ML18096A827: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 21: Line 21:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 July 9, 1992 SUPPLEMENTAL LICENSEE EVENT REPORT 91-017-01 This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73. The Apparent Cause of Occurrence and Corrective Action sections have been modified based upon completed Engineering investigations.
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 July 9, 1992 SUPPLEMENTAL LICENSEE EVENT REPORT 91-017-01 This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73. The Apparent Cause of Occurrence and Corrective Action sections have been modified based upon completed Engineering investigations.
MJP:pc Distribution  
MJP:pc Distribution  
...... -.. .** ;-* .** ,. t ' : '* .. j 9207200055 920709 PDR ADOCK 05000272 S PDR Sincerely  
...... -.. .** ;-* .** ,. t ' : '* .. j 9207200055 920709 PDR ADOCK 05000272 S PDR Sincerely
: yours, J,(J_  
: yours, J,(J_
: c. A Vondra General Manager -Salem Operations 95-2189 (lOMJ 12-89 NRC FORM 366 16-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150*0104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LERI ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP*530). U.S. NUCLEAR REGULATORY COMMISSION.
: c. A Vondra General Manager -Salem Operations 95-2189 (lOMJ 12-89 NRC FORM 366 16-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150*0104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LERI ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP*530). U.S. NUCLEAR REGULATORY COMMISSION.
WASHINGTON.DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON.
WASHINGTON.DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON.
Line 29: Line 29:
SEQUENTIAL!::;:::::::
SEQUENTIAL!::;:::::::
REVISION MONTH 1:::::::::::
REVISION MONTH 1:::::::::::
NUMBER ::;:;:::;:;NUMBER DAY YEAR OTHER FACILITIES INVOLVED (8) FACILITY NAMES DOCKET NUMBERISI Salem Unit 2 o 1s101010131111 THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §:(Check one or more of the following)  
NUMBER ::;:;:::;:;NUMBER DAY YEAR OTHER FACILITIES INVOLVED (8) FACILITY NAMES DOCKET NUMBERISI Salem Unit 2 o 1s101010131111 THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §:(Check one or more of the following)
(111 20.402(bl 20.405(cl 50.73(1)(2llivl 73.71lbl ,____ ,_ ,__ 20.406(*111llil 60.38(cll1 I 50.73(1112llvl 73.71 (cl ,__ --,__ 20.405(1111 lliil 50.36(cll21 50.73(a)(2)(viil OTHER in Absrrsct 1---,__ bslow and in Tsxt, NRC Form 20.406(0111  
(111 20.402(bl 20.405(cl 50.73(1)(2llivl 73.71lbl ,____ ,_ ,__ 20.406(*111llil 60.38(cll1 I 50.73(1112llvl 73.71 (cl ,__ --,__ 20.405(1111 lliil 50.36(cll21 50.73(a)(2)(viil OTHER in Absrrsct 1---,__ bslow and in Tsxt, NRC Form 20.406(0111  
)(iii) x 50.73(1)(2llil 366A) --20.405(1111 llivl 50.73(al12lliil 50.7311112llviiil (Bl ,____ -20.4051e)(1  
)(iii) x 50.73(1)(2llil 366A) --20.405(1111 llivl 50.73(al12lliil 50.7311112llviiil (Bl ,____ -20.4051e)(1  
)(v) 50.73(1)(2lliiil 50.73(1)(211*1 LICENSEE CONTACT FOR THIS LER (121 TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) ::::\<:::::::::::::::::  
)(v) 50.73(1)(2lliiil 50.73(1)(211*1 LICENSEE CONTACT FOR THIS LER (121 TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) ::::\<:::::::::::::::::  
'.*'**'. .. ***;*.*;;*:**:-:-:*:  
'.*'**'. .. ***;*.*;;*:**:-:-:*:  
*'.*: MANUFAC* REPORT AB LE :::.;:;:;:;:::;:  
*'.*: MANUFAC* REPORT AB LE :::.;:;:;:;:::;:
:::::::::
:::::::::
MANUFAC* REPORTABLE  
MANUFAC* REPORTABLE  
Line 49: Line 49:
I \::\{: I I I I I I I I I I I I ;:::;:::;:::::::::;:::
I \::\{: I I I I I I I I I I I I ;:::;:::;:::::::::;:::
SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED SUBMISSION DATE 1151 ,. I n YES (If yes. complete EXPECTED SUBMISSION DATE! ABSTRACT (Limir to 1400 sceces, i.e .. accroximsrely fifteen single-scace typewritten lines) (16) On 4/13/91, the 91.6% sustained undervoltage relay's minimum drop out voltage, for all 3 Vital Busses, found to be below the Technical Specification minimum allowable value of 91%. This was discovered during Technical Specification Surveillance 4.3.2.1.1 testing which requires monthly testing of undervoltage relay setpoints.
SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED SUBMISSION DATE 1151 ,. I n YES (If yes. complete EXPECTED SUBMISSION DATE! ABSTRACT (Limir to 1400 sceces, i.e .. accroximsrely fifteen single-scace typewritten lines) (16) On 4/13/91, the 91.6% sustained undervoltage relay's minimum drop out voltage, for all 3 Vital Busses, found to be below the Technical Specification minimum allowable value of 91%. This was discovered during Technical Specification Surveillance 4.3.2.1.1 testing which requires monthly testing of undervoltage relay setpoints.
New procedures  
New procedures
{Sl. MD-FT. 4KV-0001 (Q) ( 0002 or 0003) , "ESFAS Instrumentation Monthly Functional Test-lA {lB or lC) 4KV Vital Bus Under Voltage")
{Sl. MD-FT. 4KV-0001 (Q) ( 0002 or 0003) , "ESFAS Instrumentation Monthly Functional Test-lA {lB or lC) 4KV Vital Bus Under Voltage")
were being used (first use) to support the surveillance testing. The surveillance test was last performed on 1/9/91 using procedure M3T, "Undervoltage and Underfrequency Trip and Time Response Surveillance Test". It had not been performed since 1/9/91 due to ninth refueling outage activities (operability required only in Modes 1, 2, and 3). The causal factors of the setpoint variance are relay design inadequacy and procedure inadequacy.
were being used (first use) to support the surveillance testing. The surveillance test was last performed on 1/9/91 using procedure M3T, "Undervoltage and Underfrequency Trip and Time Response Surveillance Test". It had not been performed since 1/9/91 due to ninth refueling outage activities (operability required only in Modes 1, 2, and 3). The causal factors of the setpoint variance are relay design inadequacy and procedure inadequacy.
Line 61: Line 61:
4 (Hot Standby) 9. Refueling/Maintenance Outage -Plant heat up in progress (outage drawing to a close) DESCRIPTION OF OCCURRENCE:
4 (Hot Standby) 9. Refueling/Maintenance Outage -Plant heat up in progress (outage drawing to a close) DESCRIPTION OF OCCURRENCE:
On April 13, 1991, at 1430, 1700 and 1950 hours (respectively for each Vital Bus), the 91.6% sustained undervoltage relay's minimum drop out trip setp6int voltage, for all three (3) Vital Busses, was found to be below the Technical Spe.cif ication minimum allowable value of 91%. The average trip setpoint was 107.69 VAC (90.3%) and the average reset setpoint was 108.68 VAC (91.4%). This was discovered during monthly Technical Specification Surveillance 4.3.2.1.1 testing of undervoltage relay setpoints.
On April 13, 1991, at 1430, 1700 and 1950 hours (respectively for each Vital Bus), the 91.6% sustained undervoltage relay's minimum drop out trip setp6int voltage, for all three (3) Vital Busses, was found to be below the Technical Spe.cif ication minimum allowable value of 91%. The average trip setpoint was 107.69 VAC (90.3%) and the average reset setpoint was 108.68 VAC (91.4%). This was discovered during monthly Technical Specification Surveillance 4.3.2.1.1 testing of undervoltage relay setpoints.
This testing was not performed during the ninth refueling outage due to system constraints (also, applicability is modes 1, 2, and 3). New procedures Sl.MD-FT.4KV-OOOl(Q)  
This testing was not performed during the ninth refueling outage due to system constraints (also, applicability is modes 1, 2, and 3). New procedures Sl.MD-FT.4KV-OOOl(Q)
(0002 or 0003), "ESFAS Instrumentation Monthly Functional Test-lA (lB or lC) 4KV Vital Bus Under Voltage")
(0002 or 0003), "ESFAS Instrumentation Monthly Functional Test-lA (lB or lC) 4KV Vital Bus Under Voltage")
were being used (first use) for the testing. The surveillance test was last performed on January 9, 1991, using procedure M3T, "Undervoltage and Underfrequency Trip and Time Response Surveillance Test".
