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=Text=
=Text=
{{#Wiki_filter:August 27, 2019 Mr. Scott Sharp Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company, Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  
{{#Wiki_filter:ust 27, 2019
- TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000282/2019012 AND 05000306/2019012
 
==SUBJECT:==
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000282/2019012 AND 05000306/2019012


==Dear Mr. Sharp:==
==Dear Mr. Sharp:==
On July 25, 2019
On July 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and discussed the results of this inspection with Ms. Dominique Wilson, Director of Site Performance Operation Support, 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 Prairie Island Nuclear Generating Plant and discussed the results of this inspection with Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of your staff.
 
The NRC inspectors did not identify any finding or violation of more than minor significance.


The results of this inspection are documented in the enclosed report. The NRC inspectors 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.
. 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
."


Sincerely,
Sincerely,
/RA/ Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No s. 05000282 and 05000306 License No s. DPR-42 and DPR-60  
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60


===Enclosure:===
===Enclosure:===
As stated  
As stated


==Inspection Report==
==Inspection Report==
Docket Number s: 05000282 and 05000306 License Numbers:
Docket Numbers: 05000282 and 05000306 License Numbers: DPR-42 and DPR-60 Report Numbers: 05000282/2019012 and 05000306/2019012 Enterprise Identifier: I-2019-012-0020 Licensee: Xcel Energy Facility: Prairie Island Nuclear Generating Plant Location: Welch, Minnesota Inspection Dates: June 24, 2019 to July 25, 2019 Inspectors: A. Dahbur, Senior Reactor Inspector M. Domke, Reactor Inspector D. Szwarc, Senior Reactor Inspector Approved By: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
DPR-42 and DPR-60 Report Numbers:
05000282/2019012 and 05000306/2019012 Enterprise Identifier:
I-2019-012-0020 Licensee: Xcel Energy Facility: Prairie Island Nuclear Generating Plant Location: Welch, Minnesota Inspection Dates:
June 24, 2019 to July 25, 2019 Inspectors:
A. Dahbur, Senior Reactor Inspector M. Domke, Reactor Inspector D. Szwarc, Senior Reactor Inspector Approved By:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety


2
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at Prairie Island Nuclear Generating Plant 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.


=SUMMARY=
List of Findings and Violations No findings or violations of more than minor significance were identified.
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting a triennial fire protection inspection at Prairie Island Nuclear Generating Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information
. List of Findings and Violations No findings or violations of more than minor significance were identified.


Additional Tracking Items None.
Additional Tracking Items None.
3


=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 inspectors 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, "Light
-Water Reactor Inspection Program - Operations Phase."  The inspectors 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.


==REACTOR SAFETY==
==REACTOR SAFETY==
71111.05XT  
 
- Fire Protection  
===71111.05XT - Fire Protection - NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a) ===
- NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a)
{{IP sample|IP=IP 71111.05|count=3}}
(3 Sample s)  The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:
The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:
: (1) 18 Unit 2 Relay and Cable Spreading Room;
: (1) 18 Unit 2 Relay and Cable Spreading Room;
: (2) 32 "B" Train Hot Shutdown Panel; and
: (2) 32 "B" Train Hot Shutdown Panel; and
Line 72: Line 61:


Analyzed Circuits:
Analyzed Circuits:
CV-31084, Steam Generator Power Operated Relief Valve; and X-HIAW 48-22, 12 Diesel Cooling Water Pump.
* CV-31084, Steam Generator Power Operated Relief Valve; and
* X-HIAW 48-22, 12 Diesel Cooling Water Pump.


B.5.b Inspection Activities (IP Section 02.03)
B.5.b Inspection Activities (IP Section 02.03) (2 Samples)===
(2 Sample s) The inspectors evaluated the following B.5.b Mitigating Strategies:
The inspectors evaluated the following B.5.b Mitigating Strategies:
: (1) Attachment H  
: (1) Attachment H - Containment Flooding; and
- Containment Flooding; and
: (2) Attachment K - Recovery of D1/D2 Cooling.
: (2) Attachment K  
- Recovery of D1/D2 Cooling.


