CNL-15-139, Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of Insights from

Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of Insights from

ML15244B346
Person / Time
Site:	Browns Ferry
Issue date:	09/01/2015
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-15-139
Download: ML15244B346 (76)

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U.S. Nuclear Regulatory Commission CNL-15-139 Page 2 September 1, 2015 TVA committed in Reference 2 to complete seismic walkdowns for these four areas in the BFN Unit 3, 2014 Spring refueling outage. TVA has completed these remaining seismic walkdowns.

The purpose of this letter is to provide the results of the completed BFN Unit 3 walkdown inspections performed for the four pieces of equipment identified in Reference 2.

Specifically, the Enclosure of this letter provides the updated pages to the Seismic Walkdown Report for BFN, Unit 3. Pages 1 (cover page), 2, 4, 10, 14, 15, 21, 112, 113, 115, 116, 302-311, 532-541, 717, and 883-889 of the Enclosure have been revised to include the results for these walkdowns and these pages supersede those pages submitted in Enclosure 3 to Reference 2. The remaining pages of the Enclosure (Pages 2i, 2ii, 45i-45iii, 55i-55iii, and 881 i-881 xii) are new and added to the report to document these additional walkdowns. There were no degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-up actions as a result of these seismic walkdowns at BFN Unit 3.

There are no new regulatory commitments contained in this letter.

Should you have any questions regarding this matter, please contact Russell Thompson at (423) 751-2567.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1st day of September 2015.

ice President, Nuclear Licensing

Enclosure:

Browns Ferry Nuclear Plant, Unit 3, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report cc (Enclosure):

NRR Director - NRC Headquarters NRO Director - NRC Headquarters NRC JLD Director - NRC Headquarters NRC Regional Administrator - Region II NRR Project Manager - Browns Ferry Nuclear Plant NRC JLD Project Manager - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant







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NTTF Recommendation 2.3: Seismic Response Report Browns Ferry Unit 3



As a result of the Fukushima Daiichi Nuclear Power Plant accident, the U.S. Nuclear Regulatory Commission established the Near Term Task Force (NTTF) to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction. The NTTF issued a report (Reference 1) that made a series of recommendations, some of which were to be acted upon without unnecessary delay. Subsequently, the NRC issued a 50.54(f)

Letter (Reference 2) that requests information to assure that these recommendations are addressed by all U.S. nuclear power plants. This report provides guidance for conducting a seismic walkdown as required in the 50.54(f) Letter, Enclosure 3, Recommendation 2.3: Seismic. Every U.S. nuclear power plant is required to perform a seismic walkdown to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration with the current seismic licensing basis.

In support of conducting the NTTF-2.3 Seismic Walkdowns, the Electrical Power Research Institute (EPRI) issued a report entitled Seismic Walkdown Guidance (Reference 3) to provide instruction for uniform seismic walkdowns of all U.S. nuclear power plants. This document also includes guidance for reporting the findings of the required walkdowns. TVA incorporated this documentation into a procedure and provided training to all team members.

At Unit 3 of the Browns Ferry Nuclear Plant, a total of 120 items, general Seismic Category 1, were selected from the original IPEEE Safe Shutdown Equipment List (SSEL) to fulfill the requirements of the NTTF-2.3 Seismic Walkdowns. The selected equipment was located in various environments and included many different types of equipment from multiple safety systems. A total of 44 areas were included for area walk-bys. The equipment walkdowns and area walk-bys were performed by three teams each consisting of two seismic walkdown engineers and operations personnel, between July 9, 2012 and February 26, 2014.

One hundred twenty (120) equipment walkdowns were completed during the walkdown phase. No potential adverse seismic conditions were found.

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NTTF Recommendation 2.3: Seismic Response Report Browns Ferry Unit 3

3) Personnel Qualifications The personnel qualification for all individuals involved in the execution of the Fukushima Near-Term Task Force Recommendation 2.3: Seismic can be found in this section. Full resumes for the listed individuals can be found in Appendix A of this document.

