Similar Documents at Byron |
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Category:Inspection Report
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 IR 05000454/20230012023-05-0505 May 2023 Integrated Inspection Report 05000454/2023001 and 05000455/2023001 IR 05000454/20230102023-04-19019 April 2023 License Phase 1 Report 05000454/2023010 IR 05000454/20234012023-03-30030 March 2023 Baseline Security Inspection 05000454/2023401; and 05000455/2023401 IR 05000454/20223012023-03-0707 March 2023 NRC Initial License Examination Report 05000454/2022301 and 05000455/2022301 IR 05000454/20220062023-03-0101 March 2023 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2022006 and 05000454/2022006) IR 05000454/20220042023-02-0101 February 2023 Integrated Inspection Report 05000454/2022004 and 05000455/2022004 IR 05000454/20220102023-01-17017 January 2023 Design Basis Assurance Inspection (Programs) Inspection Report Report 05000454/2022010 and 05000455/2022010 IR 05000454/20224032022-12-28028 December 2022 Cyber Security Inspection Report 05000454/2022403 and 05000455/2022403 IR 05000454/20224052022-12-0909 December 2022 Material Control and Accounting Program Inspection Report 05000454/2022405 and 05000455/2022405 IR 05000454/20220032022-11-0707 November 2022 Integrated Inspection Report 05000454/2022003 and 05000455/2022003 BYRON 2022-0072, Steam Generator Tube Inspection Report for Refueling Outage 232022-10-27027 October 2022 Steam Generator Tube Inspection Report for Refueling Outage 23 IR 05000454/20220052022-08-24024 August 2022 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2022005; 05000455/2022005) IR 05000454/20224022022-08-0909 August 2022 Security Baseline Inspection Report 05000454/2022402 and 05000455/2022402 IR 05000454/20220022022-08-0808 August 2022 Integrated Inspection Report 05000454/2022002 and 05000455/2022002 IR 05000454/20220012022-05-0303 May 2022 Integrated Inspection Report 05000454/2022001 and 05000455/2022001 IR 05000454/20224012022-04-0404 April 2022 Security Baseline Inspection Report 05000454/2022401 and 05000455/2022401 IR 05000454/20210062022-03-0202 March 2022 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2021006 and 05000455/2021006) IR 05000454/20210042022-02-11011 February 2022 Integrated Inspection Report 05000454/2021004 and 05000455/2021004 IR 05000454/20210122022-01-0606 January 2022 Biennial Problem Identification and Resolution Inpsection Report 05000454/2021012 and 05000455/2021012 IR 05000454/20213012021-12-17017 December 2021 NRC Initial License Examination Report 05000454/2021301; 05000455/2021301 IR 05000454/20214032021-11-22022 November 2021 Security Baseline Inspection Report 05000454/2021403 and 05000455/2021403 IR 05000454/20210032021-10-29029 October 2021 Integrated Inspection Report 05000454/2021003 and 05000455/2021003 and Exercise of Enforcement Discretion IR 05000454/20214022021-09-28028 September 2021 Security Baseline Inspection Report 05000454/2021402 and 05000455/2021402 IR 05000454/20210052021-09-0101 September 2021 Updated Inspection Plan for Byron Station Units 1 and 2 (05000454/2021005 and 05000455/2021005) IR 05000454/20210022021-08-0404 August 2021 Integrated Inspection Report 05000454/2021002; 05000455/2021002; and 07200068/2021001 IR 05000454/20210112021-05-14014 May 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000454/2021011 and 05000455/2021011 IR 05000454/20215012021-04-21021 April 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2021501 and 05000455/2021501 IR 05000454/20210012021-04-20020 April 2021 Integrated Inspection Report 05000454/2021001 and 05000455/2021001 IR 05000454/20214012021-03-24024 March 2021 Security Baseline Inspection Report 05000454/2021401 and 05000455/2021401 IR 05000454/20180102021-03-19019 March 2021 Closure of Auxiliary Feedwater System Unresolved Item 05000454/2018010-04 and 05000455/2018010-04 IR 05000454/20200062021-03-0404 March 2021 Annual Assessment Letter for Byron Station (Report 05000454/2020006 and 05000455/2020006) IR 05000454/20210102021-02-0909 February 2021 Triennial Fire Protection Inspection Report 05000454/2021010 and 05000455/2021010 IR 05000454/20200042021-01-27027 January 2021 Integrated Inspection Report 05000454/2020004 and 05000455/2020004 IR 05000454/20204032020-12-16016 December 2020 Security Baseline Inspection Report 05000454/2020403 and 05000455/2020403 IR 05000454/20200032020-11-10010 November 2020 Integrated Inspection Report 05000454/2020003 and 05000455/2020003 IR 05000454/20200112020-09-29029 September 2020 