4. Southern Nuclear

November 20, 2017

Docket No.: 50-348

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001

Dems R. Matfson Va Plesideld - Fa.otey

Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2016-007-02

NL-17-1952

Plant Shutdown Reauired by Technical Specifications due to Inoperable Steam Row Transmitters

Ladies and Gentlemen:

This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations 10 CFR 50.73(a)(2)(i)(A), 10 CFR 50.73(a}(2)(Q(B), and 10 CFR 50.73(a)(2){v)(D).

This letter contains no NRC commitments. If you have any questions, please contact Mandy Ludlam at (334) 814-4930.

Respectfully submitted,

D.R. Madison Vice President - Farley

DRM!mmVcbg

Enclosure: Unit 1 LEA 2016-007-02

Cc: Regional Administrator, Region II NRR Project Manager- Farley Nuclear Plant Senior Resident Inspector- Farley Nuclear Plant RTYPE: CFA04.054

Enclosure

Joseph M. Farley Nuclear Plant

Unit 1 Licensee Event Report 2016-007·002

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

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1. FAcaJTY HAlE 2. DOCKET NUII8ER 3.PAGE

Joseph M. Farley Nuclear Plant. Unit I 051000 348 I OF 4

4.11TLE

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

&.EVENT DAlE I.LER NUMBER 7. REPORT DAlE 8. OTHER FACIUTJES INVOLVED

I~ I REV FAQ/fY- liOCIIEl .._ IIONlH ~y YEAR YEAR NO NOtmt ~y YEAR

05000

11 20 2017 FN::IUN - DOCI<£1" NUKilR II 17 2016 2016 - 007 - 02 05000 8. OPERATING IIOOE 11. nos REPORT IS SUBMtTTED PURSUANT TOnE REQUIREMENTS OF 10 CPR§: (Cheek 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)(o) 0 50.73(a)(2)(ii}(B) 0 50.73(a)(2)(vfu)(B)

0 20.2203(a)(1) 0 20.2203(a)(4> 0 50.73(a)(2)(iii) 0 50.73(a)(2)[1X)(A)

0 20.2203(a)(2)(i) 0 50.36{c)(1}(i){A) 0 50.73(a)(2)frv)(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(8}(4)

0 20.2203(a)(2}(iii} D 50.36{c)(2) 0 50. 73(a)(2)(v)(B) 0 73.71<a>cs>

0 20.2203(a)(2)(iv) 0 50.46(a)(3}(ii) 0 50.73(a)(2)(v)(C) O 73.n{a)(1)

099 0 20.2203(a)(2){v) 0 50. 73(a}{2}(i)(A) 0 50. 73(a)(2)(v)(D) D 73. n(a)(2)(i)

0 20.2203(a){2)(V1) 0 50.73(a)(2)(i)(B) D 50.73(a)(2)(Yii) D 73.n(a){2)(ii)

0 50.73(a)(2}(i)(C) DornER Specify tn Absnd llelcw or in NRC Form 386A

12. UCENSEE CONTACT FOR THIS lER LICENSEE CONTACT TELEPHONE NUMBER (lndJidll luee Code}

Mandy Ludlam. Licensing Engineer (334) 814-4930

13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT CAUSE SYSTEM COMPONENT MAHIJ- REPORTABLE CAUSE SYS1EM COMPONENT MANU· REPORTABLE

FACl\JRER TOEPIX FACTURER TOEPIX

D JE FT Fl80 y

14. SUPPLEMENTAL REPORT EXPECTED 16. EXPECTED MONTH DAY YEAR

0 YES (ffyes, complete 15. EXPECTED SUBMISSION DATE) 0 NO SUBMISSION DAlE

ABSTRACT (Limit to 1400 spKeS, I.e., 8ppi0Jiintalfl/y 15 si~ typewrlllfln llniiS) On 11/17/2016 at 1859 with Unit I in Mode I at 99 percent power, the plant initiated a shutdown in accordance with Limiting Condition for Operation (LCO) 3.0.3 for having no operable steam flow channels for the C Steam Generator (SO). The two steam flow channels did not meet acceptance criteria for Technical Specification (TS) 3.3.2. The shutdown was completed and the plant entered Mode 3 as required by LCO 3.0.3. This is reportable as a plant shutdown required by TS in accordance with 10 CFR 50.73(a)(2)(i)(A). This is also reportable as a condition prohibited by TS per 10 CFR 50.73(a)(2)(iXB) and an e\·ent or condition that could ha,·e prevented fulfillment of a Safety Function per I 0 CFR 50. 73(a)(2)(v)(D).

This condition was discovered during an engineering verification of beginning of cycle full power scaling values for steam flow nonnalization. The root cause was that necessary vendor manual instructions to calibrate different transmitters had not been captured into site procedures. The signal comparator card was replaced, and the channels were rescaled and restored to operable status. Instructions will be incorporated into currently planned work orders for upcoming transmitter calibrations and installations to check and adjust as needed. Also, procedures are being revised to incorporate all missing vendor requirements for all models of Foxboro transmitters.

NRC FORM 368 (04-2017)

NRC FORM 366A f04-2017)

U.S. NUa..EAR REGULA lORY COIIIIISSION APPROVED BY OMB: NO. 31&0-0104

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UCENSEE EVENT REPORT (LER) CONTINUATION SHEET

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1. FACIUTY NAME 2. DOCKET NUMBER 3.LERN1.-at

Joseph M. Far1ey Nuclear Plant, Unit 1 -1 348

NARRATIVE Event Description

On 11/17/2016 at 1859 with Unit 1 in Mode 1 at 99 percent power, the plant initiated a shutdown in accordance with Limiting Condition for Operation (LCO) 3.0.3 for having no operable steam flow channels [Fl] for the C Steam Generator [SG). The two steam flow channels on the 1C SG did not meet acceptance criteria for Technical Specification (TS) 3.3.2.

