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| | issue date = 09/04/1987 | | | issue date = 09/04/1987 |
| | title = LER 87-019-00:on 870807,manual Reactor Trip Initiated Following Short Rampdown Due to Loss of Cooling & Oil Flow for Main Transformer B.Caused by Failed Undervoltage Relay. Relay & Local Annunciator Panel replaced.W/870904 Ltr | | | title = LER 87-019-00:on 870807,manual Reactor Trip Initiated Following Short Rampdown Due to Loss of Cooling & Oil Flow for Main Transformer B.Caused by Failed Undervoltage Relay. Relay & Local Annunciator Panel replaced.W/870904 Ltr |
| | author name = BENSON D L | | | author name = Benson D |
| | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:* -----.. ,: ............ | | {{#Wiki_filter:. . ,:............ -.*.-*,,,*J.v..'",.. ~ ..........-*.*.~--~-*-**--*--***- .* : . ._. |
| -.*.-*,,,*J.v..'", .. .......... | | POW 01 |
| -*.*.~--~-*-**--*--***- | | * ~'\IRC Fo;m 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83) |
| .* : . ._. POW 01 ~'\IRC Fo;m 366 (9-83) U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB. NO. 3160-0104 EXPIRES: 8/31188 LICENSEE EVENT REPORT (LER) FACILITY NAME (1) Surry Power Station,* | | APPROVED 0MB. NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31188 FACILITY NAME (1) |
| Unit. 1 TITLE (4) Manual Reactor Trip Due To Failed Relay In Main Transformer EVENT DATE (6) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) MONTH DAY YEAR YEAR }ft MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) o I E ol 7 s 7 s 11 -o I 1 I 9 -o I o o I 9 o 14 a I 1 01s1010101 I I OPERATING MOOE (9) N THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or moro of tho fol/ovyin11} | | Surry Power Station,* Unit. 1 TITLE (4) |
| (11) 20.402(b) 20.405(0) | | Manual Reactor Trip Due To Failed Relay In Main Transformer EVENT DATE (6) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| X 60.73(o)(21(iv) 73.71(b) POWER I O I 9 -1 8 ----20.4051*)(1 )Ii) 60.38(c)(1) 60.73l*ll2llv) 73.711c) ---20.405(1)11 )Iii) 60.38(c)(2) 60.73(1)(Z)(viil OTHER (Sf)fJClfy In Ab1tn1ct -lulow *nd In T*1tt, NRC Form -11111= -20.405(1)11 | | MONTH DAY YEAR YEAR }ft SE~~~~~~AL tr~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) oI E ol 7 s 7 s 11 - o I 1I9 - oI o o I 9 o 14 aI1 01s1010101 I I THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or moro of tho fol/ovyin11} (11) |
| )(ill) 60.73(1)12)11) 60.73(1)(Z)(v1U)(A) 366A} --2Q.406(1)(1 | | OPERATING MOOE (9) |
| )(Iv) 60.73(1)12)111) 60.7311l12llvlll)(B) | | N I |
| ---20.405(1111)(¥)
| | 20.402(b) 20.405(0) X 60.73(o)(21(iv) 73.71(b) 20.4051*)(1 )Ii) 60.38(c)(1) 60.73l*ll2llv) 73.711c) |
| 60.73(1)12)1111) 60.7311l12llx) | | POWER L~~~L O I 9 -1 8 - 20.405(1)11 )Iii) 60.38(c)(2) 60.73(1)(Z)(viil OTHER (Sf)fJClfy In Ab1tn1ct lulow *nd In T*1tt, NRC Form 11111= |
| LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER AREA CODE D. L. Benson Station Manaaer 8 I O 14 31 517 1 *-1 31 11 RI ll COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) CAUSE SYSTEM COMPONENT . TURER R~~o~~:gkE i!iil!i!i!i!i!i!i!ii!ii!i!i!iii!i!i!i!i!i!i!i!i!ill!l CAUSE SYSTEM COMPONENT MANUFAC-. | | 20.405(1)11 )(ill) 60.73(1)12)11) 60.73(1)(Z)(v1U)(A) 366A} |
| TURER y i= I I IY I CIA~ IR r. I n I~ I n V li!iiiiiiii!i!i!i!i!i!iiii!i!ilillilillli!ililiiliili I I I I I I I i!!lli!i!l!ill!lil!i!i!i!i!iii!l!iii!i!i!i!i!i!ii!ili SUPPLEMENTAL REPORT EXPECTED 114) n YES /If v*s. compl*t* EXPECTED SUBMISSION DATE/ ABSTRACT (Limit to 1400 spoc*s, i,o,, oppro1timote/y fift**n 1Jn11f*-spoc* | | 2Q.406(1)(1 )(Iv) 60.73(1)12)111) 60.7311l12llvlll)(B) 20.405(1111)(¥) 60.73(1)12)1111) 60.7311l12llx) |