3.1 Equipment Selection Personnel The personnel involved in equipment selection and review are:

x Steve Gray, Retired SRO from Browns Ferry with extensive experience providing engineering support through all phases of the operating site.

x Nicholas Pressler, Senior Structural Engineer with 7 years of experience, including 2 years of experience in the nuclear industry.

x Jason Black - Associate Structural engineer with 1.5 years of engineering experience, including 1.5 years in the nuclear power industry.

3.2 Seismic Walkdown Engineers The personnel involved in performing the seismic walkdowns are:

x Nicholas Pressler x

Patrick McCarraher, Senior Supervising Structural Engineer with over 38 years of engineering experience, including 15 years in the nuclear power industry.

x Jeffry Lawrence, Mechanical Engineer II, E.I.T. with five years of engineering experience, including two in the nuclear power industry.

x Avinash Chunduri, Structural Engineer II with 6 years of engineering experience, including 1.5 years experience in nuclear power industry.

x George Bongart, Associate Civil Engineer with 9 months engineering experience.

x Jason Black x

James Edgar, Professional engineer in the state of Tennessee with 11 years of engineering experience including 2 years in the nuclear power industry.

x Travis Hockenberry, Professional Engineer in the state of Pennsylvania with 7 years of engineering experience, including 3 years in the nuclear power industry.

x Steven Summers, Professional Engineer in the state of Pennsylvania with 8 years of engineering experience, including 3 years in the nuclear power industry.

3.3 Licensing Basis Reviewers The personnel involved in performing the licensing basis reviews:

x Steve Samaras, Site engineer at Browns Ferry with extensive experience providing engineering support of the operating site.

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Page 13 of 889

NTTF Recommendation 2.3: Seismic Response Report Browns Ferry Unit 3



Guidance for performing the walkdowns and walk-bys required for Fukushima NTTF Recommendation 2.3 can be found in Reference 3 - The Electrical Power Research Institutes Seismic Walkdown Guidance.

The walkdowns and walk-bys were conducted in accordance with these guidelines and each was given a final status. If no potentially adverse seismic conditions were noted or housekeeping and minor maintenance issues were noted during a walkdown or walk-by, a YES status was given to the selected piece of equipment or area. If a potentially adverse seismic condition was noted, a NO status was given and the equipment was entered into the Corrective Action Program (CAP) to begin a functional evaluation. If equipment was inaccessible, or if a portion of an item of equipment was unobservable an UNKNOWN status was given.



One hundred twenty (120) Seismic Walkdown Checklists (SWCs) were completed at Browns Ferry Unit 3. The SWCs completed at Browns Ferry Unit 3 can be found in Appendix E of this document. The types of potentially adverse seismic conditions that were addressed during these walkdowns include:

• Bent, broken, missing, or loose hardware

• Corrosion that is more than moderate

• Visible cracks in surrounding concrete

• Impact of soft targets

• Collapsing equipment

• Line flexibility Forty-four (44) Area Walk-by Checklists (AWCs) were completed at Browns Ferry Unit 3.

These checklists can be found in Appendix F of this document. The types of potentially adverse seismic conditions that were addressed during these walk-bys include:

• Anchorage of equipment

• Degraded conditions of anchorage

• Cable/conduit raceways and HVAC ducts

• Spatial interactions between equipment

• Flooding/spray hazards

• Fire hazards

• Housekeeping and temporary equipment 3DJHRI

NTTF Recommendation 2.3: Seismic Response Report Browns Ferry Unit 3 Anchorage configuration for 4 items of equipment in Browns Ferry Unit 3 was verified by drawings, calculations, and/or the A-46 Screening Evaluation Worksheets (SEWs).

For cabinets and panels that were selected for walkdown, NRC guidance was followed to determine which could and could not be opened for internal inspection. Undue safety hazards, operational hazards, or cabinets that required extensive disassembly were documented and only observable anchorage was included in those walkdowns.