==INSPECTION RESULTS==
==INSPECTION RESULTS==
Line 86: Line 74:
==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
The inspectors verified no proprietary information was retained or documented in this report.
 
* On July 25, 2019, the inspectors presented the triennial fire protection inspection results to Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of the licensee staff.
On July 25, 2019, the inspector s presented the triennial fire protection inspection results to Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of the licensee staff.


=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


Inspection Procedure Type Designation
Inspection Type             Designation   Description or Title                                         Revision or
Description or Title
Procedure                                                                                                Date
Revision or Date 71111.05XT
71111.05XT Calculations     P2117-2400-03- Calculation for NFPA 805 Safe Shutdown Analysis - Decay     0
Calculations
Heat Removal
P2117-2400-03-00 Calculation for NFPA 805 Safe Shutdown Analysis  
Corrective Action 01515933       Missing Fire Barrier Between FA 15 And FA 59                 03/16/2016
- Decay Heat Removal
Documents        1536541       Unacceptable Thinning Found During Planned MIC               10/03/2016
Corrective Action Documents  01515933 Missing Fire Barrier Between FA 15 And FA 59
Inspection
03/16/2016
500001538543   Issues While Performing SP 1197                             10/19/2016
1536541 Unacceptable Thinning Found During Planned MIC Inspection
501000016344   Sprinkler Heads Need Cleaning                               08/30/2018
10/03/2016
501000016839   PENF 19 Concrete Needs Repair                               09/13/2018
500001538543
501000020789   NOS ID: Seal Inspection Justification                       12/07/2018
Issues While Performing SP 1197
501000028647   B5b Cell Phones Not Tested                                   06/18/2019
10/19/2016
Corrective Action 501000028783   CAP Closed to Lower Severity Level CAP                       06/20/2019
501000016344
Documents        501000028976   EDMG Cell Phones                                             06/26/2019
Sprinkler Heads Need Cleaning
Resulting from    501000029050   EDMG-1 And PINGP 1385 Not At Gate House                     06/27/2019
08/30/2018
Inspection        501000029210   B.5.b Enhancement                                           06/28/2019
501000016839
501000029213   Duplicate Calculations Issued                               07/02/2019
PENF 19 Concrete Needs Repair
501000029319   Incorrect Reference In Engineering Change                   07/08/2019
09/13/2018
501000029377   F5 Appendix D Unit 1/Unit 2 Error                           07/0/2019
501000020789
501000029377   F5 Appendix D U1/U2 Error                                   07/09/2019
NOS ID: Seal Inspection Justification
501000029388   PRA Notebook Editorial Error                                 07/10/2019
2/07/2018
501000029467   Error in Compensatory Measure Evaluation                     07/12/2019
501000028647
501000029680   Fire PRA Model Credit For Incipient Detectors               07/17/2019
B5b Cell Phones Not Tested
Drawings         97FP02-2       (97FP02) AFW Pump Room Fire Protection Piping System         0
06/18/2019
WPS-10
Corrective Action Documents Resulting from Inspection
NE-40009 Sheet 12 Diesel Cooling Water Pump                                 78
501000028783
NE-40009 Sheet 12 Diesel Cooling Water Pump                                 77
CAP Closed to Lower Severity Level CAP
NF-40022-1     Circuit Diagram - 4KV And 480 Safeguard Buses Unit 1         81
06/20/2019
NF-40322-3     Logic Diagram - Main Steam System Unit 1                     76
501000028976
Engineering       21572         NFPA 805 - PINGP Station Fire Damper -NFPA 805               02/12/2015
EDMG Cell Phones