| typewritten linos} 116) I I I I I I I I I I I I I I EXPECTED SUBMISSION DATE (15) 'lllli!liiiili!ilili!i!iliiiiiiiiiliii::ii:iiililiii MONTH DAY YEAR I I I On August 7, 1987 at 0120 hours, with the unit at approximately 98% power, a manual reactor trip was initiated, following a short rampdown, due to loss of cooling and oil flow for the 'B' Main Transformer | | LICENSEE CONTACT FOR THIS LER (12) |
| | NAME TELEPHONE NUMBER AREA CODE D. L. Benson Station Manaaer 8 I O14 31 517 1*-1 31 11 RI ll COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113) |
| | MANUFAC- MANUFAC-. |
| | CAUSE SYSTEM COMPONENT . TURER R~~o~~:gkE i!iil!i!i!i!i!i!i!ii!ii!i!i!iii!i!i!i!i!i!i!i!i!ill!l CAUSE SYSTEM COMPONENT TURER y i= I I IY I CIA~ IR r. I n I~ I n V li!iiiiiiii!i!i!i!i!i!iiii!i!ilillilillli!ililiiliili I I I I I I I I I I I I I I i!!lli!i!l!ill!lil!i!i!i!i!iii!l!iii!i!i!i!i!i!ii!ili I I I I I I I 'lllli!liiiili!ilili!i!iliiiiiiiiiliii::ii:iiililiii SUPPLEMENTAL REPORT EXPECTED 114) MONTH DAY YEAR EXPECTED n YES /If v*s. compl*t* EXPECTED SUBMISSION DATE/ |
| | ABSTRACT (Limit to 1400 spoc*s, i,o,, oppro1timote/y fift**n 1Jn11f*-spoc* typewritten linos} 116) |
| | SUBMISSION DATE (15) |
| | I I I On August 7, 1987 at 0120 hours, with the unit at approximately 98% power, a manual reactor trip was initiated, following a short rampdown, due to loss of cooling and oil flow for the 'B' Main Transformer {EIIS-XFMR}. The transformer local annunciator panel {EIIS-ANN} had failed to initiate a TROUBLE alarm on the control room annunciator panel. Following ihe trip, all control and protection systems functioned properly except: - One channel of source range nuclear instrumentation (SR NI) {EIIS-IG} did not automatically reinstate. - The 'A' main feedwater pump (MFP) {EIIS-P} did not automatically trip and the pump's minimum flow recirc. valve did not open on a low feedwater flow condition. |
| | Operators manually reinstated the SR NI and tripped the 'A' MFP. The unit was quickly stabilized at hot shutdown. Power was lost to the 'B' Main Transformer cooling fans and oil circulating pumps when an undervoltage relay {EIIS-RLY} in |
| | *the cooling control circuit failed. The relay and annunciator panel failures are attributed to aging. One channel of SR NI failed to reinstate due to under-compensation of one channel of IR NI. The 'A' MFP did not trip and its minimum flow recirc. valve did not open due to a failed air regulator diaphragm to the pneumatic pressure switch which senses main feedwater flow. The failed relay and the local annunciator panel were replaced. The transformer was checked for winding or other internal damage and was determined to be undamaged. Since the relay and annunciator failures are attributed to aging, additional transformer circuit components susceptible to failures due to their age will be identified~O-,, |
| | and replaced. |
| | 8709100301 8 ~ 2 8 1e ,i,"L J I |
| | :DR ADOCK O PDRO NRC Form 361:l |
| | |
| | POW 28-06-01 NRC Form 31141A e e U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT.REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150--0104 EXPIRES: B/31 /111 FACILITY NAME 111 DOCKET NUMBER (21 L!,R NUMBER UII PAGE (31 VEAR :::::::::: SEQUENTIAL .. '' REVISION |
| | ::::;:::;: NUMBER .. :... NUMBER Surry Power Station, Unit 1 o 15 Io Io IO I 2 IR In RI .7 - n I , I a - n In *nl ., OF n I ,, |
| | TEXT ,,, - - a ,eqund, u* .<<lltioMI NRC Fann ......, 1171 1.0 Description of the Event on August 7, 1987 at 0120 hours, with tbe unit at approximately 98% power, a manual reactor trip was initiated, following a short rampdown, due to loss of cooling and oil flow for the 'B' Main Transformer |
