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=Text=
=Text=
{{#Wiki_filter:January 5, 2016
{{#Wiki_filter:UNITED STATES ary 5, 2016


==SUBJECT:==
==SUBJECT:==
PERRY NUCLEAR POWER PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000 440/20 1 5008
PERRY NUCLEAR POWER PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000440/2015008


==Dear Mr. Hamilton:==
==Dear Mr. Hamilton:==
On October 23, 2015, the U.S. Nuclear Regulato ry Commission (NRC) completed a triennial fire protection inspection at your Perry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on December 29, 2015, with Mr. N. Conicella , and other members of your staff.
On October 23, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial fire protection inspection at your Perry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on December 29, 2015, with Mr. N. Conicella, 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 inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.


NRC inspectors documented four findings of very low safety significance (Green) in this report. These findings were determined to involve violations of NRC requirements. However, because of their very low safety significance
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
, 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 the 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:
NRC inspectors documented four findings of very low safety significance (Green) in this report.
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 a t the Perry Nuclear Power 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 Perry Nuclear Power Plant
These findings were determined to involve violations of NRC requirements. 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.
. 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).
 
If you contest the subject or severity of the 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, Region III; the Director, Office of Enforcement, U.S.
 
Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Perry Nuclear Power 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 Perry Nuclear Power 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,
Sincerely,
/RA/
/RA/
Robert C. Daley, Chi ef Engineering Branch 3 Division of Reactor Safety Docket Nos.
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-440 License Nos. NPF-58
 
50-440 License Nos. NPF-58  


===Enclosure:===
===Enclosure:===
Inspection Report 05000 440/20 1 5008 w/Attachment:
Inspection Report 05000440/2015008 w/Attachment: Supplemental Information
Supplemental Information


REGION III==
REGION III==
Docket No: 50-440 License No
Docket No: 50-440 License No: NPF-58 Report No: 05000440/2015008 Licensee: FirstEnergy Nuclear Operating Company Facility: Perry Nuclear Power Plant Location: North Perry, Ohio Dates: September 22 through October 23, 2015 Inspectors: A. Dahbur, Senior Reactor Inspector G. Hausman, Senior Reactor Inspector D. Szwarc, Senior Reactor Inspector, Lead R. Winter, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
: NPF-58 Report No:
 
05000 440/20 1 5008 Licensee: FirstEnergy Nuclear Operating Company Facility: Perry Nuclear Power Plant Location: North Perry, Ohio Dates: September 2 2 through October 23, 2015 Inspectors:
Table of Contents Table of Contents..................................................................................................................... 2
A. Dahbur, Senior Reactor Inspector G. Hausman, Senior Reactor Inspector D. Szwarc, Senior Reactor Inspector, Lead R. Winter, Reactor Inspector Approved by:
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Table of Contents Table of Contents
................................
................................................................
.....................
2  


=SUMMARY=
=SUMMARY=
................................
................................................................................................................................ 2
 
................................................................
................................
2


=REPORT DETAILS=
=REPORT DETAILS=
................................................................................................
....................


==REACTOR SAFETY==
==REACTOR SAFETY==
................................
......................................................................................... 4 {{a|1R05}}
.........................................................
 
{{a|1R05}}
==1R05 Fire Protection==
==1R05 Fire Protection==
{{IP sample|IP=IP 71111.05T}}
{{IP sample|IP=IP 71111.05T}}
....................................................................... 4
....................................................................... 4


===.1 Protection of Safe Shutdown Capabilities===
===.1 Protection of Safe Shutdown Capabilities ......................................................... 5===
 
................................
.........................
 
===.2 Passive Fire Protection===
 
................................
....................................................
 
===.3 Active Fire Protection===
 
................................
......................................................
 
===.4 Protection from Damage from Fire Suppression Activities===
 
...............................
 
===.5 Alternative Shutdown Capability===
 
................................
......................................11
 
===.6 Circuit Analyses===
 
................................
..............................................................
 
===.7 Communications===
 
................................
.............................................................


===.8 Emergency Lighting===
===.2 Passive Fire Protection .................................................................................... 8===


................................
===.3 Active Fire Protection ......................................................................................11===
........................................................


===.9 Cold Shutdown Repairs===
===.4 Protection from Damage from Fire Suppression Activities ...............................11===


...................................................................................
===.5 Alternative Shutdown Capability ......................................................................11===


===.10 Compensatory Measures===
===.6 Circuit Analyses ..............................................................................................12===


................................
===.7 Communications .............................................................................................15===
................................................