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000454/2020011 and 05000455/2020011 IR 05000454/20204022020-09-18018 September 2020 Security Baseline Inspection Report 05000454/2020402 and 05000455/2020402 IR 05000454/20200052020-09-0101 September 2020 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2020005 and 05000455/2020005) IR 05000454/20200022020-07-27027 July 2020 Integrated Inspection Report 05000454/2020002 and 05000455/2020002 IR 05000454/20200012020-04-24024 April 2020 Integrated Inspection Report 05000454/2020001 and 05000455/2020001 IR 05000454/20204012020-03-30030 March 2020 Security Baseline Inspection Report 05000454/2020401 and 05000455/2020401 IR 05000454/20190062020-03-0303 March 2020 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2019006 and 05000455/2019006) 2024-02-02
[Table view] Category:Letter
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline2023-11-17017 November 2023 Unit 2 - Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
[Table view] |
Inspection Report - Byron - 2018010 |
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Text
March 19, 2021
SUBJECT:
BYRON STATION - CLOSURE OF AUXILIARY FEEDWATER SYSTEM UNRESOLVED ITEM 05000454/2018010-04 AND 05000455/2018010-04
Dear Mr. Rhoades:
On December 4, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station and discussed the results of this inspection with Mr. K. McGuire and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000454 and 05000455 License Nos. NPF-37 and NPF-66
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000454 and 05000455 License Numbers: NPF-37 and NPF-66 Report Numbers: 05000454/2020010 and 05000455/2020010 Enterprise Identifier: I-2020-010-0055 Licensee: Exelon Generation Company, LLC Facility: Byron Station Location: Byron, IL Inspection Dates: April 13, 2020 to December 04, 2020 Inspectors: E. Sanchez Santiago, Senior Reactor Inspector Approved By: Karla K. Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Byron Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000454, Use of 10 CFR 50.54(x) for 71111.21M Closed 05000455/2018010-04 Unit AFW Cross-Tie
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
INSPECTION RESULTS
Unresolved Item Use of 10 CFR 50.54(x) for Unit AFW Cross-Tie 71111.21M (Closed) URI 05000454,05000455/2018010-04
Description:
In 2008, the licensee added steps to Emergency Operating Procedure (EOP)1/2BFR-H.1, Response to Loss of Secondary Heat Sink, to use the motor-driven auxiliary feedwater (MDAFW) train of a non-accident unit to combat a loss of all feedwater event in the opposite unit by using a recently installed unit cross-tie. The EOPs also directed operators to enter the technical specification limiting condition for operation action statement for the unit donating the MDAFW train because the MDAFW trains were not licensed to be shared between the reactor units.
In 2011, the resident inspectors documented a Severity Level IV non-cited violation (NCV) of 10 CFR 50.59 after determining the licensees 2008 EOP change resulted in more than a minimal increase in the likelihood of occurrence of a malfunction of a structure, system or component important to safety. Specifically, the Updated Final Safety Analysis Report described the auxiliary feedwater (AF) trains as non-shared systems. This violation was documented in Inspection Report 05000454/2011004; 05000455/2011004 as NCV 05000454/2011004-02; 05000455/2011004-02, Modification of the Auxiliary Feedwater System Without Prior NRC Approval (REF: ADAMS Accession No. ML113070678).
As a corrective action to this NCV, the licensee removed the steps in EOP 1/2BFR-H.1, "Response to Loss of Heat Sink," that directed the unit cross-tie to be used and removed credit for the cross-tie in the stations Probabilistic Risk Assessment model. On August 8, 2017, the licensee added direction in EOP 1/2BFR-H.1 to use the AF cross-tie by invoking 10 CFR 50.54(x). The procedure change included a note which stated, If at any time it has been determined that restoration of feed flow to any SG [steam generator] is untimely or may be ineffective in heat sink restoration, then the AF crosstie should be implemented per Step 5 (Page 8). The licensee also added a caution which stated, The AF crosstie should be implemented per Step 5 if other attempts to restore feed flow to the SG(s) will not prevent the initiation of feed and bleed. The DBAI team was concerned the note and caution provided direction to initiate the AF unit cross-tie before bleed and feed, rather than the instruction being provided in the actual procedure step.
