|
---|
Category:Inspection Report
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information IR 05000260/20244012024-04-10010 April 2024 Security Baseline Inspection Report 05000260/2024401 and 05000260/2024401 and 05000296/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000259/20230042024-02-0606 February 2024 Integrated Inspection Report 05000259/2023004; 05000260/2023004 and 05000296/2023004 IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 IR 05000259/20234022023-06-12012 June 2023 – Material Control and Accounting Program Inspection Report 05000259 2023402, 05000260 2023402 and 05000296 2023402 IR 05000259/20230912023-05-0808 May 2023 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter; NRC Inspection Report 05000259/2023091 IR 05000259/20230012023-05-0303 May 2023 Integrated Inspection Report 05000259/2023001, 05000260/2023001 and 05000296/2023001 IR 05000259/20234402023-03-23023 March 2023 – Special Inspection Supplemental Report 05000259 2023440 and 05000260 2023440 and 05000296 2023440 Cover Letter IR 05000259/20234012023-03-0808 March 2023 – Security Baseline Inspection Report 05000259 2023401 and 05000260/2023401 and 05000296/2023401 IR 05000259/20230902023-03-0202 March 2023 NRC Inspection Report 05000259/2023090 and 05000260 2023090 and Preliminary White Finding and Apparent Violation IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 IR 05000259/20220042023-02-0707 February 2023 Integrated Inspection Report 05000259/2022004, 05000260/2022004 and 05000296/2022004 IR 05000259/20220032022-11-0909 November 2022 Browns Perry Nuclear Plant - Integrated Inspection Report 05000259/2022003, 05000260/2022003 and 05000296/2022003 IR 05000259/20220122022-09-20020 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000259 2022012, 05000260 2022012 and 05000296 2022012 IR 05000259/20220112022-09-16016 September 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000259/2022011 and 05000260/2022011 and 05000296/2022011 IR 05000259/20224022022-09-0606 September 2022 Security Baseline Inspection Report 05000259/2022402 and 05000260/2022402 and 05000296/2022402 Cover Letter IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 IR 05000259/20220022022-08-0808 August 2022 Integrated Inspection Report 05000259/2022002, 05000260/2022002 and 05000296/2022002 IR 05000259/20224202022-07-19019 July 2022 – Security Baseline Inspection Report 05000259/2022420, 05000260/2022420 and 05000296/2022420 ML22181A9562022-06-29029 June 2022 Bf Report 2022-401 Base Public Cover Letter ML22173A1622022-06-21021 June 2022 Replacement Steam Dryer Visual Inspection Results (U3R20) IR 05000259/20220012022-05-12012 May 2022 Integrated Inspection Report 05000259/2022001, 05000260/2022001, 05000296/2022001 and Exercise of Enforcement Discretion IR 05000259/20220102022-03-30030 March 2022 Triennial Fire Protection Inspection Report 05000259/2022010 and 05000260/2022010 and 05000296/2022010 and Apparent Violation IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 IR 05000259/20210042022-01-31031 January 2022 Integrated Inspection Report 05000259/2021004, 05000260/2021004 and 05000296/2021004 IR 05000259/20214032022-01-19019 January 2022 NRC Inspection Report 05000259/2021403, 05000260/2021403 and 05000296/2021403 IR 05000259/20214022022-01-18018 January 2022 Brows Ferry Nuclear Plant - Security Baseline Inspection Report 05000259/2021402 and 05000260/2021402 and 05000296/2021402 IR 05000259/20210032021-11-0909 November 2021 Integrated Inspection Report 05000259/2021003, 05000260/2021003, 05000296/2021003 and 07200052/2021001 IR 05000259/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000259/2021401 and 05000260/2021401 and 05000296/2021401 IR 05000259/20210112021-08-24024 August 2021 Temporary Instruction 2515/TI-193 Inspection Report 05000259/2021011, 05000260/2021011, and 05000296/2021011 IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 ML21217A2832021-08-0505 August 2021 Resident Integrated Inspection Report 2021-002 IR 05000259/20213012021-07-28028 July 2021 NRC Operator License Examination Report Nos. 05000259/2021301, 05000260/2021301, 05000296/2021301 IR 05000259/20210102021-07-26026 July 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010 IR 05000259/20204012021-05-26026 May 2021 Security Baseline Inspection Report 05000259/2020401 and 05000260/2020401 and 05000296/2020401(U) 2024-09-03
[Table view] Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual 2024-09-03
[Table view] |
Text
,OiUTIO~ 830 Power Building TENNESSEE VALLEY AUTHORITY O
~
",'b'~~s-to<~ CHATTANOOGA. TENNESSEE 37401 May 6, 1976 Mr. Horman C. Moseley, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II Suite 818 230 Peachtree Street, HN.
