05000285/LER-2016-001, Regarding Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor

From kanterella
(Redirected from 05000285/LER-2016-001)
Jump to navigation Jump to search

Regarding Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor
ML16099A274
Person / Time
Site: Fort Calhoun 
Issue date: 04/08/2016
From: Marik S
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-16-0027 LER 16-001-00
Download: ML16099A274 (4)
v • d • e


LER-2016-001, Regarding Technical Specification Violation Due to Installation of an Unqualified Part in a Radiation Monitor
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)
2852016001R00 - NRC Website
v • d • e

text

Omaha Public Power District LIC-16-0027 April 8, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 10 CFR 73.71

Subject:

Licensee Event Report 2016-001, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2016-001, Revision 0. This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(i)(B) and 10 CFR 50. 73(a)(2)(v)(C). There are no new commitments being made in this letter.

If you should have any questions, please contact Brad Blome, Manager, Site Regulatory Assurance, at (402) 533-7270.

Sincerel

/1

.J

nl Site Vice President and CNO SMM/cac Attachment c:

M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S.M. Schneider, NRC Senior Resident Inspector 444 SOUTH 16TH STREET MALL

  • OMAHA, NE 68102-2247

NRC FORM 366 (11-2015)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018

, the NRC may not conduct or sponSOf, and a person is not reqwed to respond to, the information collection

3. PAGE Fort Calhoun Station 05000 285 I

OF 3

4. TITLE Technical Specification Violation due to Installation of an Unqualified Part in a Radiation Monitor
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED I

SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NO 05000 FACIUTY NAME DOCKET NUMBER 02 10 2016 2016 001 00 04 08 2016 05000

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50. 73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 1 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50. 73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(iii) 0 50. 73(a)(2)(ix)(A) 0 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(v)(A) 0 73.71(a){4) 0 20.2203(a)(2)(iii)

O 50.36(c)(2)

D 50.73(a)(2)(v)(B) 0 73.71(a)(5)

D 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(C) 0 73.77(a)(1) 100 0 20.2203(a)(2)(v) 0 50. 73(a){2)(i)(A) 0 50.73(a)(2)(v)(D) 0 73.77(a)(2)(i) 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii) 0 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 0 OTHER Specfy tn Abstract below or In BACKGROUND

2. DOCKET NUMBER 1

28l

3. LER NUMBER D

NUMBER NO.

I YEAR SEQUENTIAL REV

 - 1 001 1-0 Fort Calhoun Station (FCS) is a two-loop reactor coolant system (RCS) of Combustion Engineering design.

RM-052, Containment and Auxiliary Building Stack Gaseous Swing Radiation Monitor, is part of the Process Radiation Monitoring System to provide surveillance of the plant effluent and critical process streams. The safety related function of the Process Radiation Monitoring Function is to provide a signal to initiate a Containment Radiation High Signal (CRHS) when radiation high alarm setpoint values are exceeded. During normal operation RM-052 is normally lined up to monitor the Vent Stack along with Auxiliary Building Vent Stack Monitor, RM-062.

RM-052 also acts as a back up to the dedicated Containment Monitor RM-051. During abnormal or emergency operation of the Process Monitoring System RM-51, RM-052 or RM-062 will provide a signal to actuate a CRHS which activates a Ventilation Isolation Actuation Signal (VIAS) when any of the three monitors is in High Alarm.

EVENT DESCRIPTION

On February 10,2016, FCS became aware of the Canberra 10 CFR 21.21 notification related to the three separate POs to OPPD that had commercial grade items that were not properly dedicated as basic components per the PO requirements. The three POs are 185091, 185157, and 191479. (NOTE: The letter calls out PO 185167 - which is incorrect, further research identified the correct PO to be 185157). An investigation was performed by FCS staff and on February 12, 2016 determined that Catalog ID 27019-1 (PO #185157) was installed in RM-052 under Work Order 399904. At that time the control room was notified and Condition Report 2016-01409 was initiated. RM-052 was declared inoperable and the additional components identified in the notification were quarantined.

At the time the Control room was notified, RM-051 remained operable and in service sampling containment.

RM-062 also remained operable and in service sampling the Auxiliary Build ventilation stack satisfying TS 2.15.

A review of past operability identified instances when RM-051 and RM-062 were out of service for periods longer than allowed by TS. Specifically,

  • 2.15.1 (1) requires within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of RM-052 or RM-062 going inoperable containment purge and relief valves must be closed (bypass condition). After 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the CRHS would need to be locked in.
  • 2.15.1 (3) requires within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of RM-052 or RM-062 going inoperable the reactor must be placed in hot shutdown or ventilation isolation valves are closed.

This event is reportable per 10 CFR 50. 73(a)(2)(i)(B) operation or condition prohibited by Technical Specifications and 10 CFR 50. 73(a)(2)(v)(C) Event or Condition that could have prevented fulfillment of a safety condition to control the release of radioactive material.

CONCLUSION Canberra failed to establish adequate measures for the selection and review for sustainability for purchase orders 185091, 185157, and 191479. The parts are critical to the safety-related functions of the components and Canberra failed to identify and verify the appropriate critical characteristics and failed to ensure that the components meUenveloped the applicable qualification reports as required by the POs. All three POs had seismically, environmentally or electromagnetic interference (EMI)/electromagnetic compatibility (EMC) qualified (11*2015)

1. FACILITY NAME LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

2. DOCKET NUMBER I 05000- 1 28l Page 2 of2 U.S. NUCLEAR REGULATORY COMMISSION
3. LER NUMBER D

NUMBER NO.

I YEAR SEQUENTIAL REV u -I 001 I* 0 related Items tnat were not appropnately verltlect or evaluated. (Nonconformance 99901 l61/2U15-201-J1) ThiS resulted in a Technical Specification violation due to installation of an unqualified part in radiation monitor RM-052.

CORRECTIVE ACTIONS

As previously stated the Time Delay Relay was replaced on 03/19/2016 with qualified part (WO 578335) and RM-052 was returned to service following successful surveillance testing. Other equipment identified in PO 185091, 185157 and 191479 was quarantined awaiting resolution through the Over, Short, Damaged and Discrepant (OSDD) process at FCS.

SAFETY SIGNIFICANCE

The safety related function of the Process Radiation Monitoring Function is to provide a signal to initiate a Containment Radiation High Signal (CRHS) when radiation high alarm setpoint values are exceeded. During normal operation RM-052 is lined up to monitor the Vent Stack along with Auxiliary Building Vent Stack Monitor RM-062. RM-052 can also acts as a back up to the dedicated Containment Monitor RM-051. During abnormal or emergency operation of the Process Monitoring System RM-051, RM-052 or RM-062 will provide a signal to actuate a CRHS which activates a Ventilation Isolation Actuation Signal (VIAS) when any of the three monitors is in High Alarm. During the time when RM-052 contained an unqualified part, one of the three radiation monitors was available to respond to an unlikely event that would require VIAS.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does represent a safety system function failure in accordance with NEI 99-02.

PREVIOUS SIMILAR EVENTS

There were no previous LERs identified in the past three years for unqualified parts installed in a radiation monitor.

Retrieved from "https://kanterella.com/w/index.php?title=05000285/LER-2016-001,_Regarding_Technical_Specification_Violation_Due_to_Installation_of_an_Unqualified_Part_in_a_Radiation_Monitor&oldid=5174079"