IR 05000266/2019410: Difference between revisions
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| issue date = 04/16/2019 | | issue date = 04/16/2019 | ||
| title = NRC Security Baseline Inspection Report 05000266/2019410; 05000301/2019410 (DRS-N.Egan) | | title = NRC Security Baseline Inspection Report 05000266/2019410; 05000301/2019410 (DRS-N.Egan) | ||
| author name = Orth S | | author name = Orth S | ||
| author affiliation = NRC/RGN-III/DRS/PSB | | author affiliation = NRC/RGN-III/DRS/PSB | ||
| addressee name = Craven R | | addressee name = Craven R | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:ril 16, 2019 | ||
==SUBJECT:== | |||
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC SECURITY BASELINE INSPECTION REPORT 05000266/2019410; 05000301/2019410 | |||
SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND | |||
==Dear Mr. Craven:== | ==Dear Mr. Craven:== | ||
On March 14, 2019 | On March 14, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2 and discussed the results of this inspection with M. Wilcox and other members of your staff. The results of this inspection are documented in the enclosed report. | ||
, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2 and discussed the results of this inspection with M. Wilcox and other members of your staff. | |||
The NRC inspector did not identify any finding or violation of more-than-minor significance. | |||
-than-minor significance. | |||
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading | This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding. | ||
-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, | |||
If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information-Withhold from public disclosure under Title 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). | |||
-Related Information, please mark your entire response | |||
-Related Information | |||
-Withhold from public disclosure under Title 10 CFR 2.390 | |||
Sincerely, | Sincerely, | ||
/RA/ Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket | /RA/ | ||
-27 | Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos.: 05000266 and 05000301 License Nos.: DPR-24 and DPR-27 | ||
===Enclosure:=== | |||
IR 05000266/2019410; 05000301/2019410 | |||
==Inspection Report== | ==Inspection Report== | ||
Docket Numbers: | Docket Numbers: 05000266 and 05000301 License Numbers: DPR-24 and DPR-27 Report Numbers: 05000266/2019410 and 05000301/2019410 Enterprise Identifier: I-2019-410-0042 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI 54241 Inspection Dates: March 4, 2019, to March 7, 2019 Inspector: N. Egan, Sr. Physical Security Inspector Approved By: Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Enclosure | ||
05000266 and 05000301 License Numbers: | |||
DPR-24 and DPR | |||
-27 Report Numbers: | |||
05000266/2019410 and 05000301/2019410 Enterprise Identifier: | |||
I-2019-410-0042 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI 54241 Inspection Dates: | |||
March 4, 2019 , to March 7, 2019 Inspector: | |||
N. Egan, Sr. Physical Security Inspector Approved By: | |||
Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety | |||
=SUMMARY= | =SUMMARY= | ||
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the | The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Security Baseline inspection at Point Beach Nuclear Plant, Units 1 and 2 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Findings and violations being considered in the NRCs assessment are summarized in the table below. | ||
Findings and violations being considered in the | |||
List of Findings and Violations No findings were identified. | List of Findings and Violations No findings were identified. | ||
Additional Tracking Items None. | Additional Tracking Items None. | ||
=INSPECTION SCOPES= | =INSPECTION SCOPES= | ||
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading | Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. | ||
-rm/doc-collections/insp | |||
-manual/inspection | |||
-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, | |||
-Water Reactor Inspection Program - Operations Phase. | |||
==SAFEGUARDS== | ==SAFEGUARDS== | ||