The results documented by the SWCs and AWCs for Browns Ferry Unit 3 are summarized below:

• 120 SWCs resulted in a YES status

• 44 AWCs resulted in a YES status 3DJHRI



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SUMMARY

Structural Engineer with over seven years of engineering experience, including four years with WorleyParsons. Primary responsibilities included the overall structural design and coordination for all types of power plant design and retrofit projects. Tasks included structural steel design, ductwork design, qualifying existing steel for upgraded loads/new code, foundation design, and providing erection/fabrication technical support for power generating stations. Skilled in creating and analyzing STAAD models for ductwork, structural steel, mat foundations, as well as creatively utilizing other software such as Excel, MathCAD, Smart Plant, and similar programs to expedite design. Also active in client interface with participation in project meetings and budget proposals. In addition, responsibilities include the inspection of ductwork, structural steel, and chimneys as part of the Chattanooga Condition Assesment Team. Familiar with AISC Steel Manual (ASD and LRFD), ACI 318-05, IBC 2000, and ASCE 7-05.

EXPERIENCE

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Qualification of new and existing nuclear fire protection pipe supports for new loading conditions, following appropriate design criteria, code provisions, and NRC requirements. Qualification and specification of both existing and new pipe support components, such as struts, clamps, and anchors.

Qualification and design of non-standard welded connections. Pipe supports qualified using computer modeling, utilizing TVA supplied software. Software includes FAPPS (ME150),

BASEPLATE II (ME035), MAPPS (ME153), CONAN, and IAP. Creation of supporting calculation packages utilizing MathCAD, Microsoft Excel and Word. Responsible for design input and verification of DCA (Drawing Change Authorization), which serves as the working document for required pipe support configurations and final support drawings to be issued into the TVA database.

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Qualification of existing nuclear pipe supports for new loading conditions associated with the replacement of motors on two minimum flow valves, following appropriate design criteria, code provisions, and NRC requirements. Qualification and specification of existing pipe support components, such as struts, clamps, and anchors. Qualification and design of non-standard welded connections. Pipe supports qualified using computer modeling, utilizing TVA supplied software.

Software includes FAPPS (ME150), BASEPLATE II (ME035), MAPPS (ME153), CONAN, and IAP.

Creation of supporting calculation packages utilizing MathCAD, Microsoft Excel and Word.

Responsible for design input and verification of DCA (Drawing Change Authorization), which serves as the working document for required pipe support configurations and final support drawings to be issued into the TVA database.

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8QLW 6SULQJ &LW\\ 7HQQHVVHH. Served as a team lead for a group of five engineers supporting the WBN Unit 2 pipe support project. Responsibilities include, but not limited to, the qualification of existing nuclear pipe supports for new loading conditions following the appropriate design criteria, code provisions, and NRC requirements. Qualification of existing and new pipe support components, such as snubbers, struts, clamps, and springs. Qualification and design of non-standard welded connections. The task utilized computer modeling via TVA-supplied software. The software includes FAPPS (ME150), BASEPLATE II (ME035), MAPPS (ME153), CONAN, and IAP. MathCAD, Excel, and Word. Software used in the creation of support calculation packages. Responsible for the review of Drawing Revision Authorization (DRA) to ensure accurate support drawings for issuance into the TVA database. Additional responsibilities included the review and verification of pipe support calculations prior to issuance and coordination between multiple offices to ensure quality, completeness, and consistency.

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&RUSRUDWH %DVH Page 2 Rev 6 (03-Feb-09) 79$ +/- :LGRZV &UHHN )RVVLO 8QLW  2SDFLW\\ 5HGXFWLRQ 6WXG\\. Served as the structural task lead for a cost study of the addition of various air quality control measures (baghouse/precipitator) to Widows Creek Unit 8. The task included preliminary structural engineering of new ductwork, structural support steel, foundations, as well as the retrofit of the existing ductwork and structures.