| {EIIS-XFMR}. | | {EIIS-XFMR}. |
| The transformer local annunciator panel {EIIS-ANN}
| | During his rounds, the outside plant operator noticed the cooling fans for the 'B' Main Transformer were stopped and that oil was flowing from a relief valve on the transformer. He informed the Shift Supervisor and the decision was made to initiate a rampdown and, subsequently, a manual reactor trip to prevent trans.former damage due to overheating. The transformer local annunciator panel {EIIS-ANN} had failed to initiate a TROUBLE alarm on the control room annunciator panel. |
| had failed to initiate a TROUBLE alarm on the control room annunciator panel. Following ihe trip, all control and protection systems functioned properly except: -One channel of source range nuclear instrumentation (SR NI) {EIIS-IG}
| | Immediately following the trip, all control and protection systems functioned properly except: |
| did not automatically reinstate.
| | One channel of source range nuclear instrumentation (SR NI) {EIIS-IG} did not automatically reinstate due to under-compensation of one channel of intermediate range (IR NI) {EIIS-IG}, and the 'A' main feedwater pump (MFP) {EIIS-P} |
| -The 'A' main feedwater pump (MFP) {EIIS-P} did not automatically trip and the pump's minimum flow recirc. valve did not open on a low feedwater flow condition.
| | did not automatically trip and* the pump's minimum flow recirc. valve did not open on a low feedwater flow cond~tion. |
| Operators manually reinstated the SR NI and tripped the 'A' MFP. The unit was quickly stabilized at hot shutdown.
| | 2.0 Safety Consequences and Implications A manual reactor trip from full power is well within the bounds of the UFSAR safety and accident analyses and all safety related and other systems required to shut the plant down safely functioned as designed. |
| Power was lost to the 'B' Main Transformer cooling fans and oil circulating pumps when an undervoltage relay {EIIS-RLY}
| | Therefore, this event did not constitute an unreviewed safety question and the health and safety of the public were not affected. |
| in *the cooling control circuit failed. The relay and annunciator panel failures are attributed to aging. One channel of SR NI failed to reinstate due to compensation of one channel of IR NI. The 'A' MFP did not trip and its minimum flow recirc. valve did not open due to a failed air regulator diaphragm to the pneumatic pressure switch which senses main feedwater flow. The failed relay and the local annunciator panel were replaced.
| | NRC FORM 3S6A |
| The transformer was checked for winding or other internal damage and was determined to be undamaged.
| | * U.S.GPO: 1988-0-624*538/466 19-831 |
| Since the relay and annunciator failures are attributed to aging, additional transformer circuit components susceptible to failures due to their age will be identified~O-,, and replaced.
| |
| 1 e ,i,"L I J 8709100301 8~28 :DR ADOCK O PDRO NRC Form 361:l NRC Form 31141A (9-831 FACILITY NAME 111 POW 28-06-01 e e LICENSEE EVENT.REPORT (LER) TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150--0104 EXPIRES: B/31 /111 DOCKET NUMBER (21 VEAR L!,R NUMBER UII ::::::::::
| |
| SEQUENTIAL
| |
| .. '' REVISION ::::;:::;:
| |
| NUMBER .. : ... NUMBER PAGE (31 Surry Power Station, Unit 1 o 15 Io Io IO I 2 IR In RI .7 -n I , I a -n In *nl ., OF n I ,, TEXT ,,, --a ,eqund, u* .<<lltioMI NRC Fann ...... , 1171 NRC FORM 3S6A 19-831 1.0 Description of the Event on August 7, 1987 at 0120 hours, with tbe unit at approximately 98% power, a manual reactor trip was initiated, following a short rampdown, due to loss of cooling and oil flow for the 'B' Main Transformer
| |
| {EIIS-XFMR}.