==71130.02 - Access Control | ==71130.02 - Access Control The inspector evaluated the security access control program. The following elements were evaluated from this IP: | ||
Access Control== | |||
The inspector evaluated the security access control program. | {{IP sample|IP=IP 71130.02|count=1}} | ||
* Tier I: All | |||
The following elements were evaluated from this IP: | * Tier II: 02.06 a-d, 02.08 a-d | ||
Access Control | * Tier III: 02.10 a | ||
-d | |||
==INSPECTION RESULTS== | ==INSPECTION RESULTS== | ||
Line 96: | Line 67: | ||
==EXIT MEETINGS AND DEBRIEFS== | ==EXIT MEETINGS AND DEBRIEFS== | ||
The inspector verified no proprietary information was retained or documented in this report. | The inspector verified no proprietary information was retained or documented in this report. | ||
* On March 14, 2019, the inspector presented the Security Baseline inspection results to M. Wilcox and other members of the licensee staff. | |||
=DOCUMENTS REVIEWED= | |||
SY-AA-102-1022; Vehicle and Material Searches; Revision 10 | |||
SY-AA-102-1022; Vehicle and Material Searches; Revision | SY-AA-102-1016; Control of Security Sensitive Equipment; Revision 7 | ||
SY-AA-102- | |||
PBSAP 1.3.2; Vehicle Processing; Revision 36 | PBSAP 1.3.2; Vehicle Processing; Revision 36 | ||
PBSAP 1.3.4; Personnel Searches; Revision 20 | PBSAP 1.3.4; Personnel Searches; Revision 20 | ||
PBSAP 1.8; Security Emergency Response; | PBSAP 1.8; Security Emergency Response; Revision 22 | ||
Revision 22 | |||
PBSAP 1.3.2; Vehicle Processing; Revision 36 | PBSAP 1.3.2; Vehicle Processing; Revision 36 | ||
3 | |||
}} | }} |
Latest revision as of 08:51, 15 November 2019
ML19106A195 | |
Person / Time | |
---|---|
Site: | Point Beach |
Issue date: | 04/16/2019 |
From: | Steven Orth Plant Support Branch II |
To: | Craven R Point Beach |
References | |
IR 2019410 | |
Download: ML19106A195 (5) | |
Text
ril 16, 2019
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2NRC SECURITY BASELINE INSPECTION REPORT 05000266/2019410; 05000301/2019410
Dear Mr. Craven:
On March 14, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Point Beach Nuclear Plant, Units 1 and 2 and discussed the results of this inspection with M. Wilcox and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspector did not identify any finding or violation of more-than-minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information-Withhold from public disclosure under Title 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1).
Sincerely,
/RA/
Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Docket Nos.: 05000266 and 05000301 License Nos.: DPR-24 and DPR-27
Enclosure:
IR 05000266/2019410; 05000301/2019410
Inspection Report
Docket Numbers: 05000266 and 05000301 License Numbers: DPR-24 and DPR-27 Report Numbers: 05000266/2019410 and 05000301/2019410 Enterprise Identifier: I-2019-410-0042 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI 54241 Inspection Dates: March 4, 2019, to March 7, 2019 Inspector: N. Egan, Sr. Physical Security Inspector Approved By: Steven K. Orth, Chief Plant Support Branch Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Security Baseline inspection at Point Beach Nuclear Plant, Units 1 and 2 in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations No findings were identified.
Additional Tracking Items None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs)in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
SAFEGUARDS
==71130.02 - Access Control The inspector evaluated the security access control program. The following elements were evaluated from this IP:
Access Control==
- Tier I: All
- Tier II: 02.06 a-d, 02.08 a-d
- Tier III: 02.10 a
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspector verified no proprietary information was retained or documented in this report.
- On March 14, 2019, the inspector presented the Security Baseline inspection results to M. Wilcox and other members of the licensee staff.
DOCUMENTS REVIEWED
SY-AA-102-1022; Vehicle and Material Searches; Revision 10
SY-AA-102-1016; Control of Security Sensitive Equipment; Revision 7
PBSAP 1.3.2; Vehicle Processing; Revision 36
PBSAP 1.3.4; Personnel Searches; Revision 20
PBSAP 1.8; Security Emergency Response; Revision 22
PBSAP 1.3.2; Vehicle Processing; Revision 36
3