GO2-17-139, Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report

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Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report
ML17215B031
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 08/03/2017
From: Gregoire D
Energy Northwest
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-17-139
Download: ML17215B031 (2)
v • d • e


Text

Donald W Gregoire Columbia Generating Station P.O. Box 968, MD PE20 Richland, WA 99352-0968 Ph. 509-377-8616 l F. 509-377-4317 dwgregoire@energy-northwest.com August 3, 2017 GO2-17-139 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 TECHNICAL SPECIFICATIONS SECTION 5.6.4 POST ACCIDENT MONITORING INSTRUMENTATION REPORT

Dear Sir or Madam:

This letter is being submitted pursuant to Technical Specifications (TS) Section 5.6.4 for Columbia Generating Stations Post Accident Monitoring Instrumentation Report.

On June 25, 2017, during a planned maintenance activity the closed position indication for the Reactor Recirculation System Inboard Primary Containment Isolation Valve (RRC-V-19) did not indicate closed as expected when isolated.

This required entry into TS Section 3.3.3.1, Post Accident Monitoring (PAM)

Instrumentation Condition A, due to an inoperable indication channel for Function 7 of Table 3.3.3.1-1 Penetration Flow Path PCIV Position. Condition A requires restoration of the required indication channel to an operable status within 30 days, or per Condition B initiate reporting requirements in accordance with TS Section 5.6.4.

Resolution of this issue within the 30-day requirement was not feasible due to the physical location of the affected valve in primary containment which precludes access while the unit is at power. For this reason, Energy Northwest is submitting this letter in accordance with TS Section 5.6.4. The failure of the valve indication is likely due to a faulty valve position switch. It is acceptable to use valve position indication when it is functioning. When valve position indication is not available, valve closure is verified in accordance with plant procedures by utilizing pressure and flow indication downstream of the affected valve. The limit switches for the affected valve are scheduled to be worked in the next refueling outage.

G02-17-139 Page 2 of 2 There are no commitments being made to the Nuclear Regulatory Commission by this letter. If you have any questions or require additional information, please contact Ms.

D.M. Wolfgramm, Regulatory Compliance Supervisor, at (509) 377-4792.

Executed on this gJ day of Avjost; 2017.

~y, D.W. Gregoire Manager, Regulatory Affairs and Performance Improvement cc: NRC Region IV Regional Admin NRC Region IV Project Manager NRC Senior Resident Inspector C.D. Sonoda - BPA W.A. Horin - Winston & Strawn

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