Changes                          Transition Activity -LAR L-PI-12-089, Attachment S, Table S-
06/26/2019
Inspection Type         Designation     Description or Title                                       Revision or
501000029050
Procedure                                                                                            Date
EDMG-1 And PINGP 1385 Not At Gate House
2, Item 16
06/27/2019
23914           NFPA 805 - Incipient Detection Project, LAR L-PI-14-045,   1
501000029210
Table S-2, Item 5, 8
B.5.b Enhancement
EC 25100       NFPA 805 - Unit 1 And 2 Auxiliary Feedwater Pump Room       12/02/2016
06/28/2019
Separation
501000029213
EC 25124       NFPA 805 12 And 22 DDCLP Modification                       0
Duplicate Calculations Issued
Engineering   FPCE 18-008     Change Evaluation For H77.3                                 07/19/2018
07/02/2019
Evaluations  FPCE 18-010     Camera To Monitor 22 RCP Motor Lower Oil Reservoir Level   0
501000029319
FPCE 18-013     Clearance Order For Pinhole Leak On Pipe 6-FP-18           2
Incorrect Reference In Engineering Change
FPEE 12-010     Access Control (FA15) To Auxiliary Building Mezzanine Level 1
07/08/2019
Unit 1 (FA59)
501000029377
FPEE-12-006     Fire Area 85 Boundaries And F5 Appendix K Barriers         3
F5 Appendix D Unit 1/Unit 2 Error
FPEE-14-003     Explosion Analysis For Compressed Gas Cylinders             12/18/2014
07/0/2019 501000029377
FPEE-17-002     NFPA 805 LAR S-2 Compensatory Measures                     0
F5 Appendix D U1/U2 Error
FPRA-PI-CF     Circuit Failure Mode Likelihood Analysis Notebook           04/13/2018
07/09/2019
FPRA-PI-MCA     Multi-Compartment Analysis Notebook                         04/13/2018
501000029388
FPRA-PI-MSO     Fire Multiple Spurious Operation Notebook                   04/13/2019
PRA Notebook Editorial Error
FPRA-PI-RRA     Relay Room Analysis Notebook                               5.3
07/10/2019
V.SMN.15.007   Relay Room Incipient Detection Modification Sensitivity     03/10/2015
501000029467
Miscellaneous FL-BSE-100-003L Introduction to Nuclear Security                           0
Error in Compensatory Measure Evaluation
PINGP 1385     Emergency Response Organization Activation                 19
07/12/2019
V.SMN.19.006   PINGP [Prairie Island Nuclear Generating Plant] NFPA       0
501000029680
                                        [National Fire Protection Association] 805 Monitoring
Fire PRA Model Credit For Incipient Detectors
Program Risk Target Values
07/17/2019
Operability   F5 APP B       Control Room Evacuation (Fire)                             65
Drawings 97FP02-2 (97FP02) AFW Pump Room Fire Protection Piping System WPS-10 0 NE-40009 Sheet
Evaluations
12 Diesel Cooling Water Pump
Procedures   EDMG-2         Guideline for Damage Mitigation Strategies                 12
NE-40009 Sheet
F5 Appendix A   Detection Zones and Fire Areas                             41
12 Diesel Cooling Water Pump
F5 APPENDIX D   Impact of Fire Outside Control/Relay Room                   42
NF-40022-1 Circuit Diagram  
F5 Appendix D   Impact of Fire Outside Control/Relay Room                   41
- 4KV And 480 Safeguard Buses Unit 1
F5 Appendix F   Fire Hazards Analysis                                       36
NF-40322-3 Logic Diagram  
F5 Appendix K   Fire Protection Systems Functional Requirements             29
- Main Steam System Unit 1
FP-PE-PRA-02   PRA Guideline for Model Maintenance and Update             16
Engineering Changes  21572 NFPA 805 - PINGP Station Fire Damper  
Inspection Type       Designation Description or Title                                     Revision or
-NFPA 805 Transition Activity  
Procedure                                                                                    Date
-LAR L-PI-12-089, Attachment S, Table S
H77         Fire Protection Program                                   2
-02/12/2015
H77.1       Fire Protection Program NFPA 805 Chapter 3 Compliance     2
 
