IR 05000266/2015010: Difference between revisions

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{{Adams
{{Adams
| number = ML15261A631
| number = ML15131A313
| issue date = 09/16/2015
| issue date = 05/08/2015
| title = IR 05000266/2015010, 05000301/2015010; on 08/10/2015 - 08/28/2015; Point Beach Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications. (Jjc)
| title = Ltr. 05/08/15 Point Beach Nuclear Plant, Units 1 and 2 - Information Request for an NRC Triennial Permanent Modifications and 10 CFR 50.59 (Mod/50.59) Baseline Inspection 05000266/2015010; 05000301/2015010 (Jjc)
| author name = Daley R C
| author name = Daley R C
| author affiliation = NRC/RGN-III/DRS/EB3
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = McCartney E
| addressee name = McCartney E A
| addressee affiliation = NextEra Energy Point Beach, LLC
| addressee affiliation = NextEra Energy Point Beach, LLC
| docket = 05000266, 05000301
| docket = 05000266, 05000301
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = IR 2015010
| document report number = IR 2015010
| document type = Inspection Report, Letter
| document type = Inspection Plan, Letter
| page count = 16
| page count = 7
}}
}}


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=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:
[[Issue date::September 16, 2015]]
[[Issue date::May 8, 2015]]


Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241


SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2015010; 05000301/2015010
SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - INFORMATION REQUEST FOR AN NRC TRIENNIAL PERMANENT MODIFICATIONS AND 10 CFR 50.59 (MOD/50.59) BASELINE INSPECTION 05000266/2015010; 05000301/2015010


==Dear Mr. McCartney:==
==Dear Mr. McCartney:==
On August 28, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications inspection at your Point Beach Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on August 28, 2015, with you, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The NRC inspectors documented one finding of very-low safety significance (Green) in this report. This finding was determined to involve a violation of NRC requirements. However, because of its very-low safety significance, and because the issue was entered into your Corrective Action Program, the NRC is treating the issue as a Non-Cited Violation (NCV) in accordance with Section 2.3.2 of the NRC Enforcement Policy. If you contest the subject or severity of the Non-Cited-Violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, Region III; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Point Beach Nuclear Plant. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS)
On August 10, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin a MOD/50.59 baseline inspection at the Point Beach Nuclear Plant, Units 1 and 2. This inspection will be performed in accordance with the NRC baseline Inspection Procedure (IP) 71111.17T. The onsite portion of the inspection will take place on August 10 -14, 2015, and August 24-28, 2015. Experience has shown that these baseline inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection. These documents have been divided into three groups. The first group of information is necessary to ensure that the inspection team is adequately prepared for the inspection. This information should be made available via compact disc, and delivered to the regional office no later than June 30, 2015. The inspection team will review this information and, by July 14, 2015, will request specific items that should be provided for review in the regional office by July 27, 2015. The second group of requested documents contains additional items that the team will review, or need access to, during the inspection. Certain documents contained within Group II (i.e., Item [1]), will be requested for review in the regional office prior to the inspection by July 27, 2015, as identified above. The remaining documents should be available by the first day of the on-site inspection, August 10, 2015. The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection. The lead inspector for this inspection is Mr. Jorge Corujo-Sandín. We understand that our regulatory contact for this inspection is Ms. Kim Locke of your organization. If there are any questions about the inspection or the material requested, please contact the lead inspector at (630) 829-9741, or via e-mail at Jorge.Corujo-Sandin@nrc.gov. 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 Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).


Sincerely,/RA/
Sincerely,/RA Dariusz Szwarc Acting for/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27  
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27  


