05000348/LER-2016-007, Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters

Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters

ML17013A394
Person / Time
Site:	Farley
Issue date:	01/13/2017
From:	Pierce C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-0004 LER 16-007-00
Download: ML17013A394 (6)

LER-2016-007, Regarding Plant Shutdown Required by Technical Specifications Due to Inoperable Steam Flow Transmitters

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(ix)(A) 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)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
3482016007R00 - NRC Website

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~ Southern Nuclear JAN 13 2017 Docket Nos.: 50-348 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Charles R. Pierce Regulatory Affairs Director Joseph M. Farley Nuclear Plant-Unit 1 Licensee Event Report 2016-007-00 40 Inverness Center Parkway Birmingham, AI 35242 205.992.7872 tel 205.992.7601 fax crpierce@ southernco.com NL-17-0004 Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters Ladies and Gentlemen:

This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50.73(a)(2)(i)(A) and 10 CFR 50.73(a)(2)(v)(D) for Unit 1.

This letter contains no NRC commitments. If you have any questions regarding the submittal, please contact Ms. Julie Collier at (334) 814-4639.

Rc~~~~y tt:d*

C. R. Pierce Regulatory Affairs Director CRP/jac/lac Enclosure: Unit 1 Licensee Event Report 2016-007-00

U.S. Nuclear Regulatory Commission NL-17-0004 Page2 cc:

Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. M. D. Meier, Vice President-Regulatory Affairs Mr. D. R. Madison, Vice President-Fleet Operations Mr. B. J. Adams, Vice President-Engineering Ms. C. A. Gayheart, Vice President-Farley Ms. B. L. Taylor, Regulatory Affairs Manager-Farley Mr. K. D. Miller, Operating Experience Coordinator-Farley RTYPE: CFA04.054 U.S. Nuclear Regulatory Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley

Joseph M. Farley Nuclear Plant-Unit 1 Unit 1 Licensee Event Report 2016-007-00 Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 1013112018 (11 *2015)

, the NRC may not conduct or sponsor, and a person is no required to respond to, the information collection.

3. PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000- I 348 1

of 3

~*TITLE Plant Shutdown Required by Technical Specifications due to Inoperable Steam Flow Transmitters

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE B. OTHER FACILITIES INVOLVED I SEQUENTIAL I REV NO ACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR ACILITYNAME DOCKET NUMBER 11 17 2016 2016 007 -

00 1

13 2017

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) 0 50.36(c)(2) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 99 0 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50. 73(a)(2)(v)(C) 0 73.77(a)(1) 0 20.2203(a)(2)(v)

[8] 50. 73(a)(2)(i)(A)

[8] 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)

D 50.73(a)(2)(i)(C) 0 OTHER Specify in Abslract below or in Two additional means of providing a main steam line isolation in the event of a steam line break were available. One is the low-steam-pressure main steam line isolation signal, and the other is the containment pressure signal. These functions remained fully capable of performing the main steam line isolation function during the periods that the steam flow channels were known to be out of tolerance.

Additional means of providing the necessary protection against a steam pipe rupture were maintained.

One of these was safety injection (SI) system actuation from low pressurizer pressure signals, high steam line differential pressure, low main steam line pressure, or high containment pressure signals. Another means available was the overpower reactor trips and the reactor trip occurring in conjunction with receipt of the Sl signal. A third was the redundant isolation of the main feedwater lines to prevent sustained high feedwater flow which would cause additional cooldown.

The loss of the main steam line isolation from the high steam flow and low-low RCS average temperature signal was determined to be of low risk due to redundant trips for mitigation of a steam line break remaining operable.

F.

CORRECTIVE ACTION

The steam flow transmitters were restored to operable status. New scaling data was calculated and the channels were rescaled. Further corrective actions will be determined upon completion of the causal analysis and will be scheduled to ensure timeliness of implementation before the next refueling outage.

G. ADDITIONAL INFORMATION

1) Previous Similar Events:

Joseph M. Farley Unit 2 LER 2013-001-00 was submitted on July 26, 2013 to report two instances of a condition prohibited by Technical Specifications due to the untimely renormalization of Steam Flow Transmitter FT -494 at the beginning of two operating cycles.

Joseph M. Farley Unit 1 LER 2013-003-00 was submitted on January 3, 2014 to report a condition prohibited by Technical Specifications due to the untimely renormalization of Steam Flow Transmitter FT -495 at the beginning of an operating cycle.

Joseph M. Farley Units 1 and 2 LER 2014-003-00 was submitted on June 2, 2014 for scaling errors that resulted in inoperable steam flow channels for durations longer than allowed by Technical Specifications.

2) Commitment Information: This report does not create any licensing commitments 00 Page 3 of 3