Summary (NEI 04-02 Table B-1)
Inspection Procedure Type Designation
H77.2       Fire Protection Program NSCA Methodology Compliance       0
Description or Title
                                  (NEI 04-02 Table B-2)
Revision or Date 2, Item 16
H77.3       Fire Area Assessments                                    0
23914 NFPA 805 - Incipient Detection Project, LAR L
Work Orders 700010880   SP 1192 Safeguards Electrical And Mechanical Penetrations 10/15/2018
-PI-14-045, Table S-2, Item 5, 8
Surveillance Inspection
EC 25100 NFPA 805 - Unit 1 And 2 Auxiliary Feedwater Pump Room Separation
700025089   SP 1197 Annual Header/Drains Flush Fire Protection System 06/18/2018
2/02/2016
700028970   SP 1275 18 Month Safe Shutdown Fire Barrier Inspection   08/01/2018
EC 25124 NFPA 805 12 And 22 DDCLP Modification
700030214   SP 1196 Fire Protection Safety Related Sprinkler System   08/30/2018
Engineering Evaluations
Test
FPCE 18-008 Change Evaluation For H77.3
700032679   TP 1423 Portable Diesel Fire Pump Test                   09/17/2018
07/19/2018
700041404   SP 1197 Annual Header/Drains Flush Fire Protection System 07/13/2018
FPCE 18-010 Camera To Monitor 22 RCP Motor Lower Oil Reservoir Level
6
FPCE 18-013 Clearance Order For Pinhole Leak On Pipe 6
-FP-18 2 FPEE 12-010 Access Control (FA15) To Auxiliary Building Mezzanine Level Unit 1 (FA59)
FPEE-12-006 Fire Area 85 Boundaries And F5 Appendix K Barriers
FPEE-14-003 Explosion Analysis For Compressed Gas Cylinders
2/18/2014
FPEE-17-002 NFPA 805 LAR S
-2 Compensatory Measures 0 FPRA-PI-CF Circuit Failure Mode Likelihood Analysis Notebook
04/13/2018
FPRA-PI-MCA Multi-Compartment Analysis Notebook
04/13/2018
FPRA-PI-MSO Fire Multiple Spurious Operation Notebook
04/13/2019
FPRA-PI-RRA Relay Room Analysis Notebook
5.3 V.SMN.15.007
Relay Room Incipient Detection Modification Sensitivity
03/10/2015
Miscellaneous
FL-BSE-100-003L Introduction to Nuclear Security
PINGP 1385
Emergency Response Organization Activation
V.SMN.19.006
PINGP [Prairie Island Nuclear Generating Plant] NFPA [National Fire Protection Association] 805 Monitoring Program Risk Target Values
Operability Evaluations
F5 APP B Control Room Evacuation (Fire)
Procedures
EDMG-2 Guideline for Damage Mitigation Strategies
F5 Appendix A
Detection Zones and Fire Areas
F5 APPENDIX D
Impact of Fire Outside Control/Relay Room
F5 Appendix D
Impact of Fire Outside Control/Relay Room
F5 Appendix F
Fire Hazards Analysis
F5 Appendix K
Fire Protection Systems Functional Requirements
FP-PE-PRA-02 PRA Guideline for Model Maintenance and Update
Inspection Procedure Type Designation
Description or Title
Revision or Date H77 Fire Protection Program
H77.1 Fire Protection Program NFPA 805 Chapter 3 Compliance Summary (NEI 04
-02 Table B
-1) 2 H77.2 Fire Protection Program NSCA Methodology Compliance (NEI 04-02 Table B
-2) 0 H77.3 Fire Area Assessmen
ts 0 Work Orders
700010880 SP 1192 Safeguards Electrical And Mechanical Penetrations Surveillance Inspection
10/15/2018
700025089 SP 1197 Annual Header/Drains Flush Fire Protection System
06/18/2018
700028970 SP 1275 18 Month Safe Shutdown Fire Barrier Inspection
08/01/2018
700030214 SP 1196 Fire Protection Safety Related Sprinkler System Test 08/30/2018
700032679 TP 1423 Portable Diesel Fire Pump Test
09/17/2018
700041404 SP 1197 Annual Header/Drains Flush Fire Protection System
07/13/2018
}}
}}

