IR 05000440/2007010: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:January 25, 2008  
{{#Wiki_filter:ary 25, 2008


Mr. Barry Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P. O. Box 97, 10 Center Road, A-PY-290 Perry, OH 44081-0097 SUBJECT: PERRY NUCLEAR POWER PLANT NRC SPECIAL INSPECTION REPORT 05000440/2007010
==SUBJECT:==
PERRY NUCLEAR POWER PLANT NRC SPECIAL INSPECTION REPORT 05000440/2007010


==Dear Mr. Allen:==
==Dear Mr. Allen:==
On December 13, 2007, the Nuclear Regulatory Commission (NRC) completed a Special Inspection at your Perry Nuclear Power Plant to evaluate the facts and circumstances surrounding the reactor scram with loss of all feedwater on November 28, 2007. The enclosed report documents the inspection findings, which were discussed on December 13, 2007, with you and members of your staff.
On December 13, 2007, the Nuclear Regulatory Commission (NRC) completed a Special Inspection at your Perry Nuclear Power Plant to evaluate the facts and circumstances surrounding the reactor scram with loss of all feedwater on November 28, 2007. The enclosed report documents the inspection findings, which were discussed on December 13, 2007, with you and 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 plant personnel.
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.


Based on the risk and deterministic criteria specified in Management Directive 8.3, "NRC Incident Investigation Program," and Inspection Procedure 71153, "Event Follow-up," and due to the equipment performance problems which occurred, a Special Inspection was initiated in accordance with Inspection Procedure 93812, "Special Inspection." The Special Inspection evaluated the facts and circumstances surrounding the event, as well as the actions taken by your staff in response to the unexpected equipment conditions. The inspection focus areas are detailed in the Special Inspection Charter (Attachment 3).
The inspectors reviewed selected procedures and records, observed activities, and interviewed plant personnel.
 
Based on the risk and deterministic criteria specified in Management Directive 8.3,
"NRC Incident Investigation Program," and Inspection Procedure 71153, "Event Follow-up," and due to the equipment performance problems which occurred, a Special Inspection was initiated in accordance with Inspection Procedure 93812, "Special Inspection." The Special Inspection evaluated the facts and circumstances surrounding the event, as well as the actions taken by your staff in response to the unexpected equipment conditions. The inspection focus areas are detailed in the Special Inspection Charter (Attachment 3).


Based on the results of this special inspection, one inspector-identified finding of very low safety significance (Green) was identified.
Based on the results of this special inspection, one inspector-identified finding of very low safety significance (Green) was identified.


At the conclusion of the inspection, questions remained regarding the past operability of the reactor core isolation cooling system following a calibration performed in January 2006, the initial classification of the condition report documenting the RCIC system failure, and the quality of two Immediate Investigation reports. The outcome of these questions will directly affect the significance characterization of the performance deficiencies associated with RCIC operability, event classification, and event evaluation. One unresolved item has been opened to monitor your assessment of the RCIC system's operability from January 2006 to November 28, 2007, including your assessment of the appropriateness of the system's monthly and quarterly surveillance procedures. Two other unresolved items have been opened regarding the initial classification of the condition report written on the RCIC failure and the quality of two immediate investigations unrelated to RCIC. The immediate remedial corrective actions included, but were not limited to: troubleshooting, maintenance, repair, and modification of the digital feedwater control system; tuning and testing of the RCIC system; re-classification of the initial RCIC condition report; and re-investigation of the issues associated with the motor drive feedwater pump operation without cooling flow and control rod drive hydraulic unit scram valve operation. At the conclusion of the inspection, we understand that your staff continued to evaluate the RCIC system operability, including the quarterly surveillance test, RCIC flow controller settings and equipment qualification issues.
At the conclusion of the inspection, questions remained regarding the past operability of the reactor core isolation cooling system following a calibration performed in January 2006, the initial classification of the condition report documenting the RCIC system failure, and the quality of two Immediate Investigation reports. The outcome of these questions will directly affect the significance characterization of the performance deficiencies associated with RCIC operability, event classification, and event evaluation. One unresolved item has been opened to monitor your assessment of the RCIC systems operability from January 2006 to November 28, 2007, including your assessment of the appropriateness of the systems monthly and quarterly surveillance procedures. Two other unresolved items have been opened regarding the initial classification of the condition report written on the RCIC failure and the quality of two immediate investigations unrelated to RCIC. The immediate remedial corrective actions included, but were not limited to: troubleshooting, maintenance, repair, and modification of the digital feedwater control system; tuning and testing of the RCIC system; re-classification of the initial RCIC condition report; and re-investigation of the issues associated with the motor drive feedwater pump operation without cooling flow and control rod drive hydraulic unit scram valve operation. At the conclusion of the inspection, we understand that your staff continued to evaluate the RCIC system operability, including the quarterly surveillance test, RCIC flow controller settings and equipment qualification issues.