| |
| During his rounds, the outside plant operator noticed the cooling fans for the 'B' Main Transformer were stopped and that oil was flowing from a relief valve on the transformer. | |
| He informed the Shift Supervisor and the decision was made to initiate a rampdown and, subsequently, a manual reactor trip to prevent trans.former damage due to overheating. | |
| The transformer local annunciator panel {EIIS-ANN} | |
| had failed to initiate a TROUBLE alarm on the control room annunciator panel. Immediately following the trip, all control and protection systems functioned properly except: One channel of source range nuclear instrumentation (SR NI) {EIIS-IG} | |
| did not automatically reinstate due to under-compensation of one channel of intermediate range (IR NI) {EIIS-IG}, and the 'A' main feedwater pump (MFP) {EIIS-P} did not automatically trip and* the pump's minimum flow recirc. valve did not open on a low feedwater flow cond~tion. | |
|
| |
|
| ===2.0 Safety===
| | ~- ~ ... _,,,, __._,_ .... ~ *- ...._...... **-**-'**---*,:.. *-*- |
| Consequences and Implications A manual reactor trip from full power is well within the bounds of the UFSAR safety and accident analyses and all safety related and other systems required to shut the plant down safely functioned as designed.
| | POW 28-06-01 NRC Form 3118A e U.S. NUCLEAR REGULATORY ~OMMISSION 19-831 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED 0MB NO. 3150~104 EXPIRES: 8/31/111 FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER (Ill PAGE (31 VEAR Surrv Power Station Unit 1 o 1s Io Io Io I 218 IO 81 7 - Ol 119 - OI C OI 3 OF O14 TEXT (If""""~ o ,eqund, u* IMldllioMI NRC Form :m.1'1/ 1171 |
| Therefore, this event did not constitute an unreviewed safety question and the health and safety of the public were not affected.
| | : 3. 0 , Cause Power was lost to the 'B' Main Transformer cooling fans and oil circulating pumps when an undervoltage relay |
| * U.S.GPO: 1988-0-624*538/466 NRC Form 3118A 19-831 FACILITY NAME (11 ~-... _,,,, __ ._,_ .... *-.... _ ...... **-**-'**---*,:
| | {EIIS-RLY} in the cooling control circuit failed. The relay and annunciator panel failures are attributed to aging. Without cooling, the transformer began to overheat and oil pressure increased causing the relief valve to lift. |
| .. *-*-e LICENSEE EVENT REPORT ILER) TEXT CONTINUATION DOCKET NUMBER (2) VEAR POW 28-06-01 U.S. NUCLEAR REGULATORY | | One channel of SR NI failed to reinstate due to under compensation of one channel of IR NI. |
| ~OMMISSION APPROVED 0MB NO. 3150~104 EXPIRES: 8/31/111 LER NUMBER (Ill PAGE (31 Surrv Power Station Unit 1 o 1s Io Io Io I 218 IO 81 7 -Ol 119 -O I C OI 3 OF O 14 TEXT (If""""~ o ,eqund, u* IMldllioMI NRC Form :m.1'1/ 1171 NRC FORM 366A 19-83) 3. 0 , Cause Power was lost to the 'B' Main Transformer cooling fans and oil circulating pumps when an undervoltage relay {EIIS-RLY} | | The 'A' MFP did not trip and its minimum flow recirc. |
| in the cooling control circuit failed. The relay and annunciator panel failures are attributed to aging. Without cooling, the transformer began to overheat and oil pressure increased causing the relief valve to lift. One channel of SR NI failed to reinstate due to under compensation of one channel of IR NI. The 'A' MFP did not trip and its minimum flow recirc. valve did not open because they failed to receive the low feedwater flow signal. The air regulator to the pneumatic pressure switch which senses main feedwater flow was found to have a ruptured diaphragm. | | valve did not open because they failed to receive the low feedwater flow signal. The air regulator to the pneumatic pressure switch which senses main feedwater flow was found to have a ruptured diaphragm. This resulted in an erroneous high feedwater flow signal in the MFP/recirc. valve logic circuit. |
