IR 05000266/2015010: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532
[[Issue date::September 16, 2015]]
-4352 September 16, 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
 
- EVALUATION S OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2015010; 05000301/2015010 Dear Mr. McCartney
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
: 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 Plan The enclosed inspection report documents the inspection results which were discussed on August 28, 2015, with you, and other members of your staf 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 licens The inspectors reviewed selected procedures and records, observed activities, and interviewed personne The NRC inspectors documented one finding of very
 
-low safety significance (Green)
==Dear Mr. McCartney:==
in this repor This finding was determined to involve a violation of NRC requirement 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. of the NRC Enforcement Polic If you contest the subject or severity of the N on-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:
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)
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
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).
-0001; and the NRC Resident Inspector at the Point Beach Nuclear Plan 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/
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  
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No ; 50-301 License Nos. DPR-24; DPR-27  


===Enclosure:===
===Enclosure:===
IR 05000266/2015010; 05000301/2015010  
IR 05000266/2015010; 05000301/2015010


===w/Attachment:===
===w/Attachment:===
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  
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=
=SUMMARY=
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.
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 J uly 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===
===Cornerstone: Mitigating Systems===
: '''Green.'''
: '''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) 
The inspectors identified a finding of very-low safety significance
, and an associated N CV 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 System s 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.


3
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=
=REPORT DETAILS=


==REACTOR SAFETY==
==REACTOR SAFETY==
Cornerstones:  Initiating Events, Mitigating Systems, and Barrier Integrity
Cornerstone s:  Initiating Events, Mitigating Systems, and Barrier Integ rity 1R17 Evaluation s of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.17 T)
{{a|1R17}}
 
==1R17 Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications==
===.1 Evaluation of Changes, Tests, and===
{{IP sample|IP=IP 71111.17T}}
 
===.1 Evaluation of Changes, Tests, and Experiments===
Experiments


====a. Inspection Scope====
====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.
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 o f screenings and/or applicability determinations as defined in Inspection Procedure (
IP) 71111.17-04.


====b. Findings====
====b. Findings====
Line 63: Line 105:


=====Introduction:=====
=====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).
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:=====
=====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.
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 function s 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:=====
=====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.
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 System s 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 bindi ng 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.
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:=====
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.
: 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.


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).
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 a n NCV, consistent with Section 2.3.2 of the NRC Enforcement Poli cy. 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===
===.2 Permanent Plant Modifications===


====a. Inspection Scope====
====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.
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 ai r 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.
6 This inspection constituted seven permanent plant modification samples as defined in IP 71111.17-04.
Line 92: Line 168:


====a. Inspection Scope====
====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.
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 p lant 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====
====b. Findings====
No findings were identified.
No findings were identified.
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Management Meetings==
==4OA6 Management Meetings==


===.1 Exit Meeting Summary===
===.1 Exit Meeting===
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:   
 
