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Category:Inspection Report
MONTHYEARIR 05000445/20240032024-10-30030 October 2024 Integrated Inspection Report 05000445/2024003 and 05000446/2024003 IR 05000445/20244042024-10-23023 October 2024 Security Baseline Inspection Report 05000445/2024404 and 05000446/2024404 (Public) IR 07200074/20244012024-10-10010 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200074/2024401 Public IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 IR 05000445/20240012024-04-26026 April 2024 Integrated Inspection Report 05000445/2024001 and 05000446/2024001 IR 05000445/20244022024-04-17017 April 2024 Security Baseline Inspection Report 05000445/2024402 and 05000446/2024402 (Full Report) IR 05000445/20243012024-02-28028 February 2024 Notification of NRC Initial Operator Licensing Examination 05000445/2024301 and 05000446/2024301 IR 05000445/20230062024-02-28028 February 2024 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 Reports 05000445/2023006 and 05000446/2023006 IR 05000445/20230132024-01-31031 January 2024 License Renewal Inspection Report 05000445/2023013 and 05000446/2023013 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 ML24018A1072024-01-18018 January 2024 – Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 IR 05000445/20230052023-08-23023 August 2023 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2023005 and 05000446/2023005)- Mid Cycle Letter 2023 IR 05000445/20233012023-08-21021 August 2023 NRC Examination Report 05000445/2023301 and 05000446/2023301 IR 05000445/20230112023-07-20020 July 2023 Fire Protection Team Inspection Report 05000445/2023011 and 05000446/2023011 IR 05000445/20230022023-07-14014 July 2023 Integrated Inspection Report 05000445/2023002 and 05000446/2023002 IR 05000445/20230012023-04-13013 April 2023 Integrated Inspection Report 05000445/2023001 and 05000446/2023001 IR 05000445/20234012023-03-29029 March 2023 NRC Security Inspection Report 050004452023401 and 050004462023401 (Cover Letter Only) IR 05000445/20230102023-03-24024 March 2023 Biennial Problem Identification and Resolution Inspection Report 05000445/2023010 and 05000446/2023010 IR 05000445/20220062023-03-0101 March 2023 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2022006 and 05000446/2022006) IR 05000445/20220042023-01-26026 January 2023 Integrated Inspection Report 05000445/2022004 and 05000446/2022004 IR 05000445/20220102023-01-23023 January 2023 TI-194 Report 05000445/2022010 and 05000446/2022010 IR 05000445/20224202022-12-0707 December 2022 Security Baseline Inspection Report Cover Letter 05000445/2022420 and 05000446/2022420 ML22319A0732022-11-15015 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22299A0562022-11-0101 November 2022 Integrated Inspection Report 05000445/2022003 and 05000446/2022003 and Notice of Violation IR 05000445/20220032022-11-0101 November 2022 Integrated Inspection Report 05000445/2022003 and 05000446/2022003 and Notice of Violation IR 05000445/20220052022-08-22022 August 2022 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2022005 and 05000446/2022005) IR 05000445/20224032022-08-0909 August 2022 NRC Security Inspection Report 05000445/2022403 and 05000446/2022403 (Full Report) IR 05000445/20220022022-08-0505 August 2022 2nd Quarter 2022 Integrated Inspection Report 05000445/2022002 and 05000446/2022002 IR 05000445/20224012022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000445/2022401; 05000446/2022401 ML22174A2792022-06-22022 June 2022 Notification of NRC Evaluations of Changes, Tests and Experiments Inspection (05000445/2022003 and 05000446/2022003) and Request for Information IR 05000445/20220012022-04-26026 April 2022 Integrated Inspection Report 05000445/2022001 and 05000446/2022001 IR 05000445/20224022022-04-25025 April 2022 Security Baseline Inspection Report 05000445/2022402 and 05000446/2022402 IR 05000445/20210062022-03-0202 March 2022 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2021006 and 05000446/2021006) IR 05000445/20200112022-02-0707 February 2022 Amended - Comanche Peak Nuclear Power Plant - Triennial Fire Protection Inspection Report 05000445/2020011 and 05000446/2020011 and Notice of Violation IR 05000445/20210042022-01-25025 January 2022 Integrated Inspection Report 05000445/2021004 and 05000446/2021004 IR 05000445/20210122022-01-13013 January 2022 TI-194 Report 05000445/2021012 and 05000446/2021012 IR 05000445/20214052021-12-15015 December 2021 Security Baseline Inspection Report 05000445/2021405 and 05000446/2021405 IR 05000445/20214032021-12-0909 December 2021 Powerplant, Units 1 and 2 - Security Baseline Inspection Report 05000445/2021403 and 05000446/2021403 IR 05000445/20210032021-11-0303 November 2021 Integrated Inspection Report 05000445/2021003 and 05000446/2021003 IR 05000445/20213012021-10-19019 October 2021 NRC Examination Report 05000445/2021301 and 05000446/2021301 IR 05000445/20210102021-10-0707 October 2021 Biennial Problem Identification and Resolution Inspection Report 05000445/2021010 and 05000446/2021010 IR 05000445/20214012021-09-0909 September 2021 Security Baseline Inspection Report 05000445/2021401 and 05000446/2021401 IR 05000445/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2021005 and 05000446/2021005) IR 05000445/20214022021-08-19019 August 2021 Security Baseline Inspection Report 05000445/2021402 and 05000446/2021402 IR 05000445/20210022021-08-10010 August 2021 Integrated Inspection Report 05000445/2021002 and 05000446/2021002 2024-08-15