| This resulted in an erroneous high feedwater flow signal in the MFP/recirc. | | 4.0 Immediate Corrective Action Control room operators manually reinstated the SR NI and tripped the 'A' MFP. Appropriate plant procedures were followed .and the unit was quickly stabilized at hot shutdown conditions. The Shift Technical Advisor performed critical safety function status tree reviews to ensure plant parameters were observed and maintained within safe limits. |
| valve logic circuit. 4.0 Immediate Corrective Action Control room operators manually reinstated the SR NI and tripped the 'A' MFP. Appropriate plant procedures were followed .and the unit was quickly stabilized at hot shutdown conditions. | | 5.0 Additional Corrective Actions The Main Transformer cooling circuit under voltage relay and the local annunciator panel were replaced. |
| The Shift Technical Advisor performed critical safety function status tree reviews to ensure plant parameters were observed and maintained within safe limits. 5.0 Additional Corrective Actions The Main Transformer cooling circuit under voltage relay and the local annunciator panel were replaced. | |
| The transformer was checked for winding or other internal damage and was determined to be undamaged based on an oil analysis and a high potential winding continuity test. | | The transformer was checked for winding or other internal damage and was determined to be undamaged based on an oil analysis and a high potential winding continuity test. |
| * Compensating voltage was adjusted on the IR NI and the air regulator diaphragm for the feedwater flow pressure switch was replaced. | | * Compensating voltage was adjusted on the IR NI and the air regulator diaphragm for the feedwater flow pressure switch was replaced. The 'A' MFP trip and recirculation valve logic circuit was tested to ensure proper operation. |
| The 'A' MFP trip and recirculation valve logic circuit was tested to ensure proper operation. | | NRC FORM 366A |
| * U.S.GPO: 1988*0-1124*538/465 | | * U.S.GPO: 1988*0-1124*538/465 19-83) |
| ... NRC Form 3811A 19-831 FACILITY NAME 111 . '.*,,,., .. ,.--.,-*,.~-*
| | |
| ,_,,,*..:.,.*.~-~--**---**:-. | | . '.*,,,., .. ,.--.,-*,.~-* ,_,,,*..:.,.*.~-~--**---**:-. .... _; - ---** |
| .... _; ----** | | NRC Form 3811A 19-831 FACILITY NAME 111 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER 121 e |
| * e POW 28-06-01 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31 /BB DOCKET NUMBER 121 YEAR LER NUMIIER 1111 **********
| | POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION LER NUMIIER 1111 APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31 /BB PAGE (31 YEAR ********** SEQUENTIAL -:*:*:*:*:* REVISION |
| SEQUENTIAL | | .......... NUMBER * ..... NUMIIER Surry Power Station. Unit 1 01s101010121slo1Rl7 -nl, b -1nh- nJllOFn ILI TEXT 1/f - - II ,equltw/, ua .,,,,,,.,,_ NRC .Fann .-.,.*,1 1171 6.0 *Actions Taken To Prevent Recurrence Preventive maintenance was performed on the three main transformers. Since the relay and annunciator failures were attributed to aging, additional transformer control and protection circuit components susceptible to failures due to their age will be identified and* |
| -:*:*:*:*:* | | replaced. |
| REVISION ..........