The work involved site visits to walkdown existing structures to find ways to interface with existing equipment and route ductwork through the existing structure. Interface with mechanical leads to provide the necessary ductwork cross-section and to ensure an efficient flow path to achieve a minimal pressure drop. Worked closely with the estimating department in order to produce an accurate cost estimate for four different retrofitting options.

6RXWKHUQ &RPSDQ\\ +/- 6FKHUHU 8QLW  )OXH *DV 'HVXOSKXUL]DWLRQ )*'6HOHFWLYH &DWDO\\WLF 5HGXFWLRQ 6&5 3URMHFW -XOLHW *HRUJLD Responsible for the design of an electrical utility bridge for Units 1 and 2. The process included the layout of the utility bridge using SmartPlant Review and the design of the structure utilizing STAAD Pro. The task included the design of anchor bolts and the design of spread footings to support the structure.

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1HZ -HUVH\\. Primary responsibilities included the analysis and design of pile foundations to support the new SCR structure. The task included using SmartPlant Review to coordinate the layout of augercast piles in order to avoid existing interferences and obstructions. STAAD Pro 2007 finite element analysis used to analyze the pipe cap foundation. ACI 318-05 was utilized to provide the proper reinforcement for the pile cap as well as ensure that the anchor bolts met the requirements of Appendix D.

  

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&36 3HDNLQJ +/- 7XUELQH 3URMHFW %UDXQLJ 3ODQW 7H[DV. Primary responsibilities included the computer modeling, anlaysis, and design of soil supported mat foundations. Analysis and design of small equipment foundations including oil containment areas. Interfaced with the mechanical department in order to provide pipe supports and the associated foundations to support the chilled water and natural gas piping systems throughout the plant.

6RXWKHUQ &RPSDQ\\ +/- 6FKHUHU 8QLW  )*'6&5 3URMHFW -XOLHW *HRUJLD +/- Primary responsibilities included the retrofit of existing ductwork and support structures due to increased loading caused by an upgraded pressure load associated with the addition of a mercury baghouse, FGD, and SCR. STAAD used to analyze the ductwork and support structures while PCA Column and LPile were used to evaluate the existing caissons and piers. Retrofit modifications were made to qualify the structures for the increased shear, uplift, and compressive forces that were caused by the upgraded pressure.

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&RQYHUVLRQ &DUWHJHQD &RORPELD Primary responsibilities included the computer modeling, analysis, and design of soil supported mat foundations. Analysis and design of small equipment foundations including oil containment areas. Provided pipe supports and foundations to assist mechanical/electrical engineers in the balance-of-plant design. Produced calculations for cast-in-place and post-installed equipment anchorage to concrete. Other duties included the design of concrete and masonry structures that were needed due to fire rating requirements. Work also included coordinating work with other disciplines to produce deliverables, providing project manager with regular updates, and producing estimates and NWIs for additional work added to the Structural Engineering Scope.

6RXWKHUQ &RPSDQ\\ +/- 3ODQW 6FKHUHU 8QLW  0HUFXU\\ %DJKRXVH -XOLHW *HRUJLD. Primary responsibilities included performing the design and analysis of large ductwork and their support structures, as well as providing fabrication/erection support to the client. Other duties included creating and analyzing models for existing steel, ductwork, and working with designers to facilitate the generation of drawing deliverables, and meeting schedule requirements.

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7HQQHVVHH In addition to structural engineering responsibilities, additional responsibilities include condition assessment inspections at fossil power plants. The tasks include traveling to the site and performing inspections, documenting the existing conditions of the respective component during the inspection, and providing a formalized post-inspection report which documents the findings and makes recommendations on any needed modifications to the structure. Typical inspections include air and flue gas ductwork, circulating cooling water tunnels, chimneys and stacks, and other miscellaneous structural systems.