===.11 Review and Documentation of Fire Protection Program Changes===
===.8 Emergency Lighting ........................................................................................15===


...................
===.9 Cold Shutdown Repairs...................................................................................15===


===.12 Control of Transient Combustibles and Ignition Sources===
===.10 Compensatory Measures ................................................................................16===


................................
===.11 Review and Documentation of Fire Protection Program Changes ...................18===


===.18 .13 B.5.b Inspection Activities===
===.12 Control of Transient Combustibles and Ignition Sources .................................18===


................................
===.13 B.5.b Inspection Activities===
...............................................


==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
................................
.......................................................................................19 {{a|4OA2}}
.......................................................
 
{{a|4OA2}}
==4OA2 Identification and Resolution of Problems==
==4OA2 Identification and Resolution of Problems==
{{IP sample|IP=IP 71152}}
{{IP sample|IP=IP 71152}}
................................
...................................19
...19
 
{{a|4OA6}}
{{a|4OA6}}
==4OA6 Management Meetings==
==4OA6 Management Meetings .............................................................................20==
 
................................
.............................................
 
===.1 Exit Meeting Summary===


....................................................................................
===.1 Exit Meeting Summary ....................................................................................20===


===.2 Interim Exit Meetings===
===.2 Interim Exit Meetings .......................................................................................20===
 
................................
.......................................................
20  


=SUPPLEMENTAL INFORMATION=
=SUPPLEMENTAL INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
.................................................................................................. 1


................................
................................................................
.. 1
==LIST OF ITEMS==
==LIST OF ITEMS==
 
OPENED, CLOSED AND DISCUSSED........................................................ 1
===OPENED, CLOSED AND DISCUSSED===
 
................................
........................


==LIST OF DOCUMENTS REVIEWED==
==LIST OF DOCUMENTS REVIEWED==
 
...................................................................................... 2
}}
}}

Latest revision as of 01:24, 20 December 2019

Inspection Report 05000440/2015008; 09/22/2015 - 10/23/2015; Perry Nuclear Power Plant; Routine Triennial Fire Protection Baseline Inspection (Dxs)
ML16005A548
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 01/05/2016
From: Robert Daley
Engineering Branch 3
To: Hamilton D
FirstEnergy Nuclear Operating Co
References
IR 2015008
Download: ML16005A548 (31)


Text

UNITED STATES ary 5, 2016

SUBJECT:

PERRY NUCLEAR POWER PLANT - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000440/2015008

Dear Mr. Hamilton:

On October 23, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed a triennial fire protection inspection at your Perry Nuclear Power Plant. The enclosed inspection report documents the inspection results, which were discussed on December 29, 2015, with Mr. N. Conicella, and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

NRC inspectors documented four findings of very low safety significance (Green) in this report.

These findings were determined to involve violations of NRC requirements. 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 the 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, Region III; the Director, Office of Enforcement, U.S.

Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Perry Nuclear Power 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 Perry Nuclear Power 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/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-440 License Nos. NPF-58

Enclosure:

Inspection Report 05000440/2015008 w/Attachment: Supplemental Information

REGION III==

Docket No: 50-440 License No: NPF-58 Report No: 05000440/2015008 Licensee: FirstEnergy Nuclear Operating Company Facility: Perry Nuclear Power Plant Location: North Perry, Ohio Dates: September 22 through October 23, 2015 Inspectors: A. Dahbur, Senior Reactor Inspector G. Hausman, Senior Reactor Inspector D. Szwarc, Senior Reactor Inspector, Lead R. Winter, Reactor Inspector Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

Table of Contents Table of Contents..................................................................................................................... 2

SUMMARY

................................................................................................................................ 2

REPORT DETAILS

REACTOR SAFETY

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

1R05 Fire Protection

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

.1 Protection of Safe Shutdown Capabilities ......................................................... 5

.2 Passive Fire Protection .................................................................................... 8

.3 Active Fire Protection ......................................................................................11

.4 Protection from Damage from Fire Suppression Activities ...............................11

.5 Alternative Shutdown Capability ......................................................................11

.6 Circuit Analyses ..............................................................................................12

.7 Communications .............................................................................................15

.8 Emergency Lighting ........................................................................................15

.9 Cold Shutdown Repairs...................................................................................15

.10 Compensatory Measures ................................................................................16

.11 Review and Documentation of Fire Protection Program Changes ...................18

.12 Control of Transient Combustibles and Ignition Sources .................................18

.13 B.5.b Inspection Activities

OTHER ACTIVITIES

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

4OA2 Identification and Resolution of Problems

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

4OA6 Management Meetings .............................................................................20

.1 Exit Meeting Summary ....................................................................................20

.2 Interim Exit Meetings .......................................................................................20

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

.................................................................................................. 1

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED........................................................ 1

LIST OF DOCUMENTS REVIEWED

...................................................................................... 2