were being used (first use) for the testing. The surveillance test was last performed on January 9, 1991, using procedure M3T, "Undervoltage and Underfrequency Trip and Time Response Surveillance Test".
Line 82: Line 82:
The Vital Bus (lE) 70% Loss of Voltage, 91.6% Sustained Degraded Voltage, and 35% Vital Bus Undervoltage Bus Transfer relays monitor the Vital Bus voltage via 35:1 ratio potential transformers (PTs). Each Vital Bus contains one 70% IAV relay three 91.6% Rochester Instrument Systems model PR-2035.Pl-Tl-O relays, and one 35% ITE-27H relay. The 70% and 91.6% relays provide input to the Safeguard Equipment Control (SEC) Systems so the SEC can determine Vital Bus emergency loading requirements.
The Vital Bus (lE) 70% Loss of Voltage, 91.6% Sustained Degraded Voltage, and 35% Vital Bus Undervoltage Bus Transfer relays monitor the Vital Bus voltage via 35:1 ratio potential transformers (PTs). Each Vital Bus contains one 70% IAV relay three 91.6% Rochester Instrument Systems model PR-2035.Pl-Tl-O relays, and one 35% ITE-27H relay. The 70% and 91.6% relays provide input to the Safeguard Equipment Control (SEC) Systems so the SEC can determine Vital Bus emergency loading requirements.
On Aprii 13, 1991, all nine (9) 91.6% relays' as-found trip setpoints were less than the minimum Technical Specification allowable value (91%). The relays were then recalibrated to the 91.6% value specified in the applicable Surveillance Test Procedure Sl. MD-FT. 4KV-0001 (Q) ( 0002 or 0003) . *Recalibration was completed for each relay of each Vital Bus, at the time the out of specification reading was found. All three (3) Vital Busses relays (total of nine relays) were recalibrated on April 13, 1991. An engineering analysis (conducted in support of Salem Unit 2 LER 311/91-005-00) previously determined the impact low as-found 91.6% relay setpoints (90%) would have on Vital Bus motors and loads. For all scenarios, the undervoltage relays would perform their design function and provide adequate protection to Vital Bus motors and loads. The analysis several .scenarios that could result in.low voltage at the 4KV Vital Busses; however, those situations were highly improbable during this* period since the 500 KV grid voltage was 108% of 500 KV and all step down transformers equipped with load tap changers were operable.
On Aprii 13, 1991, all nine (9) 91.6% relays' as-found trip setpoints were less than the minimum Technical Specification allowable value (91%). The relays were then recalibrated to the 91.6% value specified in the applicable Surveillance Test Procedure Sl. MD-FT. 4KV-0001 (Q) ( 0002 or 0003) . *Recalibration was completed for each relay of each Vital Bus, at the time the out of specification reading was found. All three (3) Vital Busses relays (total of nine relays) were recalibrated on April 13, 1991. An engineering analysis (conducted in support of Salem Unit 2 LER 311/91-005-00) previously determined the impact low as-found 91.6% relay setpoints (90%) would have on Vital Bus motors and loads. For all scenarios, the undervoltage relays would perform their design function and provide adequate protection to Vital Bus motors and loads. The analysis several .scenarios that could result in.low voltage at the 4KV Vital Busses; however, those situations were highly improbable during this* period since the 500 KV grid voltage was 108% of 500 KV and all step down transformers equipped with load tap changers were operable.
Therefore, based on the above analysis, tnis event did not affect the health or safety of the public. However, since the Technical Specification requirement for the undervoltage relay setpoint was not met, this event is reportable to the commission in accordance with
Therefore, based on the above analysis, tnis event did not affect the health or safety of the public. However, since the Technical Specification requirement for the undervoltage relay setpoint was not met, this event is reportable to the commission in accordance with
:: . LICENSEE.
:: . LICENSEE.
EVENT REPORT (LER) TEXT CONTINUATION_
EVENT REPORT (LER) TEXT CONTINUATION_

