05000327/LER-2016-006, Regarding Improper Calibration of Reactor Trip Instrumentation Results in Condition Prohibited by Technical Specifications

Regarding Improper Calibration of Reactor Trip Instrumentation Results in Condition Prohibited by Technical Specifications

ML16256A335
Person / Time
Site:	Sequoyah
Issue date:	09/12/2016
From:	Schwarz C Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LER 16-006-00
Download: ML16256A335 (8)

LER-2016-006, Regarding Improper Calibration of Reactor Trip Instrumentation Results in Condition Prohibited by Technical Specifications

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)
3272016006R00 - NRC Website

text

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 September 12, 2016 10 CFR 50.73 ATTN:

Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Renewed Facility Operating License Nos. DPR-77 NRC Docket No. 50-327

Subject:

Licensee Event Report 50-327/2016-006-00, Improper Calibration of Reactor Trip Instrumentation Results in Condition Prohibited by Technical Specifications The enclosed licensee event report provides details concerning the noncompliance of one channel of the Reactor Trip System Instrumentation for longer than allowed by Technical Specifications. This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B), as any operation or condition which was prohibited by the plant's Technical Specifications.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact Michael McBrearty, Site Licensing Manager, at (423)843-7170.

Respectfully,

^y^^=v

- etiristopher J. Schwarz Site Vice President Sequoyah Nuclear Plant Enclosure: Licensee Event Report 50-327/2016-006-00 cc:

NRC Regional Administrator - Region II NRC Senior Resident Inspector-Sequoyah Nuclear Plant printed on recycled paper

NRC FORM 366 (11-2015)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (11-2015)

LICENSEE EVENT REPORT (LER)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Sequoyah Nuclear Plant Unit 1

2. DOCKET NUMBER 05000327

3. PAGE 1 OF 7

4. TITLE Improper Calibration of Reactor Trip Instrumentation Results in Condition Prohibited by Technical Specifications

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR FACILITY NAME NA DOCKET NUMBER 06 25 2016 2016 -

006

- 00 09 12 2016 FACILITY NAME NA DOCKET NUMBER

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x)

10. POWER LEVEL 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(v)(A) 73.71(a)(4) 100 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D) 73.77(a)(2)(i) 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(vii) 73.77(a)(2)(ii) 50.73(a)(2)(i)(C)

OTHER Specify in Abstract below or in LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET B.

Corrective actions to reduce probability of similar events occurring in the future:

Corrective actions include adding labeling to all Fluke 8845A DMMs to call attention to the impedance function of the device, briefing technicians on operation of the Fluke 8445A DMM, and revising the procedure associated with measuring M&TE to require a training performance analysis worksheet for all new M&TE.

Additional actions include:

determining if the same Fluke 8845A DMM was previously used in the past twelve months and validating with Reactor Engineering if additional actions are required.

revising procedures requiring use of the Fluke 8845A DMM to include a note to the technicians to ensure that the input impedance is set correctly.

VII. ADDITIONAL INFORMATION

A.

Previous similar events at the same plant:

A review of SQN LERs identified a similar event. LER 327/2016-005-00 submitted August 17, 2016, reports a condition prohibited by TS associated with the Hydrogen Mitigation System caused most likely by human error.

B.

Additional Information

None.

C. Safety System Functional Failure Consideration:

This condition did not result in a safety system functional failure.

D. Scrams with Complications Consideration:

There was no scram associated with this event.

VIII. COMMITMENTS

None.