Revision as of 23:56, 7 October 2019

Triennial Fire Protection Inspection Report 05000282/2019012 and 05000306/2019012 (DRS-A.Dahbur)
ML19239A415
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/27/2019
From: Robert Daley
Engineering Branch 3
To: Sharp S
Northern States Power Company, Minnesota
References
IR 2019012
Download: ML19239A415 (8)
v • d • e


Text

ust 27, 2019

SUBJECT:

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000282/2019012 AND 05000306/2019012

Dear Mr. Sharp:

On July 25, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Prairie Island Nuclear Generating Plant and discussed the results of this inspection with Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC inspectors 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.

Sincerely,

/RA/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 05000282 and 05000306 License Nos. DPR-42 and DPR-60

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000282 and 05000306 License Numbers: DPR-42 and DPR-60 Report Numbers: 05000282/2019012 and 05000306/2019012 Enterprise Identifier: I-2019-012-0020 Licensee: Xcel Energy Facility: Prairie Island Nuclear Generating Plant Location: Welch, Minnesota Inspection Dates: June 24, 2019 to July 25, 2019 Inspectors: A. Dahbur, Senior Reactor Inspector M. Domke, Reactor Inspector D. Szwarc, Senior Reactor Inspector Approved By: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection inspection at Prairie Island Nuclear Generating Plant 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.

List of Findings and Violations No findings or violations of more than minor significance 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 inspectors 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.

REACTOR SAFETY

71111.05XT - Fire Protection - NFPA 805 Fire Protection Inspection Requirements (IP Section 02.01a)

Main article: IP 71111.05

The inspectors evaluated fire protection program implementation in the following selected areas and/or fire zones, including analyzed electrical circuits:

(1) 18 Unit 2 Relay and Cable Spreading Room;
(2) 32 "B" Train Hot Shutdown Panel; and
(3) 59 Auxiliary Building Mezzanine Level.

Analyzed Circuits:

  • X-HIAW 48-22, 12 Diesel Cooling Water Pump.

B.5.b Inspection Activities (IP Section 02.03) (2 Samples)===

The inspectors evaluated the following B.5.b Mitigating Strategies:

(1) Attachment H - Containment Flooding; and
(2) Attachment K - Recovery of D1/D2 Cooling.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On July 25, 2019, the inspectors presented the triennial fire protection inspection results to Ms. Dominique Wilson, Director of Site Performance Operation Support, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.05XT Calculations P2117-2400-03- Calculation for NFPA 805 Safe Shutdown Analysis - Decay 0

Heat Removal

Corrective Action 01515933 Missing Fire Barrier Between FA 15 And FA 59 03/16/2016