During full power engineering verification of beginning of cycle full power scaling values for steam flow normalization it was discovered that the two steam flow transmitter protection channels for the 1 C SG were outside the 2.5% acceptance criteria. This condition resulted in the Engineered Safety Feature Actuation System Instrumentation (ESFAS) function for high steam flow in the C steam line to be declared inoperable. The plant entered LCO 3.0.3 which required actions to be initiated within one (1) hour to place the Unit in MODE 3 within the following six hours.

The first attempt to calibrate one of the steam flow transmitter protection channels for the C SG was unsuccessful. Maintenance was not able to adjust this channel's signal comparator card to within the acceptable voltage tolerance. The inability to restore the signal comparator card for this first steam flow transmitter protection channel, along with the other C SG steam flow transmitter protection channel being outside acceptance criteria, led to the TS shutdown.

Event Cause Analysis

Two inoperable steam flow transmitters for the C SG caused the plant to enter LCO 3.0.3. The root cause was that vendor manual instructions had not been captured into site procedures.

Reportability and Safety Assessment

This event is reportable as the completion of a plant shutdown required by Technical Specifications in accordance with 10 CFR 50.73(a)(2)(i)(A).

The 1C SG steam flow transmitter calibration data was obtained and reviewed on 11/17/2016 at 1115. Following review of the data, both 1C SG steam flow transmitters were declared inoperable, and TS 3.0.3 was entered on 11/17/2016 at 1759. Since the data showed that the two channels were inoperable when the data was obtained, Far1ey Unit 1 operated in a condition prohibited by TS from 11/17/2016 at 1815 until TS 3.0.3 was exited on 11/18/2016 at 0418. Therefore, this event is also reportable as an operation or condition prohibited by TS in accordance with 10 CFR 50.73(a)(2){0(8).

Steam flow channels perform a safety function by providing a high steam flow input to main steam line isolation logic circuitry. Each of the three steam generators is equipped with two redundant steam flow transmitters. A high steam flow signal from one of the two steam flow transmitters on two of the three steam generators coincident with a low-low reactor coolant system (RCS) average temperature signal from two of three RCS temperature channels generates a main steam line isolation signal that causes closure of all main steam line isolation valves. This signal is to mitigate the consequences of a main steam line break accident and the resulting rapid depressurization. Having both of the steam flow channels inoperable for the 1 C SG caused a loss of safety function for this signal. Therefore, this is also reportable as an event or condition that could have prevented fulfillment of a Safety Function needed to mitigate the consequences of an accident. in accordance with 10 CFR 50.73(a)(2)(v)(D).

NRC FORM 368A (Q.4.2Dtn Page 2 of 4

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U.S. ..0 EM IREGW.ATORY cc.asSION APPROVED BY OE: NO. 3110-0104

UCENSEE EVENT REPORT (LER) CONTINUATION SHEET

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1. FACIUTY NAIIE 2. DOCKET NUIIBFR

~Joseph M. Farley Nuclear F1miC Unit 1

NARRATIVE

Two additional means of providing a main steam line isolation in the event of a steam line break were available. One was the low-steam-pressure main steam line isolation signal, and the other was 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 reador 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.

Corrective Actions

The signal comparator card was replaced, and the channels were rescaled and restored to operable status. Instructions will be incorporated into currenUy planned work orders for upcoming transmitter calibrations and installations to check and adjust as needed. Also, procedures are being revised to incorporate all missing vendor requirements for all models of Foxboro and Barton transmitters.

Extent of Condition actions involve upcoming outages on both Units 1 and 2. Outage contingency plans will be prepared to allow renorrnalization to be timely to limit the need to shut down the plant in the event an LCO 3.0.3 entry occurs.

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 renorrnalization of Steam Flow Transmitter FT -494 at the beginning of two operating cycles. • 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. • Joseph M. Farley Unit 1LER 2013-003-00 submitted on January 3, 2014 (and 2013-003-01 on February 21, 2014) reported a condition prohibited by Technical Specifications due to the untimely renorrnalization of Steam Flow Transmitter FT -495 at the beginning of an operating cycle.

The last event listed (Unit 1 LER 2013-003-01) was a missed opportunity for the subject event for this LER. The 2013 cause analysis for the out of tolerance steam flow transmitter identified transmitter calibration as a possible contributor and the identified corrective action was an enhancement. That action was not effective in preventing the recurrence. This will be addressed by the Corrective Action Program.

Other systems affected:

Similar necessary information was also missing from Barton transmitter calibration procedures which involved Steam Generator Loop Calibration and Operational Test procedures. Actions to correct this have been entered into the Corrective Adion Program.

NRC FORM 368A (04-2017) Page 3 of 4

U.S. NUCLEAR REGli.ATORY oc.IBSSION APPROVED BY 0118: NO. 3tliO-OtD4 EXPIRES! D3I31I2020

UCENSEE EVENT REPORT (LER) CONTINUATION SHEET

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1. FACILITY HAlE 2. DOCKEr NUMBER

!Joseph M. Farley Nuclear Plant. Unit ' 11::1-1-=:; 1-1 : I NARRATIVE Commitments:

This report contains no licensing commitments.

NRCFORM3884 (114-2017) Page 4 of 4