Atlanta, Georgia 30303
Dear Mr. Moseley:
This is in response to F. J. Long's letter of Apri1 20, 1976, IE:II:BJC 50-259/76-6, 50-260/76-6, which transmitted.
for our. review an IE Inspection Report (same number) Ue have reviewed that report and do not consider any part of to be proprietary.
it Very truly yours,
/ ,'A~gr'g J. F.. Gillelaad Assistant Manage& of Power An Equal Opportunity Employer
4l
~k
c"~ RKQ0 P
O UNITED STATES Cy ~i NUCLEAR REGULATORY COMMISSION nO REGION II 0 Q 330 PEACHTREE STREETe H W SUITE SIS ATLANTA,GEORGIA 30303 APR 2 0 1976 In Reply Refer To:
IE3IIIBJC 50-260/76-6 Tennessee Valley Authority ATTN: Mr. Godwin Wi11iams, Jr.
Manager of Power 818 Power Building Chattanooga, Tennessee 37401 Gentlemen:
This refers to the inspection conducted by Mr. T. D. Gibbons of this office on March 10-12, 1976 and March 31 April 2, 1976, of activities authorized by NRC Operating License Nos. DPR-33 and DPR-52 for the 10 Browns Ferry Units 1, and 2 facilities, and to the discussion of our findings held. with Mr. J. R. Hilding at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in the, encl'osed inspection report. Within these areas, the inspection consisted of selective examination of procedures and repxesentative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no items of noncompliance were disclosed.
In accordance with Section 2.790 of the KRC's "Rules of Practice,"
Part 2, Title 10,, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe to be proprietary, it is necessaxy that you submit a written application to this office requesting that such information be withheld from public disclosure., If no proprietary information is identified, a written statement to that, effect should be submitted.. If an application is submitted, it must fully identify the bases for which information is claimed to be propxietary., The application should be prepared so that infoxmation sought to be withheld is incorporated in .a separate paper and. referenced in the app&.cation since the application will be placed in the Public. Document Room. Your application,, or written statement,
APR 20 816 Tennessee Valley Authority should be submitted to us within 20 days. If we are not contacted as specified,, the enclosed report and this letter may then be placed in the Public Document Room.
Should you. have any questions concerning this letter, we will be glad to discuss them with you.
Very truly yours, P.. J. Long, Chief Reactor Operations and Nuclear Support Branch
Enclosure:
IE'nspection Report Nos.
50-259/76-6 and'0-260/76-6.
~s REotl, UNITED STATES 0
Cy NUCLEAR REGULATORY COMMISSION fl O
I 0 K REGION It 230 PKACHTREK STREET, N W SUITE $ $ 8
/g ATLANTA'KORCRIA 30303
+**++
IE Inspection Report Nos. 50-259/76-6 and 50-260/76-6 Licensee: Tennessee Valley Authority 818 Power Building Chattanooga, Tennessee 37401 Facility Name: Browns Ferry Units 1 and 2 Docket Nos.: 50-259 and 50-260 License Nos.: DPR-33 and DPR-52 Category: C/C Location. Limestone County, Alabama Type of License: GE, 1098 Mme, BWR Type of Inspection: Fire Damage Restoxation Dates of Inspection. March 10-12, 1976 March 31-April 2, 1976 Dates of Px'evious Inspection: February 9-11, 1976 February 24-March 1, 1976 Inspectox-in-Charge: T. D. Gibbons, Reactor Inspector Engineering Support Section No. 1 Reactor Construction and .Engineering Support Branch Accompanying Inspector: None Other Accompanying Personnel n Principal Inspector: yy .