Revision as of 15:59, 25 April 2019

LER 91-017-01:on 910413,sustained Undervoltage Relay Min Drop Voltage Found Below TS Min Allowable Value & Monthly Surveillance Test of Undervoltage Relay Setpoints Not Performed Since 910109.Procedures enhanced.W/920709 Ltr
ML18096A827
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/09/1992
From: POLLACK M J, VONDRA C A
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-017, LER-91-17, NUDOCS 9207200055
Download: ML18096A827 (6)


Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station 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 July 9, 1992 SUPPLEMENTAL LICENSEE EVENT REPORT 91-017-01 This Licensee Event Report supplement is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73. The Apparent Cause of Occurrence and Corrective Action sections have been modified based upon completed Engineering investigations.

MJP:pc Distribution

...... -.. .** ;-* .** ,. t ' : '* .. j 9207200055 920709 PDR ADOCK 05000272 S PDR Sincerely

yours, J,(J_
c. A Vondra General Manager -Salem Operations 95-2189 (lOMJ 12-89 NRC FORM 366 16-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150*0104 EXPIRES: 4/30/92 LICENSEE EVENT REPORT (LERI ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP*530). U.S. NUCLEAR REGULATORY COMMISSION.

WASHINGTON.DC 20555. AND TO THE PAPERWORK REDUCTION PROJECT OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON.

DC 20503. FACILITY NAME (11 n,..,; +-i I DOCKET NUMBER (2) I *PAGE 131 o I 5 I o I o I O I 21 7 12 1 OF O 15 TITLE (41 -Vital Bµs UV Relay Found Below Minimum Tech. Spec.

EVENT DATE 151 MONTH DAY OPERATING MODE (91 POWER LEVEL YEAR l .(101 l 0 0 NAME LER NUMBER 16) REPORT DATE (7) YEAR !'::::::::::

SEQUENTIAL!::;:::::::

REVISION MONTH 1:::::::::::

NUMBER ::;:;:::;:;NUMBER DAY YEAR OTHER FACILITIES INVOLVED (8) FACILITY NAMES DOCKET NUMBERISI Salem Unit 2 o 1s101010131111 THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §:(Check one or more of the following)

(111 20.402(bl 20.405(cl 50.73(1)(2llivl 73.71lbl ,____ ,_ ,__ 20.406(*111llil 60.38(cll1 I 50.73(1112llvl 73.71 (cl ,__ --,__ 20.405(1111 lliil 50.36(cll21 50.73(a)(2)(viil OTHER in Absrrsct 1---,__ bslow and in Tsxt, NRC Form 20.406(0111

)(iii) x 50.73(1)(2llil 366A) --20.405(1111 llivl 50.73(al12lliil 50.7311112llviiil (Bl ,____ -20.4051e)(1

)(v) 50.73(1)(2lliiil 50.73(1)(211*1 LICENSEE CONTACT FOR THIS LER (121 TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) ::::\<:::::::::::::::::

'.*'**'. .. ***;*.*;;*:**:-:-:*:

  • '.*: MANUFAC* REPORT AB LE :::.;:;:;:;:::;:

MANUFAC* REPORTABLE

.*.-.-.-*.* .. -.* -.*: CAUSE SYSTEM COMPONENT TURER TO NPRDS -:-:-:*:::-:::::::::::::::

CAUSE SYSTEM COMPONENT TURER TO NPRDS *.-. .:-:::::::::::::::::::::::::::

f:*::::;:;::;:;

  • .*; *.* .. ; .. ;. (:::: :::::: :)})( -r-------t---r--------t+/-+/-+/-ettf:@1 .... ....
    • :-::*:* *:*:*::*:*

I I I I I I I ??:??}):}'/}

I I I I I I I :::::: :,:,::;: :;::;:: ...........

  • .-:-*:*:

........ :-:::*:*:*:*

I -:-:*>:* :;::::::;::{)

I \::\{: I I I I I I I I I I I I ;:::;:::;:::::::::;:::

SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR EXPECTED SUBMISSION DATE 1151 ,. I n YES (If yes. complete EXPECTED SUBMISSION DATE! ABSTRACT (Limir to 1400 sceces, i.e .. accroximsrely fifteen single-scace typewritten lines) (16) On 4/13/91, the 91.6% sustained undervoltage relay's minimum drop out voltage, for all 3 Vital Busses, found to be below the Technical Specification minimum allowable value of 91%. This was discovered during Technical Specification Surveillance 4.3.2.1.1 testing which requires monthly testing of undervoltage relay setpoints.

New procedures

{Sl. MD-FT. 4KV-0001 (Q) ( 0002 or 0003) , "ESFAS Instrumentation Monthly Functional Test-lA {lB or lC) 4KV Vital Bus Under Voltage")

were being used (first use) to support the surveillance testing. The surveillance test was last performed on 1/9/91 using procedure M3T, "Undervoltage and Underfrequency Trip and Time Response Surveillance Test". It had not been performed since 1/9/91 due to ninth refueling outage activities (operability required only in Modes 1, 2, and 3). The causal factors of the setpoint variance are relay design inadequacy and procedure inadequacy.

