam, September 22, 2010; Watts Bar; Operator License Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.
Members of the Watts Bar staff developed both the operating tests and the written examination. The NRC developed the written examination outlines. The initial written SRO examination submittal did not meet the quality guidelines contained in NUREG-1021.
The NRC administered the operating tests during the period August 23 - 31, 2010. Members of the Watts Bar training staff administered the written examination on September 22, 2010. Four Reactor Operator (RO) and eight Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. Three SRO applicants failed the written examination. Ten applicants were issued licenses commensurate with the level of examination administered.
Two SRO applicants passed the operating test, but passed the SRO portion of the written examination with a score less than 74%. These applicants were issued a letter stating that they passed the examination and issuance of their license has been delayed pending any written examination appeal that may impact the licensing decision for their application.
There were no post-examination comments.
No findings of significance were identified.
Enclosure 1 REPORT DETAILS
4. OTHER ACTIVITIES 4OA5 Operator Licensing Examinations
a. Inspection Scope Members of the Watts Bar Nuclear Power Plant staff developed both the operating tests and the written examination. All examination material was developed in accordance with the guidelines contained in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The NRC examination team reviewed the proposed examination. Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021 and incorporated into the final version of the examination materials.
The NRC reviewed the licensee's examination security measures while preparing and administering the examinations in order to ensure compliance with 10 CFR §55.49,
"Integrity of examinations and tests."
The NRC examiners evaluated four Reactor Operator (RO) and eleven Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period August 23 -31 2010.
Members of the Watts Bar Nuclear Power Plant training staff administered the written examination on September 22, 2010. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Watts Bar Nuclear Plant, met the requirements specified in 10 CFR Part 55, "Operators' Licenses."
b. Findings The NRC determined that the licensee's examination submittal was outside the range of acceptable quality specified by NUREG-1021. The initial written SRO examination submittal was outside the range of acceptable quality because more than 20%, (13 of 25) questions sampled for review contained unacceptable flaws. Individual questions were evaluated as unsatisfactory for the following reasons:
- 1 question failed to meet the K/A statement contained in the examination outline.
- 6 questions contained two or more implausible distractors.
- 10 questions on the SRO examination were not written at the SRO license level.
- 4 questions contained multiple unacceptable flaws.
Administration of the written examination was delayed, in part, because the quality of the licensee's examination submittal was unacceptable. Additional delays were incurred due to the licensee's request to change/replace questions on the originally approved examination. Future examination submittals need to incorporate lessons learned.
The NRC determined that the licensee's initial operating test submittal was within the range of acceptability expected for a proposed examination.
4 Enclosure 1 Four Reactor Operator (RO) and eight Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. Three SRO applicants failed the written examination. Ten applicants were issued licenses commensurate with the level of examination administered.
Two SRO applicants passed the operating test, but passed the SRO portion of the written examination with scores between 70 and 74%. These applicants were issued a letter stating that they passed the examination and issuance of their license has been delayed pending any written examination appeal that may impact the licensing decision for their application.
Copies of all individual examination reports were sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training.
The licensee submitted no post-examination comments on either the operating test or the written examination. A copy of the final written RO and SRO examinations and answer keys, with all changes incorporated may be accessed not earlier than October 26, 2012, in the ADAMS system (ADAMS Accession Number(s) ML102940196 and ML102940181).
4OA6 Meetings, Including Exit Exit Meeting Summary On August 31, 2010, the NRC examination team discussed generic issues associated with the operating test with Mr. Mark McFadden, Operations Manager, and members of the Watts Bar staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.
KEY POINTS OF CONTACT Licensee personnel G. Boerschig, Watts Bar Nuclear Plant General Manager R. Crews, Operations Training Manager N. Good, Training Simulator Manager D. Grissette, Watts Bar Nuclear VP J. Dalton, ILT Supervisor B. Hunt, Ops Superintendent M. McFadden, Operations Manager R. Mende, Director, U1/U2 Integration R. Milner, GM Corporate Nuclear Training C. Riedl, Licensing S. Smith, Operations Facility Representative W. Thompson, Site Training Director NRC personnel R. Monk, Senior Resident Inspector
Enclosure 2 SIMULATOR FIDELITY REPORT
Facility Licensee: Watts Bar Nuclear Plant Facility Docket No.: 05000390/2010-301
Operating Test Administered: August 23 - 31, 2010.
This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with Inspection Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations.
While conducting the simulator portion of the operating test, examiners observed the following:
Item Boration did not start when an operator attempted to borate.
MSR Switches failed to operate when manipulated.
"B" Pressurizer Heaters failed to turn off when operator took control switch to off.
Valves 1-LCV-62-135 and 1-LCV-62-136 closure times differed.
The ICS hard drive failed just prior to prep week and had communication issues Description During scenario 1, the make-up system failed to start in the borate mode when an operator attempted to start a boration to facilitate a plant downpower. DR3177 was written to address the issue.
During scenario 4, an operator made several attempts to close MSR valves in accordance with Attachment 2 of E-3 Steam Generator tube Rupture, and the switches failed to work. DR3187 was written to address the issue.
During one scenario, an operator went to off on the "B" pressurizer heaters and they failed to de-energize. DR3190 was written to address the issue.
During the administration of JPM B.1.c, Perform ES-1.3 "Transfer to Containment Sump" 1-LCV-62-135 took almost 1 minute to close, and 1-LCV-62-136 closed almost instantaneously, operators believed that the valves should take the same amount of time to close. DR3186 was written to address the issue.
During prep week delays were incurred due to the failure of the ICS hard drive the week before and ensuing communication issues between CERPI and ICS. DR3169 was written to address the issue.