During the 2018 design basis assurance inspection, the inspectors initiated an unresolved item to document their concerns associated with the licensees actions in response to the 2011 SLIV NCV. Specifically, the inspectors challenged the use of 10 CFR 50.54(x) to implement this change. In addition, the inspectors noted that the licensees 10 CFR 50.59 screening for the procedure change did not include or evaluate the aforementioned note and caution statements to determine whether the 2017 EOP change required prior NRC approval via a license amendment.
Since 2018, the NRC has evaluated the details associated with the above concerns, engaged NRC staff experts, and reviewed licensee procedures and owners group documents related to the technical aspects of the issue to determine whether a performance deficiency or violation occurred. Based on this review, the inspectors did not identify a performance deficiency or violation of requirements.
Specifically, regarding the concern the licensee used 10 CFR 50.54(x) to implement a permanent change, the inspector concluded the 2017 EOP revision which added the note, caution and the step for implementing the AF cross-tie by invoking 10 CFR 50.54(x) did not constitute a change as defined in 10 CFR 50.59, Changes, tests and experiments. Title 10 CFR 50.59 defines change as, a modification or addition to, or removal from, the facility or procedure that affects a design function, method of performing or controlling the function, or an evaluation that demonstrated that intended functions will be accomplished. Also, NEI 96-07, Section 1.2.4, Relationship of 10 CFR 50.59 to 10 CFR 50.2 Design Bases, states, 10 CFR 50.59 controls changes to both 10 CFR 50.2 design basis and supporting design information contained in the Updated Final Safety Analysis Report. The AF cross-tie would be implemented during beyond design basis events and would require invoking 10 CFR 50.54(x), therefore the change falls outside the site's licensing and design basis.
The inspectors also reviewed the URI concern:
- (1) the added note and caution were the only procedure provisions that provided direction on when to use the MDAFW cross-tie; and (2)those procedure provisions were not included in the 10 CFR 50.59 screening. Per the above discussion, the inspectors concluded the change did not fall under the requirements of 10 CFR 50.59. Regarding the caution statement providing direction, the inspectors noted that the caution includes a should statement which per procedure AD-AA-101-1002, Writers Guide for Procedures and T&RM, denotes a management expectation but does not require or direct a specific action. When the licensee was questioned on the purpose of the caution statement, they indicated it was to let the operators know the AF cross-tie should be implemented after all other options are exhausted and feed and bleed was the only remaining alternative. The licensee also stated that per EOP 1/2BFR-H.1, Step 2, "Check if Bleed and Feed is Required," if the criteria described in the procedure for initiating feed and bleed are met, the licensed operators would be required to implement the bleed and feed actions.
There is no allowance to bypass actions related to initiating bleed and feed, once the criteria are met. The licensee also stated the bleed and feed actions would not be delayed to allow implementation of the AF cross-tie. Per the licensee, the added note and caution did not require the use of the cross-tie prior to implementing feed and bleed. Step 5 of procedure 1/2BFR-H.1, "Crosstie Train A AF From Unit 1/2," stated, "Shift Manager has: Determined other heat sink restoration efforts are not available or are untimely; Has implemented 10 CFR 50.54(x); Approved implementation of 1BFSG-3, Alternate Low Pressure Feedwater for AF crosstie." Based on these instructions, the decision to invoke 10 CFR 50.54(x) and implement the cross-tie would be made by the shift manager. The caution also served the purpose of informing the operators that the implementation of the AF cross-tie would require invoking 10 CFR 50.54(x). Per procedure AD-AA-101-1002, one of the purposes of a caution statement is to alert personnel of violations of rules, regulations or work practices. Therefore, the inspectors did not identify a performance deficiency associated with these actions.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.21M Engineering 362168 Installation of the Final Phase of the Motor-Driven Auxiliary 0
Changes Feedwater Pump Crosstie Line between Units 1&2
Miscellaneous Email AFW Issue - 5054x Licensees_BGH.docx 08/28/2019
Federal Register Applicability of License; Conditions and Technical 04/01/1983
Vol. 48, No. 64 Specifications in an Emergency
ML043440415 Letter to A. Scherer (Southern California Edison) from 02/05/1999
J. Moore (NRC)
NEI 96-07 Guidelines for 10 CFR 50.59 Implementation 1
Procedures 1BFR-H.1 Response to Loss of Secondary Heat Sink 300
AD-AA-101-1002 Writer's Guide for Procedures and T&RM 18
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