===Enclosure:===
===Enclosure:===
IR 05000266/2015010; 05000301/2015010  
Modification and 50.59 Inspection Document Request cc w/encl: Distribution via LISTSERV MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST Enclosure Inspection Report: 05000266/2015010; 05000301/2015010 Inspection Dates: August 10-14, 2015 August 24-28, 2015 Inspection Procedure: IP 71111.17T, "Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications" Lead Inspector: Jorge Corujo-Sandín (630) 829-9741 Jorge.Corujo-Sandin@nrc.gov I. Information Requested for In-Office Preparation Week The following information is requested by June 30, 2015, or sooner, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspection team will select specific items from the information requested below, and submit a list to your staff by July 14, 2015. We will request that certain items be made available to the regional office prior to the inspection by July 27, 2015. We request that the remaining items selected from the lists be available and ready for review on the first day of inspection. All requested information should identify the associated system, and cover the time frame from the receipt of information for the last MOD/50.59 inspection to the present. The required information identified below should be provided on compact disc (CD). Please provide three copies of each CD submitted (i.e., one for each inspector). The preferred file format is a searchable "pdf" file. The CDs should be indexed and hyper-linked to facilitate ease of use, if possible. If you have any questions regarding this information, please call the inspection team leader as soon as possible. (1) List of "permanent plant modifications" to systems, structures or components that are field work complete. (For the purpose of this inspection, permanent plant modifications include permanent: plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications.) The list should contain the number of each document, the title, the revision (or date), and the affected system. In addition to the list, please provide a description of each modification and a list of associated calculations and affected procedures. (2) List of all Title 10, Code of Federal Regulations (CFR) Part 50.59 completed evaluations involving (a) calculations, (b) procedure revisions, (c) changes to the facility (modifications), (d) non-routine operating configurations, or (e) departures in methods of analyses. This list should include 50.59 evaluations for the following:
MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST 2 a. Changes that have been made under the provisions of 10 CFR 50.59 that have been updated in accordance with 10 CFR 50.71(e)(4) since the last MOD/50.59 inspection; b. Modifications that are field work complete; and c. Changes to calculations (or initiation of new calculations) that have been issued. The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies). The list should NOT include any evaluations in which prior NRC approval was sought and obtained. (3) A list of all 10 CFR 50.59 changes that have been screened out as not requiring a full evaluation involving: (a) calculations; (b) procedure revisions; (c) changes to the facility (modifications); (d) non-routine operating configurations; or (e) departures in methods of analyses. The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies). (4) A list of any modifications, procedure revisions, or Updated Final Safety Analysis Report (UFSAR) changes where it was determined that 10 CFR 50.59 did not apply. (5) A list of calculation changes that have been issued for use. (6) A list of corrective action documents (open and closed) that address permanent plant modifications or 10 CFR 50.59 issues, concerns, or processes. These documents should also include the corrective action documents associated with the modification, and the 50.59 change implementation. The list should contain the number, title and revision (or date) of each document, the affected system and corresponding documentation (if applicable), and should be sorted in order of significance. (7) Copies of procedures addressing the following: modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modification testing, 10 CFR 50.59 evaluations and screenings, and UFSAR updates. (8) UFSAR updates submitted in accordance with 10 CFR 50.71(e)(4). Provide copies of the complete submittal. (9) Copy of the UFSAR change log or a synopsis of the changes. This should include all of the changes made to the UFSAR that were incorporated in the last 10 CFR 50.71(e)(4) submittal. (10) Electronic copy of the UFSAR and technical specifications, if available. (11) Name(s) and phone numbers for the regulatory and technical contacts. (12) Current management and engineering organizational chart.


===w/Attachment:===
MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST 3 II. Information Requested to be Available Prior to Inspection. Requests will be Made for Specific Item (1) Documents by July 14, 2015, for Availability of Requested Item (1) Documents in Regional Office by July 27, 2015, and Items (2), (3) and (4) Documents on First Day of Inspection (August 10, 2015). (1) Copies of all selected items from Section I. This includes copies of associated documents such as calculations, post-modification test packages, 10 CFR 50.59 evaluations or screenings, and any corrective action documents. (2) Copies of these documents do not need to be solely available to the inspection team as long as the inspectors have easy and unrestrained access to them. a. UFSAR, if not previously provided; b. Original FSAR Volumes; c. Original SER and Supplements; d. FSAR Question and Answers; e. Quality Assurance Plan; f. Technical Specifications, if not previously provided; g. Latest IPE/PRA Report; h. Vendor Manuals; and i. The latest 10 CFR 50.59 UFSAR Update Submittal. (3) Please ensure that other supporting documents for the selected items have been located and are readily retrievable as the inspection team will likely be requesting these documents during the inspection. Examples of supporting documents are: a. Drawings supporting the modifications; b. Procedures affected by the modifications; and c. UFSAR change papers generated due to a 10 CFR 50.59 evaluation. (4) Assessment and Corrective Actions: a. The most recent MOD/50.59 Quality Assurance (QA) audit and/or self-assessment; and b. Corrective action documents (e.g., condition reports, including status of corrective actions) generate as a result of the most recent MOD/50.59 Quality Assurance (QA) audit and/or self-assessment.
Supplemental Information cc w/encl: Distribution via LISTSERV Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-266; 50-301 License No: DPR-24; DPR-27 Report No: 05000266/2015010; 05000301/2015010 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Dates: August 10 - 28, 2015 Inspectors: Jorge J. Corujo-Sandín, Reactor Inspector (Lead) Mark T. Jeffers, Reactor Inspector Michael A. Jones, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety 2


=SUMMARY=
MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST 4 III. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the inspection team's questions or queries during this inspection. (2) Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provide daily during the inspection to each inspection team member). If you have any questions regarding the information requested, please contact the inspection team leader.
Inspection Report 05000266/2015010, 05000301/2015010; 08/10/2015 - 08/28/2015; Point Beach Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications. This report covers a 2-week announced baseline inspection on evaluations of changes, tests, and experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. One finding was identified by the inspectors. The finding was considered a Non-Cited Violation (NCV) of U.S. Nuclear Regulatory Commission (NRC) regulations. The significance of most findings is indicated by their color (i.e., Greater than Green, or Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, "Significance Determination Process."  Cross-cutting aspects were determined using IMC 0310, "Aspects Within the Cross Cutting Areas."  Findings for which the Significance Determination Process does not apply may be Green or be assigned a severity level after NRC management review. All violations of NRC requirements are dispositioned in accordance with the NRC's Enforcement Policy dated July 9, 2013. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 5, dated February 2014.
 
