IR 05000266/2012007
| ML12132A221 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/10/2012 |
| From: | Hironori Peterson Engineering Branch 3 |
| To: | Meyer L Point Beach |
| Alan Dahbur | |
| References | |
| IR-12-007 | |
| Download: ML12132A221 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 May 10, 2012 Mr. Larry Meyer Senior 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, OR EXPERIMENTS ANDPERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2012007(DRS); 05000301/2012007(DRS)
Dear Mr. Meyer:
On May 3, 2012, the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Inspection at your Point Beach Nuclear Plant. The enclosed inspection report documents the inspection results which were discussed on May 3, 2012 , 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.
Based on the results of this inspection, no findings of significance were identified
. In accordance with Title 10, Code of Federal Regulations (CFR), Part 50, Section 2.390 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 Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC w ebsite at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Hironori Peterson , Acting Chief Engineering Branch 3 Division of Reactor Safety Docket No s.: 50-266; 50-301 License No s.: DPR-24; DPR-27
Enclosure:
Inspection Report 05000 266/20 12 0 07(DRS); 05000301/201 2007(DRS) w/Attachment: Supplemental Information
REGION III Docket No s.: 50-266; 50-301 License No s.: DPR-24; DPR-27 Report No:
05000266/2012007(DRS); 05000301/2012007(DRS)
Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Unit s 1 and 2 Location: Two Rivers, WI Dates: April 16, 2012, through May 3, 201 2 Inspectors:
Alan Dahbur, Senior Reactor Inspector (Lead)
George Hausman , Senior Reactor Inspector Dariusz Szwarc
, Reactor Inspector Approved by:
Hironori Peterson , Acting Chief Engineering Branch 3 Division of Reactor Safety 1 Enclosure
SUMMARY OF FINDINGS
IR 05000266/201 2007(DRS), 05000301/2012007(DRS)
- 04/16/2012 - 05/03/2012; Point Beach Nuclear Plant, Units 1 and 2; Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications.
This report covers a two-week announced baseline inspection on evaluations of changes, tests, or experiments and permanent plant modifications. The inspection was conducted by Region III based engineering inspectors. Based on the results of this inspection, no findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG
-1649, "Reactor Oversight Process," Revision 4, dated December 2006. A.
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity
N RC-Identified and Self-Revealed Findings No significance f i n d i n g s were identified.
B. No violations of significance were identified.
=
Licensee-Identified Violations===
1. REACTOR SAFETY
REPORT DETAILS
Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity 1R17 Evaluation
s of Changes, Tests, or Experiments and Permanent Plant Modifications
.1
a. Evaluation of Changes, Tests, or Experiments From April 16, 2012, through May 3, 2012, the inspectors reviewed seven 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 NRC approval was obtained as appropriate. The inspectors also reviewed 1 6 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
Inspection Scope the changes, tests, or 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, or experiments were correct and consistent with 1 0 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 seven samples of evaluations a nd 1 6 samples of changes as defined in IP 71111.17-04. b. No findings of significance were identified.
Findings
.2 a. Permanent Plant Modifications
From April 16, 2012, through May 3, 2012, the inspectors reviewe d eight permanent plant modifications that had been installed in the plant during the last three years. Inspection Scope
3 Enclosure This review included in-plant walkdowns for portions of the emergency diesel generators G-01 and G-02 heat exchanger s replacement modification; the removal of boric acid heat trace equipment; the removal of racks RK
-52J and RK L and reroute of transformer 1X04 low voltage side power cables modification
. 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.
This inspection constitut ed eight permanent plant modification samples as defined in IP 71111.17-04. b. No findings of significance were identified.
Findings
OTHER ACTIVITIES
(OA)
4OA2
.1 Problem Identification and Resolution
a. Routine Review of Condition Reports From April 16, 2012, through May 3, 2012, the inspectors reviewe d various 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 evaluations of changes, tests, or experiments and permanent p lant modifications. 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.
Inspection Scope b. No findings of significance were identified.