Special relay tests show that the relay circuitry is influenced by the amount/type of harmonics present in the external test signal; the relay trip/reset setpoints change on subsequent checks when the test signal contains a different range of harmonics/noise plus the relay's allowable design setpoint drift. For additional root cause and corrective action details refer to LER 311/91-008-01.

  • Contributing factors to the cause of this event are test equipment inaccuracies and test methodology.

Procedure enhancements have been made to address human factor and test methodology concerns found during System Engineering's investigation.

NRC Form 366 (6-891 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

-Pressurized Water Reactor LER NUMBER 91-017-01 PAGE 2 of 5 Energy Industry Identification System (EIIS) codes are identified in . the text as {xx}. IDENTIFICAT.ION OF OCCURRENCE:

The Vital Bus 91.6%*undervoltage relay setpoints (all three busses) were found below the minimum Technical Specification allowable value Event Date: 1/9/91 Discovery Date: 4/13/91 Report Date: 7/9/92 This report was initiated by Incident Report Nos.91-265, 91-266, and 91-267. CONDITIONS PRIOR TO OCCURRENCE:

4 (Hot Standby) 9. Refueling/Maintenance Outage -Plant heat up in progress (outage drawing to a close) DESCRIPTION OF OCCURRENCE:

On April 13, 1991, at 1430, 1700 and 1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br /> (respectively for each Vital Bus), the 91.6% sustained undervoltage relay's minimum drop out trip setp6int voltage, for all three (3) Vital Busses, was found to be below the Technical Spe.cif ication minimum allowable value of 91%. The average trip setpoint was 107.69 VAC (90.3%) and the average reset setpoint was 108.68 VAC (91.4%). This was discovered during monthly Technical Specification Surveillance 4.3.2.1.1 testing of undervoltage relay setpoints.

This testing was not performed during the ninth refueling outage due to system constraints (also, applicability is modes 1, 2, and 3). New procedures Sl.MD-FT.4KV-OOOl(Q)

(0002 or 0003), "ESFAS Instrumentation Monthly Functional Test-lA (lB or lC) 4KV Vital Bus Under Voltage")

were being used (first use) for the testing. The surveillance test was last performed on January 9, 1991, using procedure M3T, "Undervoltage and Underfrequency Trip and Time Response Surveillance Test".

  • The as-found condition of the Bus relays potentially placed the Unit outside its design basis. To be conservative, the Nuclear Regulatory Commission was notified of this event on April 14, 1991, at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> in accordance with Code of Federal Regulations lOCFR 5 0. 7 2 ( b) ( 1) (ii') ( B) .

LICENSEE EVENT REPORT (LER) .* TEXT CONTINUATION Salem Generating Station Unit 1 APPARENT CAUSE OF OCCURRENCE:

DOCKET NUMBER 5000272 LER NUMBER. 91-017-01 PAGE 3 of 5 The causal factors of the setpoint variance are relay design inadequacy and procedure inadequacy.

Special relay tests show that the relay circuitry is influenced by the amount/type of harmonics present in the external test signal; the relay trip/reset setpoints change on subsequent checks when the test signal contains a different amount/type of harmonics/noise plus the relay's allowable design setpoint drift. For additional details refer to LER Contributing factors, to the cause of this event, include test equipment inaccuracies and test methodology.

Procedure M3T did not define the different test equipment setups or specify*the test equipment required to support each type of undervoltage or underfrequency relay test. As explained below, personnel error did not contribute to this.event as.was the case for a similar Unit 2 event (reference LER 311/91-005-01).

The Unit 1 calibration (January 9, 1991) had taken place prior to the Unit 2 event. When the relay's trip/reset setpoints were checked on January 9, 1991, the variable power supply's output voltage was varied using thumb-wheel switches.

These switches have increments of 0.1 VAC. Although the procedure required verification of settings using a DVM (good to 0.01 VAC), the recorded data indicated that the trip/reset setpoints were determined by reading the thumb-wheel switch settings.

When the relay's trip/reset setpoints were checked on April 13, 1991* in accordance with new procedures, the thumb-wheel switches were set to 115 VAC and relay input voltage was adjusted using a variable resistor network. The variable resistor network provided 0.01 VAC increments instead of the previous thumb-whee*1 method of O. 1 VAC. Since the trip/reset setpoints indicated.

on the DVM were more accurate, this method verified that additional variable power supply calibration and thumb-wheel switch tolerances contributed to the error. When the as-found setpoint (on January 9, 1991) was not within M3T's administra.tive setpoint span, the relay was recalibrated as follows: the thumb-wheel switches were set to 108.9 VAC and the relay's "Low Trip" potentiometer was adjusted until the red LED illuminated.