[Table view] Category:Letter
MONTHYEARIR 05000445/20240032024-10-30030 October 2024 Integrated Inspection Report 05000445/2024003 and 05000446/2024003 IR 05000445/20244042024-10-23023 October 2024 Security Baseline Inspection Report 05000445/2024404 and 05000446/2024404 (Public) IR 07200074/20244012024-10-10010 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200074/2024401 Public 05000445/LER-2024-002-01, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-10-0303 October 2024 Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions 05000446/LER-2024-001-01, Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-09-30030 September 2024 Unit Two, Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24031A6322024-09-11011 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4), Final Safety Analysis Report Update Schedule (EPID L-2023-LLE-0023) - Letter ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24194A1332024-08-28028 August 2024 Issuance of Amendment Nos. 190 and 190, Respectively, Revision to Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24228A2252024-08-22022 August 2024 Relief to Use Later Code Edition for Inservice Inspection Program ML24179A0772024-08-20020 August 2024 Issuance of Amendment Nos. 189 and 189, Respectively, Extension of Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000445/20240052024-08-15015 August 2024 Updated Inspection Plan for Comanche Peak Nuclear Power Plant, Units 1 and 2 (Report 05000445/2024005 and 05000446/2024005) CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants 05000445/LER-1924-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator 05000446/LER-2024-001, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications 05000445/LER-2024-001, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma 2024-09-30
[Table view] |
See also: IR 05000445/2011004
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION IV
612 EAST LAMAR BLVD, SUITE 400
ARLINGTON, TEXAS 76011-4125
June 30, 2011
Rafael Flores, Senior Vice President
and Chief Nuclear Officer
Luminant Generation Company LLC
Comanche Peak Nuclear Power Plant
P.O. Box 1002
Glen Rose, TX 76043
SUBJECT: COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 -
NOTIFICATION OF INSPECTION (NRC INSPECTION REPORT
05000445/2011004; 05000446/2011004) AND REQUEST FOR INFORMATION
Dear Mr. Flores:
On August 15, 2011, the U.S. Nuclear Regulatory Commission (NRC) will begin the onsite
portion of the Gas Accumulation Management in Emergency Core Cooling, Decay Heat
Removal, and Containment Spray Systems Temporary Instruction at your Comanche Peak
Nuclear Power Plant, Units 1 and 2. This inspection will be performed in accordance with NRC
Temporary Instruction (TI) 2515/177.
Experience has shown that this inspection is resource intensive both for the NRC inspectors
and your staff. In order to minimize the impact to your onsite resources and to ensure a
productive inspection, we have enclosed a request for documents needed for this inspection.
The documents have been divided into two groups.
- The first group lists information necessary for our initial inspection scoping and in-office
preparation activities. This information should be separated by information request number,
especially if provided electronically (e.g., folder with the information request number). This
information should be available to the inspector no later than August 1, 2011. Upon review of
these documents, the inspectors will select additional documentation for review upon arrival.
By August 10, 2011, the inspector will communicate the initial selected samples.
- The second group of documents requested is needed to support our onsite inspection
activities. This set of documents should be available to the inspector on August 15, 2011. It
is also requested that corrective action documents and responses to questions developed
during the inspection be provided to the inspector as the documents are generated.
We have discussed the schedule for these inspection activities with your staff and understand
that our regulatory contact for this inspection will be Gary Merka of your licensing organization.
If there are any questions about this inspection or the materia! requested, please contact the
inspector, Matt Young, at 817-276-6545 or by email at '-'-==:.J:-==~=~='
-2-
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, control number
3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,
a request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget control number.
In accordance with Code of Federal Regulations, Title 10, Part 2.390 of the NRC's Rules of
Practice, a copy of this letter and its enclosure will be available electronically for public
inspection in the NRC Public Document Room or from the Publicly Available Records (PARS)
component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web
site at (the Public Electronic Reading Room).