Findings 4 Enclosure
4OA5 Power Uprate
.1
a. Evaluation of Changes, Tests, or Experiments (2 Samples) The inspectors reviewed safety evaluations for those implemented for the extended power uprate
.
Inspection Scope Safety Evaluation 2011
-003 , "Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
- Radiological Consequences
"; and Safety Evaluation 2011
-004 , "Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
- Ctmt Pressure a n d Temp." b. No findings of significance were identified.
Findings
4OA6
.1 Meetings On May 3, 2012, the inspectors presented the inspection results to
Mr. Meyer 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 reviewed during the inspection was returned to the licensee staff. Exit Meeting Summary ATTACHMENT:
SUPPLEMENTAL INFORMATION
Attachment
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTAC
T
- L. Meyer, Site Vice President
Licensee
- C. Trezise, Engineering Director
- P. Wild, Design Engineering Manager
- B. Woyak, Design Engineering Supervisor
- F. Hennessy, Excellence Manager
- B. Scherwinski, Licensing
- B. Hennessy, Licensing
- V. Kanal, Engineering Supervisor
- C. Ford, Maintenance Supervisor
- J. Niffenegger, Electrical Design Engineering
- S. Burton, Senior Resident Inspector
Nuclear Regulatory Commission
LIST OF ITEMS OPENED, CLOSED AND DISCUSS
ED None.Opened, Closed and Discussed
Attachment
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
2011-003 Date or Revision
Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
- Radiological Consequences
May 29, 2011 2011-00 4 Raise EOP Setpoint 0.2 (RWST Level to Stop Spray Pumps) to 17 percent
- Ctmt Pressure & Temp.
May 29, 2011 2009-009 EC 11682, Modifications for Flow Control to Prevent RHR Pump Excessive Flow with Containment Spray Aligned During the Recirculation Phase (Unit 1)
August 20, 2009
2010-003 EC 15413 "Control Room Alternate Cooling"
November 1, 2010
2009-014-02 Use of ECCS Suction Line Vent Valves Within Procedures 1
-TS-ECCS-002 Train A, 1
-TS-ECCS-002 Train B, 2
-TS-ECCS-002 Train A, 2
-TS-ECCS-002 Train B, OI
-128E and OI-129E June 10, 2010
2010-002 Reroute of 1X04 Low Voltage Power Cables to FAÇADE
November 10, 2010
2011-001 1A-01 and 1A-02 Loss of Voltage Relay Setpoint Changes
April 13, 2011
CFR 50.59 SCREENINGS
Number Description or Title
201 0-0 24 3 Date or Revision
NAMS E C 263219 Temporary Re location of the H
Supp l y (formerly
E C-16851) February 1, 2011 2011-0093 AST Related RWST EOP Setpoint
Changes May 28, 2011 2011-0332 Disable FS
-4909 & FS-4910 in Battery Rooms D
-105 & D-I06 December 13, 2011
2010-0169 Change Stated Capacity of Relief Valve RH
-861C From 990 GPM to 1106 GPM in FSAR 9.2 per USAR 1149992
August 4, 2010
2010-0152 Normal Ingress and Egress via HELB Barrier Doors
July 1, 2010
2011-0061 Development of New Limiting Value of Full Stroke Time for 1SC-959 April 9, 2011
2009-0186 Development of New Limiting Value of Full Stroke Time for 2RH-625 October 6, 2009
2008-0163-02 EC 11683 - Modifications for Flow Control to Prevent RHR Pump Excessive Flow with Containment Spray Aligned During the Recirculation Phase
April 29, 2010
2010-0170 Change to 2P
-10A RHR Pump IST Acceptance Criteria Based on Calculation 96
-0229 Revision
August 14, 2010 2010-0228 EC 14350 - Demolition of Boric Acid Heat Trace Circuitry
November 30, 2010
2010-0145-01 Temporary Cooling for Unit 1 and Unit 2 Steam Generator Feed Pump Motors 1(2)P
-028A-M and 1(2)P
-028B-M July 14, 2010
2009-0166 Install Test Switches for 4.16 KV Bus Loss of Voltage Relays
October 09, 2009
Attachment
CFR 50.59 SCREENINGS
Number Description or Title
