ML18093A744

LER 88-002-00:on 880218,control Room Indication Identified to Register Approx 5 F Above Wide Range RCS Indication. Caused by Mfg Not Identifying Component Design Mod in Specs. W/880316 Ltr

ML18093A744
Person / Time
Site:	Salem
Issue date:	03/16/1988
From:	Pollack M, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-002-03, LER-88-2-3, NUDOCS 8803220450
Download: ML18093A744 (5)

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• LICENSEE EVENT REPORT (LER)

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• I.a.-""-" fl'-.,,.,._ ~,_ 111W1 1111 bi NO SUIMISllON DATI! 1151 I I I On February 18, 1988 at 0800 'hours the Tavg .control Room indication was identified to register approximately 5° F above the Wide Range Reactor Coolant System {RCS) indication.* *subsequent investigation revealed the resistance compensation circuit for the field wiring length {RTD to the Low Level Amp) was jumpered out not in accordance with design. Therefore, all narrow range Tavg channels were declared inoperable. Technical Specification Table 3.3-3 requires at least 1 Tavg channel in any t~ree {3) ioops to be operable in Modes 1, 2, and 3. If .the Table requirement cannot be met Action .14 must be entered. However, with all channels: declared inoperable, Action 14 could no~ be met, therefore, Technical Specification 3.0.3 was entered at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />. The jumpers we~e removed at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />, on 2/18/88, after a review of applicable prints and recent:! completed design change packages {DCPs). Technical Specification 3.-0.3 was exited upon removal of the jumpers. The root cause has been attributed to the manufacturer not identifying a component design modification in its specifications for that component. The manufacturer of the Low Level Amp has been formally notified of the concerns as documented by this LER. Discussions associated with these concerns are continuing. An INPO "Note Pad" entry addressing the concerns expressed in.this LER will be made. Those Maintenance personnel involved in the installation of the Low Level Amp have been informed of the jumpered connection. The ordering folio for the Low Level Amp will be updated to address the jumpered connection.  ?;'l.-

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e- I LICENSEE EVENT REPORT {LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 88-002-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

W,e,s tinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as (xx}

IDENTIFICATION OF OCCURRENCE:

Tavg Deviation on all channels due to design Event Date: 02/18/88 Report Date: 03/16/88 This report was initiated by Incident Report No.88-058.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 3 Reactor Power 0% - Unit Load 0 MWe DESCRIPTION OF OCCURRENCE:

On February 18, 1988 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> the Tavg Control Room indication f JCJ was identified to register approximately 5° F above the Wide Range Reactor Coolant System (RCS) fABJ indication. Subsequent investigation revealed the resistance compensation circuit for the field wiring length (RTD to the Low Level Amp) wcis jumpered out not in accordan~e with design. Therefore, all narrow range Tavg channels were declared inoperable. Technical Specification Table 3.3-3 requires at least 1 Tavg channel in any three (3) loops to be operable in Modes 1, 2, and 3. *If the Table requirement cannot be met Action 14 must be entered. However, with all channels declared inoperable, Action 14 could not be met, therefore, Technical Specification 3.0.3 was entered at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />.

Technical Specification Table 3.3-3 Action 14 states:

"With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />."

Technical Specification 3.0.3 states:

"When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specificaton does not apply by placing it, as applicable, in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation

LICENSEE EVENT REPORT {LER)' TEXT CONTINUATION Salem Generating Station DOCKET NUMBER . LER NUMBER PAGE Unit 1 5000272 88-002-00 3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd) under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications."

The jumpers were removed at 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />, on February 18, 1988, after a review of applicable prints and recently completed design change packages (DCPs). Technical Specification 3.0.3 was exited upon removal of the jumpers.

APPARENT CAUSE OF OCCURRENCE:

The root cause has been attributed to the manufacturer not identifying a component design modification in its specifications for that component.