===Cornerstone: Mitigating Systems===
: '''Green.'''
The inspectors identified a finding of very-low safety significance, and an associated NCV of Title 10, Code of Federal Regulations, Part 50, Appendix B, Criterion III, "Design Control," for the licensee's failure to evaluate for potential gas intrusion from the spray additive tank into the containment spray (CS) system during the injection phase of a design-basis accident. As part of immediate corrective actions, the licensee entered the concern in the Corrective Action Process as AR 2068569, and performed an evaluation which determined no air entrainment is expected to occur during the injection phase. The performance deficiency was determined to be more than minor because it was associated with the Mitigating Systems cornerstone attribute of equipment performance, and affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, air intrusion into the CS system could affect the operability of the CS pumps by causing degraded performance and/or air binding of the pumps. The finding screened as having very-low safety significance. Specifically, the finding was a deficiency affecting the design or qualification of a mitigating structure, system, or component (SSC), however, based on the evaluation performed by the licensee the SSC maintained its operability. Based on the timeframe of the violation the inspectors did not identify a cross-cutting aspect associated with this finding.  (Section 1R17.1b) 
 
3
 
=REPORT DETAILS=
 
==REACTOR SAFETY==
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity
{{a|1R17}}
==1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications==
{{IP sample|IP=IP 71111.17T}}
===.1 Evaluation of Changes, Tests, and Experiments===
 
====a. Inspection Scope====
The inspectors reviewed 7 safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59, to determine if the evaluations were adequate, and that prior U.S. Nuclear Regulatory Commission (NRC) approval was obtained as appropriate. The inspectors also reviewed 16 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:  the changes, tests, and experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;  the safety issue requiring the change, tests or experiment was resolved;  the licensee conclusions for evaluations of changes, tests, and experiments were correct and consistent with 10 CFR 50.59; and  the design and licensing basis documentation was updated to reflect the change. The inspectors used, in part, Nuclear Energy Institute (NEI) 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the NRC Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments." This inspection constituted 7 samples of evaluations and 16 samples of screenings and/or applicability determinations as defined in Inspection Procedure (IP) 71111.17-04.
 
====b. Findings====
Failure to Evaluate Containment Spray System for Potential Gas Intrusion
 
=====Introduction:=====
The inspectors identified a finding of very-low safety significance (Green), and an associated Non-Cited Violation (NCV) of 10 CFR Part 50, Appendix B, Criterion III, "Design Control," for the licensee's failure to evaluate for potential gas intrusion from the spray additive tank into the containment spray (CS) system during the injection phase of a design-basis accident (DBA).
 
=====Description:=====
On January 11, 2008, the NRC requested each addressee of Generic Letter (GL) 2008-01 to evaluate its Emergency Core Cooling Systems, decay heat removal, and CS systems licensing basis, design, testing, and corrective actions to 4 ensure that gas accumulation was maintained less than the amount that would challenge the operability of these systems, and take appropriate actions when conditions adverse to quality were identified. The licensee's original actions to address these requests were, in part, to perform design reviews to identify and address gas intrusion mechanisms. Vortexing was among the gas intrusions mechanisms identified by GL 2008-01. Per its design bases, the CS system would operate during both the injection phase and recirculation phase of certain DBA. However, the inspectors identified the licensee had failed to evaluate the CS system against potential gas intrusion during the injection phase, under design bases conditions. Specifically, during the injection phase one of CS design bases functions is to transfer sodium hydroxide (NaOH) from the spray additive tank (SAT) to the containment sump. This function is required to maintain adequate pH level in the sump in order to prevent chloride induced stress corrosion cracking and maintain iodine in the iodate form that will stay in solution. To accomplish this function the CS system is aligned to two separate suction sources, the SAT and the Refueling Water Storage Tank (RWST). The inspectors noted the licensee had evaluated for potential gas intrusion, including vortex prevention, from the RWST but had failed to evaluate for potential draining or vortex formation on the SAT during the injection phase. The inspectors discussed their concerns with the licensee and preliminary results showed the SAT could be completely drained and air ingested into the CS system. This concern was entered into the Corrective Action Program (CAP) as AR 2068569. A follow-up evaluation was performed by the licensee and determined the SAT would not drain down and no air entraining vortex should form. As a result the licensee determined the CS system remained operable.
 
=====Analysis:=====
The inspectors determined the failure to evaluate for potential gas intrusion from the SAT into the CS system during the injection phase of a DBA was contrary to 10 CFR Part 50, Appendix B, Criterion III, "Design Control," and was a performance deficiency. The performance deficiency was determined to be more than minor because it was associated with the Mitigating Systems cornerstone attribute of equipment performance, and affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, air intrusion into the CS system could affect the operability of the CS pumps by causing degraded performance and/or air binding of the pumps. The inspectors determined the finding could be evaluated using the Significance Determination Process in accordance with Inspection Manual Chapter (IMC) 0609, "Significance Determination Process," Attachment 0609.04," "Initial Characterization of Findings."  Specifically, the inspectors used IMC 0609, Appendix A, "Significance Determination Process for Findings At-Power", Exhibit 2, "Mitigating Systems Screening Questions", issued June 19, 2012, and answered "yes" to Question A.1. The finding was a deficiency affecting the design or qualification of a mitigating structure, system, or component (SSC), but the SSC maintained its operability. Specifically the licensee evaluated the CS system and determined the SSC remained operable. As a result, the finding screened as having a very-low safety significance, i.e., Green.
 
5 The inspectors did not identify a cross-cutting aspect associated with this finding. Specifically, the decision to not evaluate the injection phase was taken around the 2008 timeframe when the licensee was responding to the GL 2008-01. As a result the inspectors determined this finding was not representative of the licensee's current performance.
 