2009-0196 Date or Revision
Temporary Power to B
-21 During 2B
-04 / 2B-03 Cross Tie Bus Inspection
October 23, 2009
2011-0085 1/2 SI-860A/C Acceptance Criteria for Stroke Time to Closed Position May 11, 2011
2010-0065 Revise the Pickup and Time Delay Tolerances for the 50D Protective Relays for 1(2) P
-15B Safety Injection Pumps in Calculation 2004
-009 and 1(2)RMP 9329
-2 June 15, 2010
2010-0133 USAR 1167033 Reverse USAR 1145362
June 15, 2010
CALCULATIONS
Number Description or Title
2000-0036 Date or Revision
ph of Post
-LOCA Sump and Containment Spray
May 19, 2011 2000-0036 ph of Post
-LOCA Sump and Containment Spray
May 28, 2011 2010-08891 Tube Freeze Calculation
December 29, 21 10 PBNP-IC-02 RWST Instrument Uncertainty/Setpoint Calculation, Section 8.1.66, Process Error
(PE) 4 WE-000 5-13 Evaluation of Heat Tracing for Appendix R Fire Protection Safe Shutdown
April 6, 1999 M-11165-112-RH.1 Relief Valve 1/2RH
-00861C Setpoint
and Capacity Determination
Revision 0
96-0229 Minimum Allowable IST Acceptance Criteria for RHR Pump Performance
Revision 3
CORRECTIVE ACTION PROGRAM DOCUMENTS ISSUED DURING INSPECTION
Number Description or Title
01762646 Date or Revision
2012 Mod/50.59 Inspection SCR 2010
-0243 Clarification
May 2, 2012 01762041 0-SOP-VNCR-100 Ladder Label
May 1, 2012
01759471 2012 Mod/50.59 Inspection Evaluation 2010
-002 Clarification
May 2, 2012
CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
Number Description or Title
01328399 Date or Revision
RWST Temp Found High OOS on Logs Temp Found at 105 Degrees by PAB Operator
September 18, 2007 01655745 AST FSAR Update Deficiencies
July 30, 2011 01657526 AST - FSAR Change Request for Final Modification Configuration
May 15, 2012 01687323 Request to Add Ventilation Cross Connect Hoses Used by 0
-SOP-VNCR-100 to the Monthly Inventory
September 17, 2011 01394223 Revision to Calculation 96
August 5, 2010
01378236 NRC Inspection: TS Bases 3.8.1 Not Supported by Calculation
December 4, 2009
01671481 Multiple Inadequate 50.59 Screenings for EPU Unit 2 Modifications
July 22, 2011
Attachment
CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
Number Description or Title
01382670 Date or Revision
AR 01162577 Documents that the 50.59 Used to Support USAR Change 01145362 was Fatally Flawed
February 22, 2010 DRAWINGS Number Description or Title
MCVK000062
Date or Revision
P&ID Chemical & Volume Control Point Beach NP Unit 1
Revision E
L-23944-4 Assembly and Details of 20'
-0" I.D. x 24' High Over Str Shell Condensate Storage Tanks
Revision 6
499B466 Sh.207 4160 Switchgear 2A01, Cub. 18 Bus Tie From 2A
-03 at 2A52-44 Revision 19
MODIFICATIONS
Number Description or Title
EC-263279 Date or Revision
Temporary Relocation of the H
Supply 0 EC 250861 G-01 and G-02 Emergency Diesel Generator Heat Exchanger Replacement (HX
-55A1/A2 and HX 55B1/B2)
June 27, 2007
EC 260778 Modification for Removal of Boric Acid Heat Trace Equipment and the Removal of Racks RK52
-J and RK52
-L for Access to Valves
Revision 0
EC 273685 Add Interposing Relays in the Starting Diesel Governor Pull-in Coil Circuit to Reduce Voltage Drop
September 2, 2011
-01 Fuel Oil Valve FO
-3930 PROCEDURES
Number Description or Title
0-SOP-VNBI-003 Date or Revision
White/Yellow Battery and Inverter Room Ventilation Normal Operation
ARB C01 B 1-9 PBNPP Alarm Response Procedure
- 1T13 RWST Low Level Alert
ARB C01 B 2-9 PBNPP Alarm Response Procedure
- 1T13 RWST Level
Low 5 ARB C01 B 3-9 PBNPP Alarm Response Procedure
- 1T13 RWST Level
Low-Low 5 REFERENCES
Number Description or Title
DG-I01 Date or Revision
Instrument Setpoint Methodology
Revision 6
Bulletin No.