  

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• '27 +/- 0F)DUODQG 5G65 ,QWHUFKDQJH 3URMHFW. Primary responsibilities included the design and implementation of erosion control plans, traffic control plans, and staging plans. In addition, responsibilities included working with Department of Transportation (DOT) representatives to alter/change plan design in order to account for situations in the field or in order to have a minimal impact of the traveling public. Responsibilities also included the coordination and scheduling of work and subcontractors.

• '27 +/- 6565,QWHUFKDQJH,PSURYHPHQW 3URMHFW Primary responsibilities included the coordination and scheduling of work done by subcontractors and inspection of the work upon completion. In addition, responsibilities included working with DOT representatives to redesign plan in order to accommodate existing field conditions and to produce a more buildable design which was safer for the constructors as well as the traveling public. This included stormwater drainage plans, traffic control plans, and staging plans.

EDUCATION B.S., Civil Engineering Technology, Southern Polytechnic State University, Marietta, Georgia, 2003.

REGISTRATIONS/AFFILIATIONS Registered Professional Engineer, Civil, Pennsylvania, No. PE077046, 2009 Member, American Institute of Steel Construction (AISC)

Confined Space and Fall Protection Trained SPECIFIC TECHNICAL EXPERTISE/SPECIALIST COURSES Computer Skills STAADPro V8i AutoCAD MathCAD SmartPlant Review LPile Plus 5.0 SmartPlant Foundation Microsoft Office Applications PCA Column 3DJHLLLRI

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Page 115 of 889

Sheet 1 of 5 Status: Y N

U 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9

Equipment Class3 7 Equipment Description MSIV "A" INBOARD ISOLATION VALVE Location: Bldg. U3 RB Floor El. 563 Room, Area 129, Drywell EL Manufacturer, Model, Etc. (optional but recommended)

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments. Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

$QFKRUDJH

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y N

2. Is the anchorage free of bent, broken, missing or loose hardware?

Y N

U N/A 3Enter the equipment class name from Appendix B, Classes of Equipment.

3DJHRI

563'-2"

Sheet 2 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" INBOARD ISOLATION VALVE

$QFKRUDJH &RQWLQXHG

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Y N

U N/A

4. Is the anchorage free of visible cracks in the concrete near the anchors?

Y N

U N/A

5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Y N

U N/A 3DJHRI

Sheet 3 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" INBOARD ISOLATION VALVE

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Y N

U

,QWHUDFWLRQ (IIHFWV

7. Are soft targets free from impact by nearby equipment or structures?

Y N

U N/A

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Y N

U N/A 3DJHRI

Sheet 4 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" INBOARD ISOLATION VALVE

,QWHUDFWLRQ (IIHFWV &RQWLQXHG

9. Do attached lines have adequate flexibility to avoid damage?

Y N

U N/A

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y N

U 2WKHU $GYHUVH &RQGLWLRQV

11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

Y N

U 3DJHRI

Sheet 5 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" INBOARD ISOLATION VALVE

&RPPHQWV (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date:2/26/14 Travis Hockenberry 2/26/14 3DJHRI

Sheet 1 of 5 Status: Y N

U 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9

Equipment Class3 7 Equipment Description MSIV "A" OUTBOARD ISOLATION VALVE Location: Bldg. U3 RB Floor El. 565 Room, Area 130, Steam Tunnel Manufacturer, Model, Etc. (optional but recommended)

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments. Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

$QFKRUDJH

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y N

2. Is the anchorage free of bent, broken, missing or loose hardware?

Y N

U N/A 3Enter the equipment class name from Appendix B, Classes of Equipment.