Summary  On August 28, 2015
, the inspector s 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=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
Licensee  
T Licensee  
: [[contact::S. Aerts]], Performance Improvement Manager  
: [[contact::S. Aerts]], Performance Improvement Manager
: [[contact::D. DeBoer]], Plant Manager  
: [[contact::D. DeBoer]], Plant Manager
: [[contact::F. Eichhorst]], Design Engineering Configuration Management Supervisor  
: [[contact::F. Eichhorst]], Design Engineering Configuration Management Supervisor
: [[contact::D. Forter]], Manager of Projects  
: [[contact::D. Forter]], Manager of Projects
: [[contact::R. Harrsch]], Engineering Director  
: [[contact::R. Harrsch]], Engineering
: [[contact::D. Jensen]], Design Engineering  
Director  
: [[contact::K. Kinjerski]], Procedures Supervisor  
: [[contact::D. Jensen]], Design Engineering
: [[contact::T. Lohr]], Reactor Operator  
: [[contact::K. Kinjerski]], Procedures Supervisor
: [[contact::E. McCartney]], Site Vice President  
: [[contact::T. Lohr]], Reactor Operator
: [[contact::A. Nash Design Engineering Supervisor R. Parker]], Chemistry Manager  
: [[contact::E. McCartney]], Site Vice President
: [[contact::M. Rosseau]], Electrical / I&C Design Supervisor  
A. Nash Design Engineering Supervisor
: [[contact::G. Strharsky]], NOS Manager  
: [[contact::R. Parker]], Chemistry Manager
: [[contact::R. Webber]], Operations Director  
: [[contact::M. Rosseau]], Electrical / I&C Design Supervisor
: [[contact::P. Wild]], Design Engineering Manager  
: [[contact::G. Strharsky]], NOS Manager
: [[contact::J. Wilson]], Maintenance Director  
: [[contact::R. Webber]], Operations Director
: [[contact::B. Woyak]], Licensing Manager  
: [[contact::P. Wild]], Design Engineering Manager
: [[contact::U.S. Nuclear Regulatory Commission D. Oliver]], Senior Resident Inspector  
: [[contact::J. Wilson]], Maintenance Director
==LIST OF ITEMS==
: [[contact::B. Woyak]], Licensing Manager
OPENED, CLOSED AND DISCUSSED  
U.S. Nuclear Regulatory Commission
===Opened and Closed===
: [[contact::D. Oliver]], Senior Resident Inspector
: 05000266/2015010-01;  
LIST OF ITEMS OPENED, CLOSED AND DISCUSSED Opened and Closed
: 05000301/2015010-01 NCV Failure to Evaluate Containment Spray System for Potential Gas Intrusion (Section 1R17.1b)  
05000266/2015010
===Discussed===
-01; 05000301/2015010
None   
-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.
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"
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
2/06/12 2013-0023 CHANGE FSAR TABLE 9.1
-1, COMPONENT COOLING SYSTEM COMPONENT DATA
2/15/13 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
2/18/14
10 CFR 50.59 SCREENINGS
Number Description or Title
Date or Revision 2014-0158 EC 27745 "RCP Seal Replacement"
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
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
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
N-92-005 125 VDC Coordination Analysis
N-93-056 D05 DC System Sizing, Voltage Drop and Short Circuit Calculation
N-93-059 D106 DC System Sizing, Voltage Drop and Short Circuit
Calculation
13-298 2012 CCW Heat Exchangers HX
-012A/B Thermal Performance Test Results Report
13-316 2011 CCW Heat Exchangers HX
-012A/B Thermal Performance Test Results Report
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
2003-0046 Battery Chargers Sizing and Current Limit Set Point
2005-0037 Spent Fuel Pool Anti
-Siphon Provisions
2005-0054 Control Building GOTHIC Temperature Calculation
2008-005 4.16 KV 7 480 V Loss of Voltage and Underfrequency Relay Setting
2007-0002 Emergency Diesel Generator Frequency Uncertainty Calculation
2009-0012 Extended Power Uprate (EPU) Related EOP Setpoint Calculations
2010-0027 Miscellaneous Level EOP Setpoint Calculations
CALCULATIONS
Number Description or Title
Date or Revision 2010-01716 Eductor Analysis
- Ingestion of Air into Containment Spray Pump Suction
2013-0020 PAB Scenarios for Fukushima Coping
129187-E-0030 Cable Ampacity De
-Rating Calculation
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
2/25/14 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
MCCK00000143, Sheet 3 P&ID Auxiliary Coolant System
MCCK00000422, Sheet 2 P&ID Auxiliary Coolant System
MESK00000259, Sheet 1 P&ID Safety Injection System
MSFK00000271, Sheet 1 P&ID Auxiliary Coolant System
MSIK00000165, Sheet 2 P&ID Safety
Injection System
MSIK00001248, Sheet 3 P&ID Safety Injection System
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
EC 260313  UNIT 2 CONTAINMENT SUMP A LEVEL TRANSMITTER REPLACEMENT
EC 260347
20V Vital Cable Short Circuit Protection for Units 1 and
01 EC 260579
0P-032E-M, SW Pump Motor Equivalency
EC 260795
25 VDC Power Supply Reconfiguration for Unit 1 Turbine Auto
-Stop Trip (AST) / Emergency Trip (ET) Control Circuits
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 (+)
EC 270973
Westinghouse/Cutler Hammer DHP
-VR Breaker Enhancements
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
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
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
EC 281270
D-05 and D-06 Battery Addition
OTHER DOCUMENTS
Number Description or Title
Date or Revision DBD-11 Safety Injection & Containment Spray Pump Design Bases Document
EC 278678
G-05 Vibration Monitor: Enable Trip Multiplier Function for Resonant Speed Range
Evaluation 00456339
Commercial Grade Dedication
- Fast Acting Fuse
2/12/14 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
25V, Station Tech Spec Batteries Weekly Inspection
08/03/15 2013-0013 Change FSAR Table 9.1
-1, "Component Cooling System Component Data"
2/15/13  PROCEDURES
Number Description or Title
Revision --- Gas Accumulation Management Program
AOP 22 EDG Load Management
EOP 0.1 Reactor Trip Response
EOP-1.3 Unit 1
Transfer to Containment Sump Recirculation
- Low Head Injection
OI 168 Emergency Diesel Generator Operability
RMP 9046-4 Seven Day Pilot Cell Battery Surveillance
STPT 5.3  Pressurizer Pressure and Level Control
TS 84 Emergency Diesel Generator G
-04 Monthly
LIST OF ACRONYMS USE
D 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 Project
s 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