L-151-B McDonnell No. AF1 Air Flow Switch for Duct Installations
1973
Attachment
WORK ORDERS(WOs) Number Description or Title
25352 Date or Revision
Need to Remove Debris from Bottom of [RWST] Tank
October 16, 1992 930474 In Support of U1R20, U1 RWST Mini
-SU March 26, 1993 9945054 1T-013 [RWST] Repair Weld
October 7, 2002 00267870 2T-013 [RWST] Inspect Tank Internals for Debris
October 30, 2006 00279479 1T-013 [RWST] Inspect Tank Internals for Debris
April 14, 2007 00380254 2T-013 [RWST] Inspect Tank Internals for Debris
March 19, 2011 00387773 1T-013 [RWST] Inspect Tank Internals for Debris
October 18, 2011
Attachment
LIST OF ACRONYMS USED ADAMS Agencywide Documents Access and Management System
ATTN Attention BOP Balance of Plant
CARD Condition Assessment Resolution Document
CCDP Conditional Core Damage Probability
CFR Code of Federal Regulations
DRP Division of Reactor Project
DRS Division of Reactor Safety
EC Engineering Change
EDG Emergency Diesel Generator
EOP Emergency Operating Procedure
EPU Extended Power Uprate
EQ Environmental Qualification
FS Flow Switch
GPM Gallons Per Minute
HX Heat Exchanger
IMC Inspection Manual Chapter
IN Information Notice
IP Inspection Procedure
IR Inspection Report
NCV Non-Cited Violation
NEI Nuclear Energy Institute
NGR Neutral Grounding Resistor
NRC U.S. Nuclear Regulatory Commission
NSR Non-Safety-Related NUREG NRC Technical Report Designation
OLNC On-Line NobleChem
TM OOS Out-of-Service OPR Operability Recommendation
PARS Public Available Records System
PBNPP Point Beach Nuclear Power Plant
RWST Refueling Water Storage Tank
SP Surveillance Procedure
TS Technical Specification
USAR Updated Safety Analysis Report
WO Work Order
Mr. Larry Meyer
Senior 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, OR EXPERIMENTS ANDPERMANENT PLANT MODIFICATIONS BASELINE INSPECTION REPORT 05000266/2012007(DRS); 05000301/2012007 (DRS) Dear Mr. Meyer:
On May 3, 2012, the
- U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Inspection at your Point Beach Nuclear Plant. The
enclosed inspection report documents the inspection results which were discussed on May 3, 2012, 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.
Based on the results of this inspection, no findings of significance were identified
. In accordance with Title 10, Code of Federal Regulations
(CFR), Part
50, Section
2.390 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 Public Document Room or from the Publicly Available Records System (PARS)
component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading
-rm/adams.html
(the Public Electronic Reading Room).
Sincerely, /RA/ Hironori Peterson, Acting Chief
Engineering Branch
Division of Reactor Safety
Docket Nos.: 50
-266; 50-301 License Nos.: DPR-24; DPR-27 Enclosure:
Inspection Report 05000266/2012007(DRS); 05000301/2012007(DRS) w/Attachment: Supplemental Information
cc w/encl:
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