| | 7.0 Similar Events None. |
| NUMBER * ..... NUMIIER PAGE (31 Surry Power Station. Unit 1 01s101010121slo1Rl7 -nl, b -1nh-nJllOFn ILI TEXT 1/f --II ,equltw/, ua .,,,,,,.,,_ | | 8.0 Manufacturer/Model Number Transformer: General Electric Single ~hase Step-up Power Transformer Failed Relay: General Electric CR120E UV re-lay. |
| NRC .Fann .-.,.*,1 1171 NRC FORM 366A 19-831 6.0 *Actions Taken To Prevent Recurrence Preventive maintenance was performed on the three main transformers. | | NRC FORM 366A 19-831 |
| Since the relay and annunciator failures were attributed to aging, additional transformer control and protection circuit components susceptible to failures due to their age will be identified and* replaced. | | * U.S.GP0:19B6-0-624*536/4_55 |
|
| |
|
| ===7.0 Similar===
| | \ |
| Events None. 8.0 Manufacturer/Model Number Transformer:
| | e - |
| General Electric Single ~hase Step-up Power Transformer Failed Relay: General Electric CR120E UV re-lay.
| | VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 315 Surry, Virginie 23883 September 4, 1987 U.S. Nuclear Regulatory Commission Serial No.: 87-021 Document Control Desk Docket No. : .50-280 |
| * U.S.GP0:19B6-0-624*536/4_55
| | .016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen: |
| '* \ e September 4, 1987 U.S. Nuclear Regulatory Commission Document Control Desk .016 Phillips Building Washington, D.C. 20555 Gentlemen:
| | Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1. |
| -VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 315 Surry, Virginie 23883 Serial No.: 87-021 Docket No. : .50-280 Licensee No.: DPR-32 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1. REPORT NUMBER 87-019-00 This report ha.s been reviewed by the Station Nuclear Safety and Operating COIIIJ!littee and will be reviewed by Safety Evaluation and Control.
| | REPORT NUMBER 87-019-00 This report ha.s been reviewed by the Station Nuclear Safety and Operating COIIIJ!littee and will be reviewed by Safety Evaluation and Control. |
| * Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323}} | | * Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323}} |
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LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
ML18153A2201998-02-0606 February 1998
LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr
ML18153A2071998-01-13013 January 1998
LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors
ML18153A2101998-01-13013 January 1998
LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status
ML18153A1911997-11-26026 November 1997
LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised
ML18153A1971997-11-26026 November 1997
LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset
ML18153A1921997-11-25025 November 1997
LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr
ML18153A1831997-11-12012 November 1997
LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause
ML18153A1791997-11-0707 November 1997
LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
ML18153A1721997-10-30030 October 1997
LER 97-007-00:on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage
ML18153A1421997-06-10010 June 1997
LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr
ML18153A1391997-05-28028 May 1997
LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
ML18153A1291997-04-18018 April 1997
LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr
ML18153A1281997-04-15015 April 1997
LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr
ML18153A1241997-04-0808 April 1997
LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr
ML18153A1191997-03-19019 March 1997
LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr
ML18153A1201997-03-19019 March 1997
LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:RO)
MONTHYEARML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
ML18153A2201998-02-0606 February 1998
LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr
ML18153A2071998-01-13013 January 1998
LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors
ML18153A2101998-01-13013 January 1998
LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status
ML18153A1911997-11-26026 November 1997
LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised
ML18153A1971997-11-26026 November 1997
LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset
ML18153A1921997-11-25025 November 1997
LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr
ML18153A1831997-11-12012 November 1997
LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause
ML18153A1791997-11-0707 November 1997
LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
ML18153A1721997-10-30030 October 1997
LER 97-007-00:on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage
ML18153A1421997-06-10010 June 1997
LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr
ML18153A1391997-05-28028 May 1997
LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
ML18153A1291997-04-18018 April 1997
LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr
ML18153A1281997-04-15015 April 1997
LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr
ML18153A1241997-04-0808 April 1997
LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr
ML18153A1191997-03-19019 March 1997
LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr
ML18153A1201997-03-19019 March 1997
LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML18152B3531999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr
ML18152B6651999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18151A3981999-08-13013 August 1999
SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage.
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B3791999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr
ML18152B3911999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr
ML18152B4341999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr
ML20195E2401999-05-31031 May 1999
Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4161999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18152B6511999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7331999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr
ML18152B5421999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr
ML18151A3031999-01-29029 January 1999
ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements.
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B7081998-11-30030 November 1998
Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un.