==LIST OF DOCUMENTS REVIEWED==
E. McCartney
The following is a list of documents reviewed during the inspection.
  -2- In accordance with Title 10 of the Code of Federal Regulations
: 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.
(10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy
: 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.
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)
: 10
component of the NRC's Agencywide
: CFR 50.59 EVALUATIONS Number Description or Title Date or Revision 2010-002-01
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading
: 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
-rm/adams.html
: EC 260347 - 120V Vital Cable Short Circuit Protection for Units 1 and 2 11/04/12 2013-001
(the Public Electronic Reading Room).
: Unit 1 and Unit 2 Auxiliary Feedwater Pump Turbine Replacement 10/02/13 2014-004
Sincerely,
: EC 277545 "RCP Seal Replacement" 00
  /RA/
: 10
Robert  
: 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
: [[contact::C. Daley]], Chief Engineering Branch 3
: LIC 1756890, FSAR 6.1 and FSAR 9.2 Revision to Add
Division of Reactor Safety Docket Nos.
: 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
50-266; 50-301 License Nos. DPR-24; DPR-27 Enclosure:
: 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
IR 05000266/2015010; 05000301/2015010
: OI 168 "Emergency Diesel Generator Operability" 07/10/13 2013-0046
w/Attachment:  Supplemental Information
: G-05 Vibration Monitor: Enable Trip Multiplier Function for Resonant Speed Range 03/08/13 2014-0033
cc w/encl:  Distribution via LISTSERV
: EC 281270 - Add 60th Cell to Batteries D-05 and D-06 03/24/14 2014-0203-01
DISTRIBUTION
: EOP-1.3: Transfer to Containment Sump Recirculation - Low Head Injection 12/18/14 
w/encl: Janelle Jessie
: 10
RidsNrrDorlLpl3
: CFR 50.59 SCREENINGS Number Description or Title Date or Revision 2014-0158
-1 Resource
: EC 27745 "RCP Seal Replacement" 00 2014-0170 Emergency Diesel Generator Operability 09/20/14 2015-0002 Revise
RidsNrrPMPointBeach
: AOP-8F for INPO IER L1-11-2 Requirements 01/15/15 2015-0004 Revised
RidsNrrDirsIrib Resource
: AOP-8F for Area Radiation Monitor (72.48)
Cynthia Pederson
: 01/15/15 2013-0024 Revise TRM 3.7.7,
Darrell Roberts
: OI 70,
Richard Skokowski
: TS 33,
Allan Barker
: TS 34, AOP13A,
Carole Ariano
: AOP-8F, FSAR 9.6.1, OI I55,
Linda Linn
: 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
DRPIII DRSIII Jim Clay Carmen Olteanu
: AOP-22 Step 1.c RNO to 60 Hz 04/06/15
ROPreports.Resource@nrc.gov
: CALCULATIONS Number Description or Title Date or Revision
ADAMS Accession Number ML15261A631
: CN-SEE-III-08-10 Point Beach Units 1 and 2 RHRS Cooldown Analysis for EPU to 1806 MWT NSSS Power 03
Publicly Available
: 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
Non-Publicly Available
: HX-012A/B Thermal Performance Test Results Report 00 13-316 2011 CCW Heat Exchangers
Sensitive
: HX-012A/B Thermal Performance Test Results Report 00 13-323 2009 SFP Heat Exchanger
Non-Sensitive
: HX-013A/B Thermal Performance Test Results 11/14/13 13-326 2012 SFP Heat Exchanger
To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII  RIII  RIII  RIII  NAME JCorujo-Sandin:cl
: 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 
RDaley  DATE 09/16/15 09/16/15  OFFICIAL RECORD COPY
: 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 21:08, 30 June 2018