=====Enforcement:=====
Title 10 CFR Part 50, Appendix B, Criterion III, "Design Control," requires, in part, that measures shall be established to assure that design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews, by the use of alternate or simplified calculation methods, or by the performance of a suitable testing program. Contrary to the above, as of August 28, 2015, the licensee had not verified the adequacy of the CS design. Specifically, the licensee failed to evaluate for potential gas intrusion into the CS system due to drain down and/or vortexing in the SAT during the injection phase of a DBA.
 
This violation is being treated as an NCV, consistent with Section 2.3.2 of the NRC Enforcement Policy. The violation was entered into the licensee's CAP as AR 2068569. As part of immediate corrective actions the licensee performed an evaluation which determined the SAT would not drain down and no air entraining vortex should form. As a result the licensee determined the CS system remained operable. (NCV 05000266/2015010-01; 05000301/2015010-01, Failure to Evaluate Containment Spray System for Potential Gas Intrusion).
 
===.2 Permanent Plant Modifications===
 
====a. Inspection Scope====
The inspectors reviewed seven permanent plant modifications that had been installed in the plant during the last 3 years. This review included in-plant walkdowns for; portions of the Spent Fuel Pool Instrumentation modification; reroute of transformer 1X04 low voltage side power cables modification; portions of the CS system associated with modified procedures; and the (G-05) gas turbine generator including control cabinets, supporting equipment, including batteries, support diesels, piping, supports, and the air inlet weather hood structure. The modifications were selected based upon risk significance, safety significance, and complexity. The inspectors reviewed the modifications selected to determine if:  the supporting design and licensing basis documentation was updated;  the changes were in accordance with the specified design requirements;  the procedures and training plans affected by the modification have been adequately updated;  the test documentation as required by the applicable test programs has been updated; and  post-modification testing adequately verified system operability and/or functionality. The inspectors also used applicable industry standards to evaluate acceptability of the modifications. The list of modifications and other documents reviewed by the inspectors is included as an Attachment to this report.
 
6 This inspection constituted seven permanent plant modification samples as defined in IP 71111.17-04.
 
==OTHER ACTIVITIES==
{{a|4OA2}}
==4OA2 Problem Identification and Resolution==
 
===.1 Routine Review of Condition Reports===
 
====a. Inspection Scope====
The inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations and permanent plant modifications. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to permanent plant modifications and evaluations of changes, tests, and experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
 
====b. Findings====
No findings were identified.
{{a|4OA6}}
==4OA6 Management Meetings==
 
===.1 Exit Meeting Summary===
On August 28, 2015, the inspectors presented the inspection results to Mr. McCartney, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material provided to the inspection team was identified and will be dispositioned in accordance with applicable processes. ATTACHMENT: 
 
=SUPPLEMENTAL INFORMATION=
 
==KEY POINTS OF CONTACT==
Licensee
: [[contact::S. Aerts]], Performance Improvement Manager
: [[contact::D. DeBoer]], Plant Manager
: [[contact::F. Eichhorst]], Design Engineering Configuration Management Supervisor
: [[contact::D. Forter]], Manager of Projects
: [[contact::R. Harrsch]], Engineering Director
: [[contact::D. Jensen]], Design Engineering
: [[contact::K. Kinjerski]], Procedures Supervisor
: [[contact::T. Lohr]], Reactor Operator
: [[contact::E. McCartney]], Site Vice President
: [[contact::A. Nash Design Engineering Supervisor R. Parker]], Chemistry Manager
: [[contact::M. Rosseau]], Electrical / I&C Design Supervisor
: [[contact::G. Strharsky]], NOS Manager
: [[contact::R. Webber]], Operations Director
: [[contact::P. Wild]], Design Engineering Manager
: [[contact::J. Wilson]], Maintenance Director
: [[contact::B. Woyak]], Licensing Manager
: [[contact::U.S. Nuclear Regulatory Commission D. Oliver]], Senior Resident Inspector
==LIST OF ITEMS==
OPENED, CLOSED AND DISCUSSED
===Opened and Closed===
: 05000266/2015010-01;
: 05000301/2015010-01 NCV Failure to Evaluate Containment Spray System for Potential Gas Intrusion (Section 1R17.1b)  
===Discussed===
None 
 