3DJHRI

Sheet 2 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" OUTBOARD ISOLATION VALVE

$QFKRUDJH &RQWLQXHG

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Y N

U N/A

4. Is the anchorage free of visible cracks in the concrete near the anchors?

Y N

U N/A

5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Y N

U N/A 3DJHRI

Sheet 3 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" OUTBOARD ISOLATION VALVE

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Y N

U

,QWHUDFWLRQ (IIHFWV

7. Are soft targets free from impact by nearby equipment or structures?

Y N

U N/A

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Y N

U N/A 3DJHRI

Sheet 4 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" OUTBOARD ISOLATION VALVE

,QWHUDFWLRQ (IIHFWV &RQWLQXHG

9. Do attached lines have adequate flexibility to avoid damage?

Y N

U N/A

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y N

U 2WKHU $GYHUVH &RQGLWLRQV

11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

Y N

U 3DJHRI

Sheet 5 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)1)&9 Equipment Class3 7 Equipment Description MSIV "A" OUTBOARD ISOLATION VALVE

&RPPHQWV (Additional pages may be added as necessary)

Evaluated by: Travis Hockenberry Date:2/26/14 Lance Summers 2/26/14 3DJHRI

Sheet 1 of 5 Status: Y N

U 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9

Equipment Class3 7 Equipment Description MAIN STEAM LINE A RELIEF VLV Location: Bldg. U3 RB Room, Area 131, Floor EL Manufacturer, Model, Etc. (optional but recommended)

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments. Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

$QFKRUDJH

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y N

2. Is the anchorage free of bent, broken, missing or loose hardware?

Y N

U N/A 3Enter the equipment class name from Appendix B, Classes of Equipment.

3DJHRI

584'-11" Drywell AZ 135o

Sheet 2 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE A RELIEF VLV

$QFKRUDJH &RQWLQXHG

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Y N

U N/A

4. Is the anchorage free of visible cracks in the concrete near the anchors?

Y N

U N/A

5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Y N

U N/A 3DJHRI

Sheet 3 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE A RELIEF VLV

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Y N

U

,QWHUDFWLRQ (IIHFWV

7. Are soft targets free from impact by nearby equipment or structures?

Y N

U N/A

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Y N

U N/A 3DJHRI

Sheet 4 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE A RELIEF VLV

,QWHUDFWLRQ (IIHFWV &RQWLQXHG

9. Do attached lines have adequate flexibility to avoid damage?

Y N

U N/A

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y N

U 2WKHU $GYHUVH &RQGLWLRQV

11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

Y N

U 3DJHRI

Sheet 5 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE A RELIEF VLV

&RPPHQWV (Additional pages may be added as necessary)

Valve partially disassembled by maintenance personnel due to outage.

Evaluated by: Lance Summers Date:2/26/14 Travis Hockenberry 2/26/14 3DJHRI

Sheet 1 of 5 Status: Y N

U 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9

Equipment Class3 7 Equipment Description MAIN STEAM LINE D RELIEF VLV Location: Bldg. U3 RB Room, Area 131, Floor EL Manufacturer, Model, Etc. (optional but recommended)

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments. Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

$QFKRUDJH

1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y N

2. Is the anchorage free of bent, broken, missing or loose hardware?

Y N

U N/A 3Enter the equipment class name from Appendix B, Classes of Equipment.

3DJHRI

584'-11" Drywell AZ 225o

Sheet 2 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE D RELIEF VLV

$QFKRUDJH &RQWLQXHG

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Y N

U N/A

4. Is the anchorage free of visible cracks in the concrete near the anchors?

Y N

U N/A

5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Y N

U N/A 3DJHRI

Sheet 3 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE D RELIEF VLV

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Y N

U

,QWHUDFWLRQ (IIHFWV

7. Are soft targets free from impact by nearby equipment or structures?

Y N

U N/A

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Y N

U N/A 3DJHRI

Sheet 4 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE D RELIEF VLV

,QWHUDFWLRQ (IIHFWV &RQWLQXHG

9. Do attached lines have adequate flexibility to avoid damage?

Y N

U N/A

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

Y N

U 2WKHU $GYHUVH &RQGLWLRQV

11. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment?