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)
ML15261A631
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 09/16/2015
From: Daley R C
Engineering Branch 3
To: McCartney E
Point Beach
References
IR 2015010
Download: ML15261A631 (16)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUIT E 210 LISLE, IL 60532

-4352 September 16, 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

- EVALUATION S OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2015010; 05000301/2015010 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 Plan The enclosed inspection report documents the inspection results which were discussed on August 28, 2015, with you, and other members of your staf 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 licens The inspectors reviewed selected procedures and records, observed activities, and interviewed personne The NRC inspectors documented one finding of very

-low safety significance (Green)

in this repor This finding was determined to involve a violation of NRC requirement 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. of the NRC Enforcement Polic If you contest the subject or severity of the N on-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 Plan 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 No ; 50-301 License Nos. DPR-24; DPR-27

Enclosure:

IR 05000266/2015010; 05000301/2015010

w/Attachment:

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

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 J uly 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 N CV 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 System s 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

Cornerstone s: Initiating Events, Mitigating Systems, and Barrier Integ rity 1R17 Evaluation s of Changes, Tests, and Experiments and Permanent Plant Modifications (71111.17 T)

.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 o f 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 function s 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 System s 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 bindi ng 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 a n NCV, consistent with Section 2.3.2 of the NRC Enforcement Poli cy. 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 ai r 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

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 p lant 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.

4OA6 Management Meetings

.1 Exit Meeting

Summary On August 28, 2015

, the inspector s 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

SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC

T Licensee

S. Aerts, Performance Improvement Manager
D. DeBoer, Plant Manager
F. Eichhorst, Design Engineering Configuration Management Supervisor
D. Forter, Manager of Projects
R. Harrsch, Engineering

Director

D. Jensen, Design Engineering
K. Kinjerski, Procedures Supervisor
T. Lohr, Reactor Operator
E. McCartney, Site Vice President

A. Nash Design Engineering Supervisor

R. Parker, Chemistry Manager
M. Rosseau, Electrical / I&C Design Supervisor
G. Strharsky, NOS Manager
R. Webber, Operations Director
P. Wild, Design Engineering Manager
J. Wilson, Maintenance Director
B. Woyak, Licensing Manager

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.

