05000336/LER-2013-001, Regarding Historical Acoustic Monitor Channel Check Discovered to Have Not Met Acceptance Criteria

Regarding Historical Acoustic Monitor Channel Check Discovered to Have Not Met Acceptance Criteria

ML13080A255
Person / Time
Site:	Millstone
Issue date:	03/12/2013
From:	Scace S Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
13-091 LER 13-001-00
Download: ML13080A255 (6)

LER-2013-001, Regarding Historical Acoustic Monitor Channel Check Discovered to Have Not Met Acceptance Criteria

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function
LER closed by
IR 05000245/2013002 (11 April 2013)
3362013001R00 - NRC Website

text

iJ'rDominion Dominion Nuclear Connecticut, Inc.

Rope Ferry Road, Waterford, CT 06385 Web Address: www.dom.com MAR 12 2013 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.

MPS Lic/LES Docket No.

License No.13-091 RO 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 2 LICENSEE EVENT REPORT 2013-001-00 HISTORICAL ACOUSTIC MONITOR CHANNEL CHECK DISCOVERED TO HAVE NOT MET ACCEPTANCE CRITERIA This letter forwards Licensee Event Report (LER) 2013-001-00 documenting a condition discovered at Millstone Power Station Unit 2 on January 17, 2013.

This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications.

If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.

Sincerely, Ste e

ic Site Vice President - Millstone Attachments: 1 Commitments made in this letter: None

Serial No.13-091 Docket No. 50-336 Licensee Event Report 2013-001-00 Page 2 of 2 cc:

U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.13-091 Docket No. 50-336 Licensee Event Report 2013-001-00 ATTACHMENT LICENSEE EVENT REPORT 2013-001-00 MILLSTONE POWER STATION UNIT 2 DOMINION NUCLEAR CONNECTICUT, INC.

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10/2010)

, the NRC may not conduct or sponsor, diaits/characters for each block) and a person is not required to respond to, the information collection.

3. PAGE Millstone Power Station - Unit 2 05000336 1 OF3

4. TITLE Historical Acoustic Monitor Channel Check Discovered to Have Not Met Acceptance Criteria

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED 1SEQUENTIAL RFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR I NUMBER NO. MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 01 17 2013 2013- 001 - 00 03 12 2013 05000

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR : check all that apply)

9. OPERATING MODE 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1 )(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)

10. POWER LEVEL 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71 (a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71 (a)(5) 100 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi)

X 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in

1.

EVENT DESCRIPTION

At 0938 on January 15, 2013, with Millstone Power Station Unit 2 (MPS2) in Mode 1, operating at 100 percent power, while performing a monthly required channel check on the safety valve's position indication, technicians discovered that the channel B primary safety valve [AB] [RV] acoustic valve monitor system (AVMS) position indicator [MON] failed to meet acceptance criteria contained in Surveillance Procedure SP2410A. A CHANNEL CHECK is defined in the TS as the qualitative assessment of channel behavior during operation by observation. Its purpose is to verify Operability of the channel of AVMS. In this instance, the technicians had expected to observe a frequency peak at or near 74.25 Hz on the AVMS' output, which is induced by an operating reactor coolant pump. After reviewing a printout obtained from the instrumentation loop, it was determined that the frequency peak expected at or near 74.25 Hz was not detected. Therefore, the AVMS channel was declared inoperable and Operators entered Technical Specification (TS) 3.3.3.8, Accident Monitoring Instrumentation, Action 3, for Item 6, Safety Valve Position Indicator, which specifies that alternate indications shall be checked once each shift.

On January 17, 2013, upon reviewing the results from the previous month's completed channel check surveillance performed on the AVMS on December 18, 2012, it was discovered that the AVMS had also failed to meet the acceptance criteria for a channel check in SP241 OA at that time. It was not, however, recognized in December 2012 that the surveillance results did not meet acceptance criteria, so the instrument was not declared inoperable at the time. The technicians and condition based maintenance personnel had observed a frequency peak at approximately 72.5 Hz and incorrectly interpreted the observed frequency to be sufficiently near 74.25 Hz and therefore acceptable. On November 15, 2012, the channel check on AVMS was verified to have been successfully completed.

Troubleshooting was performed on accessible portions of the AVMS on January 25, 2013, which revealed problems with the AVMS equipment located inside reactor containment. Work has been scheduled in the station's work management process for investigation and troubleshooting of AVMS during the next MPS2 refueling outage.

This condition is being reported pursuant to 10 CFR 73(a)(2)(i)(B) as any operation or condition which was prohibited by the plant's TS.

2.

CAUSE

The cause was determined to be inadequate procedure guidance in SP2410A which led to confusion when interpreting surveillance results.

3.

ASSESSMENT OF SAFETY CONSEQUENCES

The AVMS provides indications and alarms that are a diagnostic aid for operators to determine the position of the primary (Reactor Coolant System) code safety valves. Although the AVMS provides an alarm to alert operators whenever the safety valve is open, AVMS provides no automatic equipment or protective actions. Alternative means are and always were available in the MPS2 control room which provide indication of the safety valve's position and most of these indications can be trended. Therefore, there were no adverse safety consequences.

I

4.

CORRECTIVE ACTION

Surveillance Procedure SP241 OA has been revised to include clearer acceptance criteria for a channel check, specific working group interface and peer review of data evaluation. Other actions are being taken in accordance with the station's corrective action program.

5.

PREVIOUS OCCURRENCES

No previous similar events/conditions were identified.

Energy Industry Identification System (ElIS) codes are identified in the text as [XX].