IR 05000266/2015003

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IR 05000266/2015003, 05000301/2015003; on 07/01/2015 - 09/30/2015; Point Beach Nuclear Plant, Units 1 & 2; Operability Determinations and Functionality Assessments and Follow-Up of Events and Notices of Enforcement Discretion
ML15302A428
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 10/29/2015
From: Jamnes Cameron
Reactor Projects Region 3 Branch 4
To: Mccartney E
Point Beach
References
IR 2015003
Download: ML15302A428 (67)


Text

UNITED STATES ber 29, 2015

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - NRC INTEGRATED INSPECTION REPORT 05000266/2015003; 05000301/2015003

Dear Mr. McCartney:

On September 30, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2. The enclosed report documents the results of this inspection, which were discussed on October 14, 2015, with you and other members of your staff.

Based on the results of this inspection, three NRC-identified findings of very low safety significance were identified. Two of the findings involved violations of NRC requirements.

Additionally, one licensee-identified violation is listed in Section 4OA7. However, because of their very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating the issues as non-cited violations (NCVs) in accordance with Section 2.3.2 of the NRC Enforcement Policy.

If you contest the subject or severity of these NCVs, 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, U.S. Nuclear Regulatory Commission, 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 addition, if you disagree with the cross-cutting aspect assigned to any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region III, 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 NRCs 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 John Rutkowski Acting for/

Jamnes Cameron, Chief Branch 4 Division of Reactor Projects Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27

Enclosure:

IR 05000266/2015003; 05000301/2015003 w/Attachment: Supplemental Information

REGION III==

Docket Nos: 05000266; 05000301 License Nos: DPR-24; DPR-27 Report No: 05000266/2015003; 05000301/2015003 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Dates: July 1, 2015 through September 30, 2015 Inspectors: D. Oliver, Senior Resident Inspector K. Barclay, Resident Inspector E. Coffman, Acting Senior Resident Inspector J. Mancuso, Acting Resident Inspector R. Baker, Operations Engineer B. Bartlett, Project Engineer V. Myers, Senior Health Physicist B. Palagi, Senior Operations Engineer J. Rutkowski, Project Engineer Approved by: J. Cameron, Chief Branch 4 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

......................................................................................................... 4

REPORT DETAILS

............................................................................................................... 7

Summary of Plant Status

REACTOR SAFETY

.................................................................................................. 7

1R01 Adverse Weather Protection

........................................................... 7

1R04 Equipment Alignment

...................................................................... 8

1R05 Fire Protection

................................................................................ 9

1R06 Flooding

........................................................................................10

1R07 Annual Heat Sink Performance

......................................................11

1R11 Licensed Operator Requalification Program

..................................11

1R12 Maintenance Effectiveness

............................................................15

1R13 Maintenance Risk Assessments and Emergent Work Control

.......16

1R15 Operability Determinations and Functional Assessments

..............16

1R19 Post-Maintenance Testing

.............................................................19

1R22 Surveillance Testing

......................................................................19

1EP6 Drill Evaluation

RADIATION SAFETY

...............................................................................................21

2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling,

Storage, and Transportation (71124.08)

OTHER ACTIVITIES

.................................................................................................25

4OA1 Performance Indicator Verification

......................................................25

4OA2 Identification and Resolution of Problems

...........................................27

4OA3 Follow-Up of Events and Notices of Enforcement Discretion

..............29

4OA5 Other Activities.......................................................................................................42

4OA6 Management Meetings ....................................................................................42

4OA7 Licensee-Identified Violations ..........................................................................43

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

E. McCartney, Site Vice President
D. DeBoer, Plant General Manager
S. Aerts, Performance Improvement Manager
R. Amundson, Training Operations Supervisor
R. Baird, Training Fleet Manager
L. Christensen, Project Manager
A. Cookle, Senior Security Analyst
C. Ford, Maintenance Support Department Head
D. Forter, Project Site Manager
A. Gustafson, Training Ops General Supervisor
R. Harrsch, Engineering Site Director
M. Millen, Senior Project Manager
T. Ouret, Training Fleet Manager
R. Parker, Chemistry Manager
T. Schneider, Senior Engineer
E. Schultz, Operations Assistant Manager Line
G. Strharsky, Site Quality Manager
M. Vana, Senior Training Ops Instructor
R. Webber, Operations Site Director
R. Welty, Radiation Protection Manager
M. Wilcox, On Line Manager
P. Wild, Design Engineering Manager
B. Woyak, Licensing Manager

Nuclear Regulatory Commission

J. Cameron, Chief, Reactor Projects Branch 4

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

05000266/2015003-01 FIN Incomplete Functionality Assessment for Flooding in the
05000301/2015003-01 Diesel Generator Building (Section 1R15.1)
05000266/2015003-02 NCV Potential Failure of Multiple Safety-Related Trains During
05000301/2015003-02 Flooding Events (Section 4OA3.1)
05000266/2015003-03 SLIV Failure to Perform a Written Safety Evaluation for FSAR
05000301/2015003-03 NCV Changes (Section 4OA3.1)

Closed

05000266/2015003-01 FIN Incomplete Functionality Assessment for Flooding in the
05000301/2015003-01 Diesel Generator Building (Section 1R15.1)
05000266/2015001-00 LER Inadequately Sealed Pipe Penetration Results in an Unanalyzed Condition for Internal Flooding (Section 4OA3.1)
05000266/2015003-00 LER D-107 Battery Charger Failure to Limit Current Results in Operation or Condition Prohibited by Technical Specifications (Section 4OA3.2)
05000266/2015003-01 LER D-107 Battery Charger Failure to Limit Current Results in Operation or Condition Prohibited by Technical Specifications (Section 4OA3.2)
05000266/2015004-00 LER Out-of-Service A-06 Switchgear Room Fans Result in Operation Prohibited by Technical Specifications (Section 4OA3.3)
05000266/2015003-02 NCV Potential Failure of Multiple Safety-Related Trains During
05000301/2015003-02 Flooding Events (Section 4OA3.1)
05000266/2015003-03 SLIV Failure to Perform a Written Safety Evaluation for FSAR
05000301/2015003-03 NCV Changes (Section 4OA3.1)

2515/190 TI Inspection of the Proposed Interim Actions Associated with Near-Term Task Force Recommendation 2.1 Flooding Hazard Evaluations (Section 4OA5.1)

LIST OF DOCUMENTS REVIEWED