Based on the document reviews, activity observations, and discussions with your staff, the inspection team concluded that as of December 4, 2007, your organization's response to the RCIC system's performance during the November 28, 2007 event was not consistent with the safety significance of the issue. The initial scope, depth, and level of effort applied by your organization to this issue were inadequate. While improvements were noted following the December 4, 2007, inspection team briefing and the December 13, 2007, exit meeting, the NRC remained concerned with operability of the RCIC system and efforts to properly tune the RCIC flow controller.
Based on the document reviews, activity observations, and discussions with your staff, the inspection team concluded that as of December 4, 2007, your organizations response to the RCIC systems performance during the November 28, 2007 event was not consistent with the safety significance of the issue. The initial scope, depth, and level of effort applied by your organization to this issue were inadequate. While improvements were noted following the December 4, 2007, inspection team briefing and the December 13, 2007, exit meeting, the NRC remained concerned with operability of the RCIC system and efforts to properly tune the RCIC flow controller.


If you contest the finding in this report, 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, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector at the Perry Nuclear Power Plant.
If you contest the finding in this report, 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, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector at the Perry Nuclear Power Plant.


In accordance with 10 CFR 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 document system (ADAMS), is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
In accordance with 10 CFR 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 document system (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/ Cynthia D. Pederson, Director Division of Reactor Projects Docket No. 50-440 License No. NPF-58  
/RA/
Cynthia D. Pederson, Director Division of Reactor Projects Docket No. 50-440 License No. NPF-58 Enclosure: Inspection Report 05000440/2007010(DRP);
w/Attachment: Supplemental Information DISTRIBUTION:
See next page


Enclosure: Inspection Report 05000440/2007010(DRP); w/Attachment: Supplemental Information DISTRIBUTION:
Letter to
See next page Letter to
}}
}}

Latest revision as of 21:07, 14 November 2019

IR 05000440-07-010; on 11/28/2007 - 12/13/2007; Perry Nuclear Power Plant; Special Inspection Team
ML080280499
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 01/25/2008
From: Pederson C
Division Reactor Projects III
To: Allen B
FirstEnergy Nuclear Operating Co
References
IR-07-010
Download: ML080280499 (38)
v • d • e


Text

ary 25, 2008

SUBJECT:

PERRY NUCLEAR POWER PLANT NRC SPECIAL INSPECTION REPORT 05000440/2007010

Dear Mr. Allen:

On December 13, 2007, the Nuclear Regulatory Commission (NRC) completed a Special Inspection at your Perry Nuclear Power Plant to evaluate the facts and circumstances surrounding the reactor scram with loss of all feedwater on November 28, 2007. The enclosed report documents the inspection findings, which were discussed on December 13, 2007, with you and 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 plant personnel.

Based on the risk and deterministic criteria specified in Management Directive 8.3,

"NRC Incident Investigation Program," and Inspection Procedure 71153, "Event Follow-up," and due to the equipment performance problems which occurred, a Special Inspection was initiated in accordance with Inspection Procedure 93812, "Special Inspection." The Special Inspection evaluated the facts and circumstances surrounding the event, as well as the actions taken by your staff in response to the unexpected equipment conditions. The inspection focus areas are detailed in the Special Inspection Charter (Attachment 3).

Based on the results of this special inspection, one inspector-identified finding of very low safety significance (Green) was identified.

At the conclusion of the inspection, questions remained regarding the past operability of the reactor core isolation cooling system following a calibration performed in January 2006, the initial classification of the condition report documenting the RCIC system failure, and the quality of two Immediate Investigation reports. The outcome of these questions will directly affect the significance characterization of the performance deficiencies associated with RCIC operability, event classification, and event evaluation. One unresolved item has been opened to monitor your assessment of the RCIC systems operability from January 2006 to November 28, 2007, including your assessment of the appropriateness of the systems monthly and quarterly surveillance procedures. Two other unresolved items have been opened regarding the initial classification of the condition report written on the RCIC failure and the quality of two immediate investigations unrelated to RCIC. The immediate remedial corrective actions included, but were not limited to: troubleshooting, maintenance, repair, and modification of the digital feedwater control system; tuning and testing of the RCIC system; re-classification of the initial RCIC condition report; and re-investigation of the issues associated with the motor drive feedwater pump operation without cooling flow and control rod drive hydraulic unit scram valve operation. At the conclusion of the inspection, we understand that your staff continued to evaluate the RCIC system operability, including the quarterly surveillance test, RCIC flow controller settings and equipment qualification issues.

Based on the document reviews, activity observations, and discussions with your staff, the inspection team concluded that as of December 4, 2007, your organizations response to the RCIC systems performance during the November 28, 2007 event was not consistent with the safety significance of the issue. The initial scope, depth, and level of effort applied by your organization to this issue were inadequate. While improvements were noted following the December 4, 2007, inspection team briefing and the December 13, 2007, exit meeting, the NRC remained concerned with operability of the RCIC system and efforts to properly tune the RCIC flow controller.

If you contest the finding in this report, 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, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector at the Perry Nuclear Power Plant.

In accordance with 10 CFR 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 document system (ADAMS), is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Cynthia D. Pederson, Director Division of Reactor Projects Docket No. 50-440 License No. NPF-58 Enclosure: Inspection Report 05000440/2007010(DRP);

w/Attachment: Supplemental Information DISTRIBUTION:

See next page

Letter to

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