Y N

U 3DJHRI

Sheet 5 of 5 6HLVPLF :DONGRZQ &KHFNOLVW 6:&

Equipment ID No. %)13&9 Equipment Class3 7 Equipment Description MAIN STEAM LINE D RELIEF VLV

&RPPHQWV (Additional pages may be added as necessary)

Valve partially disassembled by maintenance personnel due to outage.

Evaluated by: Travis Hockenberry Date:2/26/14 Lance Summers 2/26/14 3DJHRI

Sheet 1 of 4 Status: Y N

U

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Room, Area4 Drywell Area EL

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Area Walk-By near one or more SWEL items.

The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable 1.

Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y N

U N/A

2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

Y N

U N/A 4If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

3DJHLRI

563'-2"

Sheet 2 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Room, Area4 Drywell Area EL

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

Y N

U N/A

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Y N

U N/A

5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?

Y N

U N/A 3DJHLLRI

563'-2"

Sheet 3 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Room, Area4 Drywell Area EL

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?

Y N

U N/A

7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Y N

U N/A

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

Y N

U 3DJHLLLRI

Scaffolding and maintenance tools present but good housekeeping practice were observed.

563'-2"

Sheet 4 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Room, Area4 Drywell Area EL

&RPPHQWV (Additional pages may be added as necessary)

Equipment associated with this Area Walk-by Checklist:

BFN-3-FCV-001-0014 Evaluated by:Travis Hockenberry Date: 2/26/14 Lance Summers 2/26/14 3DJHLYRI

563'-2"

Sheet 1 of 4 Status: Y N

U

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 565 Room, Area4 Steam Tunnel

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Area Walk-By near one or more SWEL items.

The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable 1.

Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y N

U N/A

2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

Y N

U N/A 4If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

3DJHYRI

Sheet 2 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 565 Room, Area4 Steam Tunnel

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

Y N

U N/A

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Y N

U N/A

5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?

Y N

U N/A 3DJHYLRI

Sheet 3 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 565 Room, Area4 Steam Tunnel

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?

Y N

U N/A

7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Y N

U N/A

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

Y N

U 3DJHYLLRI

Scaffolding and maintenance tools present but good housekeeping practice were observed.

Sheet 4 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 565 Room, Area4 Steam Tunnel

&RPPHQWV (Additional pages may be added as necessary)

Equipment associated with this Area Walk-by Checklist:

BFN-3-FCV-001-0015 Evaluated by:Travis Hockenberry Date: 2/26/14 Lance Summers 2/26/14 3DJHYLLLRI

Sheet 1 of 4 Status: Y N

U

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 585 Room, Area4 Drywell Area EL 585

,QVWUXFWLRQV IRU &RPSOHWLQJ &KHFNOLVW This checklist may be used to document the results of the Area Walk-By near one or more SWEL items.

The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable 1.

Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

Y N

U N/A

2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

Y N

U N/A 4If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

3DJHL[RI

Sheet 2 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 585 Room, Area4 Drywell Area EL 585

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

Y N

U N/A

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Y N

U N/A

5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?

Y N

U N/A 3DJH[RI

Sheet 3 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 585 Room, Area4 Drywell Area EL 585

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?

Y N

U N/A

7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Y N

U N/A

8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?

Y N

U 3DJH[LRI

Scaffolding and maintenance tools present but good housekeeping practice were observed.

Sheet 4 of 4

5%(/

$UHD :DON%\\ &KHFNOLVW $:&

Location: Bldg. RB Floor El. 585 Room, Area4 Drywell Area EL 585

&RPPHQWV (Additional pages may be added as necessary)

Equipment associated with this Area Walk-by Checklist:

BFN-3-PCV-001-0005 BFN-3-PCV-001-0042 Evaluated by:Travis Hockenberry Date: 2/26/14 Lance Summers 2/26/14 3DJH[LLRI































































  

 



 

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