A design change to remove the Resistance Temperature Detector (RTD) bypass loop on all four Reactor Coolant {RCS) Loops was completed during the Unit 1 refueling outage just completed. These RTD loops and RTDs were replaced with a direct mounted (in thermowells) narrow range RCS temperature measurement system.

• One of the components

• added was a Low Level Amp {Westinghouse :- "Low Level Amp For RTD Application", .P/N 175511-800) which compensates for signal loss due to the hundreds of feet of distance between the detectors and the racks behind the Control Room. The connector for the Low Level Amp had a pre-installed jumper across the temperature compensation circuit.

The jumpered circuit was not identified, as a problem, prior to entry into Mode 3 {during testing or plant heat-up) because the design change testing requirements did not check the compensation leg for resistance from the terminal strip. Testing was done with the leads

'lifted from the connector thereby preventing indication of the short. Furthermore, the calibration functional test is performed without use of the compensation leg. A single failure (loss of compensation) of a channel would be immediately identified during a channel check under normal circumstances, however, due to the DCR which affected all channels this problem was masked. An additional reason why the jumpered circuit was not identified sooner was that the minimum level for narrow range Tav 9 indication in the Control Room is 530° F.

ANALYSIS OF OCCURRENCE:

The narrow range Tavg RCS temperature measurements are used in trip circuitry (Overtemperature Delta T [OTDT] and Overpower Delta T

[OPDT]}, Engineered Safety Feature Actuation System (ESFAS} and various Control Room alarms (e.g., "RC Loops Tave Deviation",*..**

etc.)

• The OTDT and OPDT ~rips are not required in Mode 3.

LICENSEE EVEN'.l'.REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 88-002-00 4 of 4 ANALYSIS OF OCCURRENCE: (cont'd)

ESFAS is used to actuate Safety Injection, Turbine Trip and Feedwater Isolation for mitigation of certain anticipated design base accidents. One of the design base accidents anticipated in Modes 1, 2, and 3 is a main steam line break. This design ba~e accident is detected, with automatic mitigation, by "Steam Flow in Two Steam Lines High Coincident With Either Tavg Low-Low or Steam Line Pressure Low".

Even though Tavg was indicating 5° F high, main steam line break mitigation would have initiated when required since the "Steam Line Pressure Low" detection capability remained operable. Therefore, this event did not affect the health or safety of the public, however, it is reportable to.the Nuclear Regulatory Commission in accordance with Code of Federal Regulations 10CFR S0.73(a) (2) (i) (B).

CORRECTIVE ACTION:

The jumpers in the temperature compensation circuit for the Low Level Amp were removed and all Tavg channels were declared operable.

The manufacturer of the Low Level Amp has been* formally notified of the concerns as documented by this LER. Discussions associated with these concerns are continuing. Based upon the results of these discussions additional corrective action will be considered.

An INPO "Note Pad" entry addressing the concerns expressed in this LER will be made.

A Salem Unit 2 design change, identical to the Salem Unit 1 design change to remove the RTD bypass loop from the RCS loops, will be performed during the upcoming refueling outage in the fall of 1988.

The design change package testing requirements will be modified to be able to identify problems with the resistance compensation circuit.

Those Maintenance personnel involved in the installation of the Low

,... Level Amp have been informed of the jumpered connection.

The ordering folio for the Low Level Amp will be updated to address the jumpered connection.

(JuJ.Lli l G~era'.!Z:aX : .

Salem Operations MJP:pc SORC Mtg.88-022

OPS~~

• Public Service Electric and Gas Company P.O. Box E Hancocks Br:dge, New Jersey 08038 Salem Generating Station March 16, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 88-002-00 This Licensee Event Report is being submitted pursuant to the requirements of 10CFR 50.73(a) (2) (i) (B). This report is required within thirty (30) days of discovery.

Sincerely yours,

</w~Y.

J. M. Zupko, Jr.

General Manager-Salem Operations MJP:pc Distribution The Energy People 95-2189 (11'.11'2-~~