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"

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

2/06/12 2013-0023 CHANGE FSAR TABLE 9.1

-1, COMPONENT COOLING SYSTEM COMPONENT DATA

2/15/13 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

2/18/14

10 CFR 50.59 SCREENINGS

Number Description or Title

Date or Revision 2014-0158 EC 27745 "RCP Seal Replacement"

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

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

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

N-92-005 125 VDC Coordination Analysis

N-93-056 D05 DC System Sizing, Voltage Drop and Short Circuit Calculation

N-93-059 D106 DC System Sizing, Voltage Drop and Short Circuit

Calculation

13-298 2012 CCW Heat Exchangers HX

-012A/B Thermal Performance Test Results Report

13-316 2011 CCW Heat Exchangers HX

-012A/B Thermal Performance Test Results Report

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

2003-0046 Battery Chargers Sizing and Current Limit Set Point

2005-0037 Spent Fuel Pool Anti

-Siphon Provisions

2005-0054 Control Building GOTHIC Temperature Calculation

2008-005 4.16 KV 7 480 V Loss of Voltage and Underfrequency Relay Setting

2007-0002 Emergency Diesel Generator Frequency Uncertainty Calculation

2009-0012 Extended Power Uprate (EPU) Related EOP Setpoint Calculations

2010-0027 Miscellaneous Level EOP Setpoint Calculations

CALCULATIONS

Number Description or Title

Date or Revision 2010-01716 Eductor Analysis

- Ingestion of Air into Containment Spray Pump Suction

2013-0020 PAB Scenarios for Fukushima Coping

129187-E-0030 Cable Ampacity De

-Rating Calculation

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

2/25/14 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

MCCK00000143, Sheet 3 P&ID Auxiliary Coolant System

MCCK00000422, Sheet 2 P&ID Auxiliary Coolant System

MESK00000259, Sheet 1 P&ID Safety Injection System

MSFK00000271, Sheet 1 P&ID Auxiliary Coolant System

MSIK00000165, Sheet 2 P&ID Safety

Injection System

MSIK00001248, Sheet 3 P&ID Safety Injection System

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

EC 260313 UNIT 2 CONTAINMENT SUMP A LEVEL TRANSMITTER REPLACEMENT

EC 260347

20V Vital Cable Short Circuit Protection for Units 1 and

01 EC 260579

0P-032E-M, SW Pump Motor Equivalency

EC 260795

25 VDC Power Supply Reconfiguration for Unit 1 Turbine Auto

-Stop Trip (AST) / Emergency Trip (ET) Control Circuits

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 (+)

EC 270973

Westinghouse/Cutler Hammer DHP

-VR Breaker Enhancements

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

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

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

EC 281270

D-05 and D-06 Battery Addition

OTHER DOCUMENTS

Number Description or Title

Date or Revision DBD-11 Safety Injection & Containment Spray Pump Design Bases Document

EC 278678

G-05 Vibration Monitor: Enable Trip Multiplier Function for Resonant Speed Range

Evaluation 00456339

Commercial Grade Dedication

- Fast Acting Fuse

2/12/14 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

25V, Station Tech Spec Batteries Weekly Inspection

08/03/15 2013-0013 Change FSAR Table 9.1

-1, "Component Cooling System Component Data"

2/15/13 PROCEDURES

Number Description or Title

Revision --- Gas Accumulation Management Program

AOP 22 EDG Load Management

EOP 0.1 Reactor Trip Response

EOP-1.3 Unit 1

Transfer to Containment Sump Recirculation

- Low Head Injection

OI 168 Emergency Diesel Generator Operability

RMP 9046-4 Seven Day Pilot Cell Battery Surveillance

STPT 5.3 Pressurizer Pressure and Level Control

TS 84 Emergency Diesel Generator G

-04 Monthly

LIST OF ACRONYMS USE

D 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 Project

s 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 LISTSERV

DISTRIBUTION

w/encl: Janelle Jessie

RidsNrrDorlLpl3

-1 Resource

RidsNrrPMPointBeach

RidsNrrDirsIrib Resource

Cynthia Pederson

Darrell Roberts

Richard Skokowski

Allan Barker

Carole Ariano

Linda Linn

DRPIII DRSIII Jim Clay Carmen Olteanu

ROPreports.Resource@nrc.gov

ADAMS Accession Number ML15261A631

Publicly Available

Non-Publicly Available

Sensitive

Non-Sensitive

To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME JCorujo-Sandin:cl

RDaley DATE 09/16/15 09/16/15 OFFICIAL RECORD COPY

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000266/2015010&oldid=773943"