==LIST OF DOCUMENTS REVIEWED==
The following is a list of documents reviewed during the inspection.
: Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
: Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
: 10
: CFR 50.59 EVALUATIONS Number Description or Title Date or Revision 2010-002-01
: EC 13251 - Reroute of 1X04 Low Voltage Side Power Cables to Façade, Rev. 1 05/22/12 2011-001 1A-01 and 1A-02 Loss of Voltage Relay Setpoint Changes 04/13/11 2011-003-01 Raise EOP Setpoint O.2 (RWST Level to Stop Spray Pumps) to 17% - Radiological Consequence 03/19/12 2011-004 Raise EOP Setpoint O.2 (RWST Level to Stop Spray Pumps) to 17% - Containment Pressure & Temperature 05/29/11 2012-004
: EC 260347 - 120V Vital Cable Short Circuit Protection for Units 1 and 2 11/04/12 2013-001
: Unit 1 and Unit 2 Auxiliary Feedwater Pump Turbine Replacement 10/02/13 2014-004
: EC 277545 "RCP Seal Replacement" 00
: 10
: CFR 50.59 SCREENINGS Number Description or Title Date or Revision 2006-0275 Replacement of Potentially Overdutied Breakers and/or Fuses in MCCs 1B-31, 2B-11, B-33, B-44, B-45, B-46, and B-47 05/02/07 2010-0186 "At-Risk" Installation to Replace Portions of Power Cables from 1X-04 to Façade 09/23/10 2011-0093 AST Related RWST EOP Setpoint Changes 05/28/11 2012-0077
: LIC 1756890, FSAR 6.1 and FSAR 9.2 Revision to Add
: GL 2008-01 Discussion 05/17/12 2012-0177-01 Replace Fuses D72-18-07, D72-22-08, D72-22-10 10/13/13 2012-0119
: EC 260347 - 120V Vital Cable Short Circuit Protection for Units 1 and 2 10/29/12 2012-0199 Revision to IT08A Following Establishment of 1MS-2082 IST Acceptance Criteria 12/06/12 2013-0023 CHANGE FSAR TABLE 9.1-1, COMPONENT COOLING SYSTEM COMPONENT DATA 02/15/13 2013-0043 Revise
: OI 168 "Emergency Diesel Generator Operability" 07/10/13 2013-0046
: G-05 Vibration Monitor: Enable Trip Multiplier Function for Resonant Speed Range 03/08/13 2014-0033
: EC 281270 - Add 60th Cell to Batteries D-05 and D-06 03/24/14 2014-0203-01
: EOP-1.3: Transfer to Containment Sump Recirculation - Low Head Injection 12/18/14 
: 10
: CFR 50.59 SCREENINGS Number Description or Title Date or Revision 2014-0158
: EC 27745 "RCP Seal Replacement" 00 2014-0170 Emergency Diesel Generator Operability 09/20/14 2015-0002 Revise
: AOP-8F for INPO IER L1-11-2 Requirements 01/15/15 2015-0004 Revised
: AOP-8F for Area Radiation Monitor (72.48)
: 01/15/15 2013-0024 Revise TRM 3.7.7,
: OI 70,
: TS 33,
: TS 34, AOP13A,
: AOP-8F, FSAR 9.6.1, OI I55,
: PC 97 Parts 1-8 and 1(2)-SOP-VNCC-001-4 to Allow 85F SW Inlet Temperature and to Specify Operability Limits on Low Pump Bay Level for the G01/G02 EDGs and the Lower Elevations CFCs 03/15/13 2015-0029 Revise Normal And Adverse Containment Pressurizer Level Values In EOP 3.1-3, 3.2, 3.3 00 2015-0032 Revise
: AOP-22 Step 1.c RNO to 60 Hz 04/06/15
: CALCULATIONS Number Description or Title Date or Revision
: CN-SEE-III-08-10 Point Beach Units 1 and 2 RHRS Cooldown Analysis for EPU to 1806 MWT NSSS Power 03
: CN-TA-07-133 Evaluation of an Increased Delay for the Reactor Coolant Pump Undervoltage Reactor Trip Function at Point Beach Nuclear Plant Units 1 and 2 02 N-92-005 125 VDC Coordination Analysis 02 N-93-056 D05 DC System Sizing, Voltage Drop and Short Circuit Calculation 07 N-93-059 D106 DC System Sizing, Voltage Drop and Short Circuit Calculation 08 13-298 2012 CCW Heat Exchangers
: HX-012A/B Thermal Performance Test Results Report 00 13-316 2011 CCW Heat Exchangers
: HX-012A/B Thermal Performance Test Results Report 00 13-323 2009 SFP Heat Exchanger
: HX-013A/B Thermal Performance Test Results 11/14/13 13-326 2012 SFP Heat Exchanger
: HX-013A/B Thermal Performance Test Results 11/20/13 2002-0003 Service Water System Design Basis 04 2003-0046 Battery Chargers Sizing and Current Limit Set Point 04 2005-0037 Spent Fuel Pool Anti-Siphon Provisions 00 2005-0054 Control Building GOTHIC Temperature Calculation 06 2008-005 4.16 KV 7 480 V Loss of Voltage and Underfrequency Relay Setting 02 2007-0002 Emergency Diesel Generator Frequency Uncertainty Calculation 00 2009-0012 Extended Power Uprate (EPU) Related EOP Setpoint Calculations 00 2010-0027 Miscellaneous Level EOP Setpoint Calculations 03 
: CALCULATIONS Number Description or Title Date or Revision 2010-01716 Eductor Analysis - Ingestion of Air into Containment Spray Pump Suction 00 2013-0020 PAB Scenarios for Fukushima Coping 00 129187-E-0030 Cable Ampacity De-Rating Calculation
: 04
: CORRECTIVE ACTION PROGRAM DOCUMENTS INITIATED DURING INSPECTION Number Description or Title Date
: 02068569 2015 MOD/50.59 NRC Inspection Review of SW Temp Increase 08/20/15
: 02069124 Eval 2013-001 Contains Typos
: 08/24/15
: 02069296
: NRC 50.59 / MOD Inspection: Analysis of SAT Emptying 08/25/15
: 02069400
: DBD For CC not Maintained 09/28/15
: 02069630
: NRC 50.59 / MOD Inspection: Potential for Error ---
: 02069693
: OI-169 EDG Operability Potentially Confusing 08/26/15
: 02069856
: TRM 3.7.7 08/27/15
: 02069859 Discrepancy in CC HX Fouling 08/27/15
: CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED Number Description or Title Date 98-0036 IST Program
: Does Not List Requirement to Exercise and Stroke Time Spray Additive Tank Valves 01/06/98
: 01221210 Degraded Seat Material on Unit 1
: SI-854 Check Valves 09/15/95
: 01316511 Appendix R Associated Circuits 120VAC Coordination Concern 04/21/07
: 01659682 Fuse Replace for D72-22-08 and -22-10, D72-18-07 and -18-10 06/10/11
: 01756590 Possible FSAR Update in Response to
: GL 2008-01 04/19/12
: 01794746 Preconditioning Issue in
: IT-08A TDAFP Test 08/17/12
: 01891067