Then the thumb-wheel switches were set to 110.0 VAC and the relay's "Low Trip Deadband" potentiometer was adjusted until the red LED extinguished.

The thumb-wheel switches were changed between the required trip and reset voltage to verify proper setpoint actuation.

Since M3T's test methodology added the variable power supply's calibration tolerance to the relay's normal monthly setpoint drift, the relay setpoint was set at a lower voltage than M3T's

  • administrative setpoint spans of 108.75 VAC -109.05 VAC and 109.85 . I VAC -110.15 VAC, respectively.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 APPARENT CAUSE OF OCCURRENCE:

DOCKET NUMBER 5000272 (cont'd) LER NUMBER 91-017-01 PAGE 4 of 5 On April 22, 1991, a special test was performed using the January 9,* 1991 variable power supply, the other variable power supply used on April 13, 1991, and a spare 91.6% relay. Test results showed that when the relay trip/reset setpoints were set using the thumb-wheel switches, the as-found setpoints using the DVM and variable resistor network were 0.53 VAC and 0.62 VAC lower respectively.

When either va.riable power supply was used to set relay setpoints using the new procedure method, the as-found setpoints were within 0.01 VAC and 0.02 VAC. Based on the worst case.relay drift found during three (3) weekly tests performed on Unit 2 relays (0-.56 VAC), DVM calibration error (0.21), and the special test results above (0.53 VAC), the total trip setpoint drift on April 13, 1991 col,lld have been as much as 1.30 VAC lower compared to the April 13, 1991 average Unit 1 as-found trip setpoint of 1.21 VAC. ANALYSIS OF OCCURRENCE:

The Vital Bus (lE) 70% Loss of Voltage, 91.6% Sustained Degraded Voltage, and 35% Vital Bus Undervoltage Bus Transfer relays monitor the Vital Bus voltage via 35:1 ratio potential transformers (PTs). Each Vital Bus contains one 70% IAV relay three 91.6% Rochester Instrument Systems model PR-2035.Pl-Tl-O relays, and one 35% ITE-27H relay. The 70% and 91.6% relays provide input to the Safeguard Equipment Control (SEC) Systems so the SEC can determine Vital Bus emergency loading requirements.

On Aprii 13, 1991, all nine (9) 91.6% relays' as-found trip setpoints were less than the minimum Technical Specification allowable value (91%). The relays were then recalibrated to the 91.6% value specified in the applicable Surveillance Test Procedure Sl. MD-FT. 4KV-0001 (Q) ( 0002 or 0003) . *Recalibration was completed for each relay of each Vital Bus, at the time the out of specification reading was found. All three (3) Vital Busses relays (total of nine relays) were recalibrated on April 13, 1991. An engineering analysis (conducted in support of Salem Unit 2 LER 311/91-005-00) previously determined the impact low as-found 91.6% relay setpoints (90%) would have on Vital Bus motors and loads. For all scenarios, the undervoltage relays would perform their design function and provide adequate protection to Vital Bus motors and loads. The analysis several .scenarios that could result in.low voltage at the 4KV Vital Busses; however, those situations were highly improbable during this* period since the 500 KV grid voltage was 108% of 500 KV and all step down transformers equipped with load tap changers were operable.

Therefore, based on the above analysis, tnis event did not affect the health or safety of the public. However, since the Technical Specification requirement for the undervoltage relay setpoint was not met, this event is reportable to the commission in accordance with

. LICENSEE.

EVENT REPORT (LER) TEXT CONTINUATION_

Salem Generating Station Unit 1 DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCE: (cont'd) LER NUMBER 91-017-01 Code of Federal Regulations lOCFR 50.73(a) (2) (i} (B). CORRECTIVE ACTION: PAGE _5 of 5 For specific details as to the corrective actions taken which address the relay's design inadequacy, refer to LER 311/91-008-01.

As indicated previously, the new relay test procedures are unit and bus specific.

The new test procedures:

1} include a test equipmen_t connection diagram for each type of relay test; 2) use a variable resistor network to provide 0.01 VAC input voltage increments; 3} increase the minimum administrative trip setpoint from 108.75 VAC to 108.90 VAC; and 4) measure relay input voltage at the relay terminals.

Additional procedure enhancements have been made to address other human factor and test methodology concerns found during System Engineering's inyestigation.

MJP:pc SORC Mtg.92-076 *@ -General Manager -Salem Operations I