(
~~~vZ, yi B.<J. Cochran, Reactor Inspector
~!i.h~
/ Date Prospects Section Reactor Construction and Engineering Support Branch Reviewed by:
J. C . ryant, C f Date Pr cts Section Reactor Construction and Engineering Support Branch
IE Rpt. Nos. 50-259/76-6 and 50-260/76-6
SUMMARY
OF FINDINGS I. Enforcement Items None.
II. Licensee Action: on,Previousl Identified Enforcement Matters Infractions 76-4-Al(II) Audits The audit schedules are not updated at the required frequency, and there is no documented evidence that audits are conducted in accordance wf.th an audit plan. This is an infraction. This item remains open.
76-4<<A2(II) Cable Minimum Bend Radius A cabl'e was installed in Unit 2 in violation of the minimum bend. radius. This. is an infraction. This item remains open.
III. New Unresolved Items None IV.'tatus of'reviousl Re orted Unresolved Items None.
None VI'.. Unusual. Occurrence None.
VII. Other Si nificant Findin s None:
IE Rpt. Nos. 50-259/76-6 and 50-260/76-6 VIII. Mana ement Interview The exit interview was held with Mr. J. R. Hilding, BFNP Restora-tion gA Manager, wherein the subjects of this inspection were discussed. No items of noncompliance were identified.
IE Rpt. Nos. 50-259/76>>6 and 50-260/76-6 DETAILS I Prepared by: i-lz,-74 T. D. Gibbons, Reactor Inspector Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Dates of Inspection: March 10-12 and March 31 April 2, 1976 Reviewed by: M / j r r~i. izl'7<:
S. D. Ebneter, Acting Section Chief Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch The discussion contained in this section of this report applies to Unit 1 and 2 equally unless noted otherwise.
- 1. Persons Contacted Tennessee Valle Authori (TVA)
J. R. Hilding - Fire Restoration QA Manager J. E. Law QA Engineer D. Wright - Electrical Engineer
- 2. Sc e of Ins ection This inspection was performed to verify that the requirements of Browns Ferry Electrical Maintenance Instruction (EMI) 20 have been met. The inspector observed work on the installation of Flameastic and firestops being installed by procedure BF 206R, (Electrical Penetration Seal and Firestop Installation and Inspection).
- 3. lementation of Electrical Maintenance Instruction EMI) 20 (Unit 1 Onl )
The inspector reviewed the records of the maintenance inspection activities which are covered by EHI 20 in Unit 1. This covered the cleaning of panels, local control stations, motor operated valves and motors. The records included the inspection, cleaning and retest as required. The records were found to be complete. The inspector made a visual check in several areas verifying that the work reported in the records was completed. The inspector identified no items of noncompliance.
IE Rpt. Nos. 50-259/76-6 and 50-260/76-6 I-2
- 4. Im lementation of BF 206R - Electrical Penetration Seal and Firesto Installation and Ins ection The inspector observed the work progressing on the installation of penetration seals and firestops on elevations 639, 621 and 591 of the reactor buildings in both units. On each elevation the equip-ment was covered with plastic sheets. Notices of no smoking were prominently displayed and firewatches were found in all areas. The craftsmen were applying the Flameastic at 1/4 inch wet which will dry to an 1/8 inch thickness. The procedure calls for 1/8 inch dry thickness. TVA inspectors were in the area observing the operation and assuring that the procedural requirements were fulfilled. The Flameastic 71 compound is a viscous, cream colored liquid which is applied by use of high pressure spray. It was noted that cable tags and tray labels were protected to prevent the Flameastic from covering any necessary information.
The firestops are constructed using various materials such as Cerafibre, Cerefoam Marinite, Silicone RTV foam and Silicone insulation. The installation covered TVA drawings, the procedure and manufacturers operating manuals. Specific inspection acceptance criteria are identified and QC signatures are required to hold points. The inspector observed the work in progress in the spreading room and various penetrations in the reactor building. Quality con-trol in-process inspections were being performed concurrent with the installation work. The inspector has no further questions at this time.
ig