: COMP-NA CR SITE DRAWING AND PROCEDURE CHANGES POST MODIFICATIONS 07/22/13
: 01904504 Clarify FSAR 7.4.3 & 10.2 Re: AFWP Suction Transfer to
: SW 09/17/13
: 01943408 FSAR Overstates Docketed Design Bases 02/25/14
: 01950740 DC Calculation Issues Identified 03/22/14
: 01979452
: Historical 50.59 Evaluations Did Not Identify FSAR Impact 07/28/14
: 01985361 Additional Performance Issues with 50.59 Products 08/19/15
: 01996270 CLB Updates are Not Timely 10/05/14
: 01998626 Revise FSAR Section 8.1.4 to Update Ref. 2 10/13/14
: 02032684
: AOP-22 Unit 1 - (LAR 4/20/2015) RFI 4/16 03/16/15
: 02037428 Plant Changed Without an EC or 50.59 04/24/15
: 02038568 RCP No. 1 Seal EOP Setpoint Not Updated Since 1995 04/07/15 
: DRAWINGS Number Description or Title Revision E-6 Sheet 1 Single Line Diagram - 125V DC Dist. System 66 MCCK00000143, Sheet 3 P&ID Auxiliary Coolant System 43 MCCK00000422, Sheet 2 P&ID Auxiliary Coolant System 22 MESK00000259, Sheet 1 P&ID Safety Injection System 54 MSFK00000271, Sheet 1 P&ID Auxiliary Coolant System 71 MSIK00000165, Sheet 2 P&ID Safety Injection System 55 MSIK00001248, Sheet 3 P&ID Safety Injection System 48
: MODIFICATIONS Number Description or Title Revision
: EC 008075 Replacement of Potentially Overdutied Breakers and/or Fuses in MCCs 1B-31, 2B-11, B-33, B-44, B-45, B-46, and B-47 00
: EC 013251 Reroute of 1X04 Low Voltage Side Power Cables to Façade 00
: EC 260287
: REPLACEMENT OF ACCIDENT FAN COOLER HOSES WITH ALTERNATE DESIGN FLEX 00
: EC 260313
: UNIT 2 CONTAINMENT SUMP A LEVEL TRANSMITTER REPLACEMENT 01
: EC 260347 120V Vital Cable Short Circuit Protection for Units 1 and 2 01
: EC 260579 0P-032E-M, SW Pump Motor Equivalency 00
: EC 260795 125 VDC Power Supply Reconfiguration for Unit 1 Turbine Auto-Stop Trip (AST) / Emergency Trip (ET) Control Circuits 00
: EC 260820 Install Test Switches for 4.16kV Bus Loss of voltage Relays - Unit 2 00
: EC 261461 Install Test Switches for 4.16kV Bus Loss of voltage Relays - Unit 1 00
: EC 261964
: P-032D-M SW PUMP MOTOR REPLACED WITH SPARE MOTOR (+) 00
: EC 270973 Westinghouse/Cutler Hammer
: DHP-VR Breaker Enhancements 01
: EC 271690 Evaluation of an Increased Delay for the Reactor Coolant Pump Undervoltage Reactor Trip Function at Point Beach Nuclear Plant Units 1 and 2 01
: EC 276487 Revise RWST Low-Low Level Alarm Setpoint in STPT 11.1 and Other Affected Documents Per CALC
: PBNP-IC-02-004-A 00
: EC 276803 NRC Order Fukushima Strategy - Spent Fuel Pool Instrumentation Upgrade 02 
: MODIFICATIONS Number Description or Title Revision
: EC 277206 Replace Fuses D72-18-07, D72-18-10, D72-22-08, D72-22-10 01
: EC 277545 RCP Seal Replacement 00
: EC 281270 D-05 and D-06 Battery Addition 02
: OTHER DOCUMENTS Number Description or Title Date or Revision
: DBD-11 Safety Injection & Containment Spray Pump Design Bases Document 22
: EC 278678 G-05 Vibration Monitor: Enable Trip Multiplier Function for Resonant Speed Range 00 Evaluation
: 00456339 Commercial Grade Dedication - Fast Acting Fuse 02/12/14
: FPTE-2007-001 Technical Evaluation of Associated Circuit by Common Power Supply and by Common Enclosure 04/30/07
: WEP-98-017 Containment Pressure and Temperature Increase During Recirculation Due to Loos of RHR Heat Exchanger Cooling 03/05/98
: WO 40127282 07 H52-DHPVR2000-3; Breaker Overhaul 03/27/14
: WO 40202961 01 D-06 Battery Modified Performance Test 01/21/14
: WO 40220768 G-05 Apply Vib Trip Block to Turbine Resonant Speed Range 03/08/13
: WO 40301275 01 D-06/Connect 60th Cell into Battery D-06 Per
: EC 281270 04/25/14
: WO 40301276 01
: D-05/Connect 60th Cell into Battery D-05 06/18/14
: WO 40302871 01 D-05 / D-07, Battery Surveillance Tests 07/15/14
: WO 40344232 01 125V, Station Tech Spec Batteries Weekly Inspection 08/03/15 2013-0013 Change FSAR Table 9.1-1, "Component Cooling System Component Data"
: 02/15/13
: PROCEDURES Number Description or Title Revision --- Gas Accumulation Management Program 03
: AOP 22 EDG Load Management
: 15 EOP 0.1 Reactor Trip Response 31
: EOP-1.3 Unit 1 Transfer to Containment Sump Recirculation - Low Head Injection 52
: OI 168 Emergency Diesel Generator Operability 20
: RMP 9046-4 Seven Day Pilot Cell Battery Surveillance 15 STPT 5.3
: Pressurizer Pressure and Level Control 11
: TS 84 Emergency Diesel Generator G-04 Monthly 34
==LIST OF ACRONYMS==
: [[USED]] [[]]
: [[ADAMS]] [[Agencywide Documents Access and Management System]]
: [[CAP]] [[Corrective Action Program]]
: [[CFR]] [[Code of Federal Regulations]]
: [[CS]] [[Containment Spray]]
: [[DBA]] [[Design-Basis Accident]]
: [[DRP]] [[Division of Reactor Projects]]
: [[DRS]] [[Division of Reactor Safety]]
: [[GL]] [[Generic Letter]]
: [[IMC]] [[Inspection Manual Chapter]]
: [[IP]] [[Inspection Procedure]]
: [[NCV]] [[Non-Cited Violation]]
: [[NEI]] [[Nuclear Energy Institute]]
: [[NRC]] [[]]
: [[U.S.]] [[Nuclear Regulatory Commission]]
: [[PARS]] [[Publicly Available Records System]]
: [[RWST]] [[Refueling Water Storage Tank]]
: [[SAT]] [[Spray Additive Tank SSC Structure, System, and Component]]
: [[E.]] [[McCartney -2- In accordance with Title 10 of the Code of Federal Regulations (10]]
CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS)
component of the
: [[NRC]] [['s Agencywide Documents Access and Management System (ADAMS).]]
: [[ADAMS]] [[is accessible from the]]
NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely,  /RA/
Robert
: [[C.]] [[Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos.]]
: [[DPR]] [[-24; DPR-27 Enclosure: IR 05000266/2015010; 05000301/2015010    w/Attachment:  Supplemental Information cc w/encl:  Distribution via]]
}}
}}