Thomas R. Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Dockets: 50-445; 50-446
Licenses: NPF-87; NPF-89
Enclosure: Management of Gas Accumulation in Emergency Core Cooling, Decay Heat
Removal, and Containment Spray Systems Temporary Instruction Document Request
cc w/encl:
Distribution via ListServ for Comanche Peak
MANAGEMENT OF GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY
HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS TEMPORARY INSTRUCTION
DOCUMENT REQUEST
inspection Report: 05000445/2011004; 05000446/2011004
On-site Inspection Dates: August 15-19, 2011
Inspection Procedure: TI 2515/177, "Management of Gas Accumulation in
Emergency Core Cooling, Decay Heat Removal, and
Containment Spray Systems"
Lead InspectorlTeam Leader: Matt Young
817 -276-6545
Matt.young@nrc.gov
The following information should be sent to the Region IV office in hard copy or electronic
format (ims.certrec.com or compact disc, preferred), in care of Matt Young, to facilitate the
selection of specific items that will be reviewed during the onsite inspection week. The
inspector will select specific items from the information requested below and then request from
your staff additional documents needed during the onsite inspection weeks. Also, we request
that you categorize the documents in your response with the numbered list below. Please
provide requested documentation electronically if possible. If requested documents are large
and only hard copy formats are available, please inform the inspector(s), and provide subject
documentation during the first day of the onsite inspection. If you have any questions regarding
this information request, please call the inspector as soon as possible.
I. Information Requested By August 1, 2011
1. List of corrective action program documents (with a short description) associated with
Generic Letter (GL) 2008-01, voids in piping, and pressure transients for the previous
three years.
2. List of changes (with a short description and tracking number) to the final safety analysis
report (FSAR), technical specifications, technical specification bases, and technical
requirements manual associated with the resolution of GL 2008-01.
3. List of calculations associated with GL 2008-01, including calculations that have been
changed or created in response to GL 2008-01 (with a short description of the
calculation and the change).
4. List (with a short description) of gas intrusion mechanisms that apply to the plant and the
affected system locations (e.g. identify the source, conditions, and expected void
locations).
5. List of the suction piping sections identified as susceptible to gas accumulation (the list
should identify the corresponding system).
- 1- Enclosure
6. List of the discharge piping sections identified as susceptible to gas accumulation (the
list should identify the corresponding system).
7. Copies of isometric drawings of the emergency core cooling, residual heat removal, and
containment spray systems (hard-copies are preferred).
8. Copies of piping and instrumentation diagrams (P&IDs) of the emergency core cooling,
residual heat removal, and containment spray systems (hard-copies are preferred).
9. Copies of program documents and procedures developed to implement the resolution of
GL 2008-01.
10. List of actions that were completed in response to GL 2008-01.
11. Copies of the modification packages for hardware modifications as part of the resolution
of GL 2008-01.
12. Design basis documents of the emergency core cooling, residual heat removal, and
containment spray systems.
13. Design basis documents of keep-full systems of the emergency core cooling, residual
heat removal, and containment spray systems.
14. System walkdown reports associated with the resolution of GL 2008-01.
15. If applicable, provide a list of inaccessible locations where plant walkdowns of the
emergency core cooling, residual heat removal, and containment spray systems have
not been completed. Include an explanation of why each area is considered
inaccessible.
16. Copies of surveillance procedures associated with the resolution of GL 2008-01 and the
results of the last two surveillances for the emergency core cooling, residual heat
removal, and containment spray systems.
17. Copies of procedures used for detecting and determining void volumes.
18. Copies of procedures used for filling and venting.
19. Copies of trends of periodic venting results.
20. Copies of the engineering evaluations performed for all identified voids in the past three
years.
21. Basis for the void acceptance criteria (e.g. calculation). If applicable, provide the
justification for any deviation from the void acceptance criteria established by the Office
of Nuclear Reactor Regulation (NRR).
22. Copy of any void transport analyses.
-2- Enclosure
23. Copy of vortexing calculations associated with systems under the scope of GL 2008-01.
24. Copies of self-assessments associated with the implementation of the GL 2008-01
program.
II. Information Requested By August 15,2011
25. Copies of the selected corrective action program documents.
26. Copies of the selected licensing and design basis document changes.
27. Copies of the selected calculations.
28. Copies of training documents that ensure that personnel are aware of gas-related
concerns.
29. Copies of corrective action program implementing procedures.
30. Electronic copies of the current technical specifications, technical specification bases,
final safety analysis report, and technical requirements manual.
-3- Enclosure