Documents 1536541 Unacceptable Thinning Found During Planned MIC 10/03/2016

Inspection

500001538543 Issues While Performing SP 1197 10/19/2016

501000016344 Sprinkler Heads Need Cleaning 08/30/2018

501000016839 PENF 19 Concrete Needs Repair 09/13/2018

501000020789 NOS ID: Seal Inspection Justification 12/07/2018

501000028647 B5b Cell Phones Not Tested 06/18/2019

Corrective Action 501000028783 CAP Closed to Lower Severity Level CAP 06/20/2019

Documents 501000028976 EDMG Cell Phones 06/26/2019

Resulting from 501000029050 EDMG-1 And PINGP 1385 Not At Gate House 06/27/2019

Inspection 501000029210 B.5.b Enhancement 06/28/2019

501000029213 Duplicate Calculations Issued 07/02/2019

501000029319 Incorrect Reference In Engineering Change 07/08/2019

501000029377 F5 Appendix D Unit 1/Unit 2 Error 07/0/2019

501000029377 F5 Appendix D U1/U2 Error 07/09/2019

501000029388 PRA Notebook Editorial Error 07/10/2019

501000029467 Error in Compensatory Measure Evaluation 07/12/2019

501000029680 Fire PRA Model Credit For Incipient Detectors 07/17/2019

Drawings 97FP02-2 (97FP02) AFW Pump Room Fire Protection Piping System 0

WPS-10

NE-40009 Sheet 12 Diesel Cooling Water Pump 78

NE-40009 Sheet 12 Diesel Cooling Water Pump 77

NF-40022-1 Circuit Diagram - 4KV And 480 Safeguard Buses Unit 1 81

NF-40322-3 Logic Diagram - Main Steam System Unit 1 76

Engineering 21572 NFPA 805 - PINGP Station Fire Damper -NFPA 805 02/12/2015

Changes Transition Activity -LAR L-PI-12-089, Attachment S, Table S-

Inspection Type Designation Description or Title Revision or

Procedure Date

2, Item 16

23914 NFPA 805 - Incipient Detection Project, LAR L-PI-14-045, 1

Table S-2, Item 5, 8

EC 25100 NFPA 805 - Unit 1 And 2 Auxiliary Feedwater Pump Room 12/02/2016

Separation

EC 25124 NFPA 805 12 And 22 DDCLP Modification 0

Engineering FPCE 18-008 Change Evaluation For H77.3 07/19/2018

Evaluations FPCE 18-010 Camera To Monitor 22 RCP Motor Lower Oil Reservoir Level 0

FPCE 18-013 Clearance Order For Pinhole Leak On Pipe 6-FP-18 2

FPEE 12-010 Access Control (FA15) To Auxiliary Building Mezzanine Level 1

Unit 1 (FA59)

FPEE-12-006 Fire Area 85 Boundaries And F5 Appendix K Barriers 3

FPEE-14-003 Explosion Analysis For Compressed Gas Cylinders 12/18/2014

FPEE-17-002 NFPA 805 LAR S-2 Compensatory Measures 0

FPRA-PI-CF Circuit Failure Mode Likelihood Analysis Notebook 04/13/2018

FPRA-PI-MCA Multi-Compartment Analysis Notebook 04/13/2018

FPRA-PI-MSO Fire Multiple Spurious Operation Notebook 04/13/2019

FPRA-PI-RRA Relay Room Analysis Notebook 5.3

V.SMN.15.007 Relay Room Incipient Detection Modification Sensitivity 03/10/2015

Miscellaneous FL-BSE-100-003L Introduction to Nuclear Security 0

PINGP 1385 Emergency Response Organization Activation 19

V.SMN.19.006 PINGP [Prairie Island Nuclear Generating Plant] NFPA 0

[National Fire Protection Association] 805 Monitoring

Program Risk Target Values

Operability F5 APP B Control Room Evacuation (Fire) 65

Evaluations

Procedures EDMG-2 Guideline for Damage Mitigation Strategies 12

F5 Appendix A Detection Zones and Fire Areas 41

F5 APPENDIX D Impact of Fire Outside Control/Relay Room 42

F5 Appendix D Impact of Fire Outside Control/Relay Room 41

F5 Appendix F Fire Hazards Analysis 36

F5 Appendix K Fire Protection Systems Functional Requirements 29

FP-PE-PRA-02 PRA Guideline for Model Maintenance and Update 16

Inspection Type Designation Description or Title Revision or

Procedure Date

H77 Fire Protection Program 2

H77.1 Fire Protection Program NFPA 805 Chapter 3 Compliance 2

Summary (NEI 04-02 Table B-1)

H77.2 Fire Protection Program NSCA Methodology Compliance 0

(NEI 04-02 Table B-2)

H77.3 Fire Area Assessments 0

Work Orders 700010880 SP 1192 Safeguards Electrical And Mechanical Penetrations 10/15/2018

Surveillance Inspection

700025089 SP 1197 Annual Header/Drains Flush Fire Protection System 06/18/2018

700028970 SP 1275 18 Month Safe Shutdown Fire Barrier Inspection 08/01/2018

700030214 SP 1196 Fire Protection Safety Related Sprinkler System 08/30/2018

Test

700032679 TP 1423 Portable Diesel Fire Pump Test 09/17/2018

700041404 SP 1197 Annual Header/Drains Flush Fire Protection System 07/13/2018

6

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