Revision as of 19:09, 11 June 2018

Ltr. 05/08/15 Point Beach Nuclear Plant, Units 1 and 2 - Information Request for an NRC Triennial Permanent Modifications and 10 CFR 50.59 (Mod/50.59) Baseline Inspection 05000266/2015010; 05000301/2015010 (Jjc)
ML15131A313
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/08/2015
From: Daley R C
Engineering Branch 3
To: McCartney E A
Point Beach
References
IR 2015010
Download: ML15131A313 (7)
v • d • e


Text

May 8, 2015

Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - INFORMATION REQUEST FOR AN NRC TRIENNIAL PERMANENT MODIFICATIONS AND 10 CFR 50.59 (MOD/50.59) BASELINE INSPECTION 05000266/2015010; 05000301/2015010

Dear Mr. McCartney:

On August 10, 2015, the U.S. Nuclear Regulatory Commission (NRC) will begin a MOD/50.59 baseline inspection at the Point Beach Nuclear Plant, Units 1 and 2. This inspection will be performed in accordance with the NRC baseline Inspection Procedure (IP) 71111.17T. The onsite portion of the inspection will take place on August 10 -14, 2015, and August 24-28, 2015. Experience has shown that these baseline inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection. These documents have been divided into three groups. The first group of information is necessary to ensure that the inspection team is adequately prepared for the inspection. This information should be made available via compact disc, and delivered to the regional office no later than June 30, 2015. The inspection team will review this information and, by July 14, 2015, will request specific items that should be provided for review in the regional office by July 27, 2015. The second group of requested documents contains additional items that the team will review, or need access to, during the inspection. Certain documents contained within Group II (i.e., Item [1]), will be requested for review in the regional office prior to the inspection by July 27, 2015, as identified above. The remaining documents should be available by the first day of the on-site inspection, August 10, 2015. The third group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection. The lead inspector for this inspection is Mr. Jorge Corujo-Sandín. We understand that our regulatory contact for this inspection is Ms. Kim Locke of your organization. If there are any questions about the inspection or the material requested, please contact the lead inspector at (630) 829-9741, or via e-mail at Jorge.Corujo-Sandin@nrc.gov. 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 Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA Dariusz Szwarc Acting for/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27

Enclosure:

Modification and 50.59 Inspection Document Request cc w/encl: Distribution via LISTSERV MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST Enclosure Inspection Report: 05000266/2015010; 05000301/2015010 Inspection Dates: August 10-14, 2015 August 24-28, 2015 Inspection Procedure: IP 71111.17T, "Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications" Lead Inspector: Jorge Corujo-Sandín (630) 829-9741 Jorge.Corujo-Sandin@nrc.gov I. Information Requested for In-Office Preparation Week The following information is requested by June 30, 2015, or sooner, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspection team will select specific items from the information requested below, and submit a list to your staff by July 14, 2015. We will request that certain items be made available to the regional office prior to the inspection by July 27, 2015. We request that the remaining items selected from the lists be available and ready for review on the first day of inspection. All requested information should identify the associated system, and cover the time frame from the receipt of information for the last MOD/50.59 inspection to the present. The required information identified below should be provided on compact disc (CD). Please provide three copies of each CD submitted (i.e., one for each inspector). The preferred file format is a searchable "pdf" file. The CDs should be indexed and hyper-linked to facilitate ease of use, if possible. If you have any questions regarding this information, please call the inspection team leader as soon as possible. (1) List of "permanent plant modifications" to systems, structures or components that are field work complete. (For the purpose of this inspection, permanent plant modifications include permanent: plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications.) The list should contain the number of each document, the title, the revision (or date), and the affected system. In addition to the list, please provide a description of each modification and a list of associated calculations and affected procedures. (2) List of all Title 10, Code of Federal Regulations (CFR) Part 50.59 completed evaluations involving (a) calculations, (b) procedure revisions, (c) changes to the facility (modifications), (d) non-routine operating configurations, or (e) departures in methods of analyses. This list should include 50.59 evaluations for the following:

MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST 2 a. Changes that have been made under the provisions of 10 CFR 50.59 that have been updated in accordance with 10 CFR 50.71(e)(4) since the last MOD/50.59 inspection; b. Modifications that are field work complete; and c. Changes to calculations (or initiation of new calculations) that have been issued. The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies). The list should NOT include any evaluations in which prior NRC approval was sought and obtained. (3) A list of all 10 CFR 50.59 changes that have been screened out as not requiring a full evaluation involving: (a) calculations; (b) procedure revisions; (c) changes to the facility (modifications); (d) non-routine operating configurations; or (e) departures in methods of analyses. The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies). (4) A list of any modifications, procedure revisions, or Updated Final Safety Analysis Report (UFSAR) changes where it was determined that 10 CFR 50.59 did not apply. (5) A list of calculation changes that have been issued for use. (6) A list of corrective action documents (open and closed) that address permanent plant modifications or 10 CFR 50.59 issues, concerns, or processes. These documents should also include the corrective action documents associated with the modification, and the 50.59 change implementation. The list should contain the number, title and revision (or date) of each document, the affected system and corresponding documentation (if applicable), and should be sorted in order of significance. (7) Copies of procedures addressing the following: modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modification testing, 10 CFR 50.59 evaluations and screenings, and UFSAR updates. (8) UFSAR updates submitted in accordance with 10 CFR 50.71(e)(4). Provide copies of the complete submittal. (9) Copy of the UFSAR change log or a synopsis of the changes. This should include all of the changes made to the UFSAR that were incorporated in the last 10 CFR 50.71(e)(4) submittal. (10) Electronic copy of the UFSAR and technical specifications, if available. (11) Name(s) and phone numbers for the regulatory and technical contacts. (12) Current management and engineering organizational chart.

MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST 3 II. Information Requested to be Available Prior to Inspection. Requests will be Made for Specific Item (1) Documents by July 14, 2015, for Availability of Requested Item (1) Documents in Regional Office by July 27, 2015, and Items (2), (3) and (4) Documents on First Day of Inspection (August 10, 2015). (1) Copies of all selected items from Section I. This includes copies of associated documents such as calculations, post-modification test packages, 10 CFR 50.59 evaluations or screenings, and any corrective action documents. (2) Copies of these documents do not need to be solely available to the inspection team as long as the inspectors have easy and unrestrained access to them. a. UFSAR, if not previously provided; b. Original FSAR Volumes; c. Original SER and Supplements; d. FSAR Question and Answers; e. Quality Assurance Plan; f. Technical Specifications, if not previously provided; g. Latest IPE/PRA Report; h. Vendor Manuals; and i. The latest 10 CFR 50.59 UFSAR Update Submittal. (3) Please ensure that other supporting documents for the selected items have been located and are readily retrievable as the inspection team will likely be requesting these documents during the inspection. Examples of supporting documents are: a. Drawings supporting the modifications; b. Procedures affected by the modifications; and c. UFSAR change papers generated due to a 10 CFR 50.59 evaluation. (4) Assessment and Corrective Actions: a. The most recent MOD/50.59 Quality Assurance (QA) audit and/or self-assessment; and b. Corrective action documents (e.g., condition reports, including status of corrective actions) generate as a result of the most recent MOD/50.59 Quality Assurance (QA) audit and/or self-assessment.

MODIFICATION AND 50.59 INSPECTION DOCUMENT REQUEST 4 III. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the inspection team's questions or queries during this inspection. (2) Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provide daily during the inspection to each inspection team member). If you have any questions regarding the information requested, please contact the inspection team leader.

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