05000272/LER-2015-002

LER-2015-002, Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

Salem Generating Station - Unit 1
Event date:	02-12-2015
Report date:	11-16-2016
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2722015002R02 - NRC Website

LER 15-002-002 for Salem, Unit 1, Regarding Condition Prohibited by Technical Specification for One Channel of Steam Generator Level Indication Inoperable

ML16321A389
Person / Time
Site:	Salem
Issue date:	11/16/2016
From:	Grover F K Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N16-0216 LER 15-002-002
Download: ML16321A389 (5)

0001, or by internet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

PLANT AND SYSTEM IDENTIFICATION

Westinghouse-Pressurized Water Reactor {PWR/4} Steam Generator Level Transmitter {JE/LT}

IDENTIFICATION OF OCCURRENCE

Event Date: 02/12/2015 Discovery Date: 02/12/2015

CONDITIONS PRIOR TO OCCURRENCE

Salem Unit 1 was in Operation Mode 1, operating at approximately 100% power. No additional structures, systems, or components were inoperable at the time of discovery that contributed to this event.

DESCRIPTION OF OCCURRRENCE

On April 11, 2013, a new level transmitter was installed for 11 SG, Channel 2, 1LT519 as part of a planned 10 year replacement program.

On August 5, 2014, control room operators identified 1LT519 indication as drifting high and approaching the 3 percent level deviation limit but not exceeding the TS level channel limit.

On October 10, 2014, at 1014, troubleshooting of 1LT519 identified the transmitter as high outside its TS calibration acceptance criteria. The transmitter was calibrated and returned to service.

On February 12, 2015, a past functionality evaluation was completed for 1LT519. The evaluation, based on drift trending, concluded that the best estimate for when 1LT519 would have exceeded its TS calibration acceptance criteria was on August 19, 2013, approximately 130 days after its installation on April 11, 2013.

The subsequent surveillance test performed on February 26, 2015 met its TS acceptance criteria. 1LT519 was subsequently replaced on March 27, 2015.

Salem Unit 1 TS 3.3-1, Action 6 requires that startup or power operation may continue with an inoperable SG level channel provided it is placed in a tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1LT519 would have exceeded its TS acceptance criteria on August 19, 2013 and was not placed in a tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> as required by TS.

This event is reported in accordance with 10CFR50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications...

0001, or by internet e-mail to I nfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

CAUSE OF EVENT

The cause of the SG protection level channel drifting was due to premature failure of its level transmitter due to a manufacturing defect. Vendor testing confirmed that a center diaphragm oil leak was the cause of the transmitter output drift. The completion of the past functionality review was delayed and not completed until February 12, 2015 due to lack of timeliness guidance in the past functionality evaluation process.

SAFETY CONSEQUENCES AND IMPLICATIONS

The safety significance of this event is minimal. This event did not result in any offsite release of radioactivity or increase of offsite dose rates, and there were no personnel injuries or damage to any other safety-related equipment.

The remaining two 11SG level protection channels were functional and their SG LO-LO Level protective trip functions remained capable of generating a reactor trip signal during the time in which 1LT519 was inoperable.

SAFETY SYSTEM FUNCTIONAL FAILURE

A review of this event determined that a Safety System Functional Failure (SSFF) as defined in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline, did not occur. This event did not prevent the ability of a system to fulfill its safety function to either shutdown the reactor, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident.

PREVIOUS EVENTS

A review of previous events for the past three years identified no other similar events.

CORRECTIVE ACTIONS

1. 1LT519 was replaced and returned to service.

2. Failure analysis was performed on the failed 1LT519 level transmitter.

3. Guidance has been added to the engineering technical evaluation procedure for past operability and functionality reviews to ensure reporting requirements are properly supported.

COMMITMENTS

This LER contains no regulatory commitments.