ML18152B5721998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6241998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B6881998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr
ML18153A3271998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A3161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr
ML18152B7621998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML18153A3141998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B8161998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML20217P9941998-04-0707 April 1998
Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024
ML18153A2951998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
1999-09-30
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Text
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- ~'\IRC Fo;m 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83)
APPROVED 0MB. NO. 3160-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31188 FACILITY NAME (1)
Surry Power Station,* Unit. 1 TITLE (4)
Manual Reactor Trip Due To Failed Relay In Main Transformer EVENT DATE (6) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR }ft SE~~~~~~AL tr~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) oI E ol 7 s 7 s 11 - o I 1I9 - oI o o I 9 o 14 aI1 01s1010101 I I THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or moro of tho fol/ovyin11} (11)
OPERATING MOOE (9)
N I
20.402(b) 20.405(0) X 60.73(o)(21(iv) 73.71(b) 20.4051*)(1 )Ii) 60.38(c)(1) 60.73l*ll2llv) 73.711c)
POWER L~~~L O I 9 -1 8 - 20.405(1)11 )Iii) 60.38(c)(2) 60.73(1)(Z)(viil OTHER (Sf)fJClfy In Ab1tn1ct lulow *nd In T*1tt, NRC Form 11111=
20.405(1)11 )(ill) 60.73(1)12)11) 60.73(1)(Z)(v1U)(A) 366A}
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LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE D. L. Benson Station Manaaer 8 I O14 31 517 1*-1 31 11 RI ll COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)
MANUFAC- MANUFAC-.
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ABSTRACT (Limit to 1400 spoc*s, i,o,, oppro1timote/y fift**n 1Jn11f*-spoc* typewritten linos} 116)
SUBMISSION DATE (15)
I I I On August 7, 1987 at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, with the unit at approximately 98% power, a manual reactor trip was initiated, following a short rampdown, due to loss of cooling and oil flow for the 'B' Main Transformer {EIIS-XFMR}. The transformer local annunciator panel {EIIS-ANN} had failed to initiate a TROUBLE alarm on the control room annunciator panel. Following ihe trip, all control and protection systems functioned properly except: - One channel of source range nuclear instrumentation (SR NI) {EIIS-IG} did not automatically reinstate. - The 'A' main feedwater pump (MFP) {EIIS-P} did not automatically trip and the pump's minimum flow recirc. valve did not open on a low feedwater flow condition.
Operators manually reinstated the SR NI and tripped the 'A' MFP. The unit was quickly stabilized at hot shutdown. Power was lost to the 'B' Main Transformer cooling fans and oil circulating pumps when an undervoltage relay {EIIS-RLY} in
- the cooling control circuit failed. The relay and annunciator panel failures are attributed to aging. One channel of SR NI failed to reinstate due to under-compensation of one channel of IR NI. The 'A' MFP did not trip and its minimum flow recirc. valve did not open due to a failed air regulator diaphragm to the pneumatic pressure switch which senses main feedwater flow. The failed relay and the local annunciator panel were replaced. The transformer was checked for winding or other internal damage and was determined to be undamaged. Since the relay and annunciator failures are attributed to aging, additional transformer circuit components susceptible to failures due to their age will be identified~O-,,
and replaced.
8709100301 8 ~ 2 8 1e ,i,"L J I
- DR ADOCK O PDRO NRC Form 361:l
POW 28-06-01 NRC Form 31141A e e U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT.REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150--0104 EXPIRES: B/31 /111 FACILITY NAME 111 DOCKET NUMBER (21 L!,R NUMBER UII PAGE (31 VEAR :::::::::: SEQUENTIAL .. REVISION
- NUMBER ..
- ... NUMBER Surry Power Station, Unit 1 o 15 Io Io IO I 2 IR In RI .7 - n I , I a - n In *nl ., OF n I ,,
TEXT ,,, - - a ,eqund, u* .<<lltioMI NRC Fann ......, 1171 1.0 Description of the Event on August 7, 1987 at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, with tbe unit at approximately 98% power, a manual reactor trip was initiated, following a short rampdown, due to loss of cooling and oil flow for the 'B' Main Transformer
{EIIS-XFMR}.
During his rounds, the outside plant operator noticed the cooling fans for the 'B' Main Transformer were stopped and that oil was flowing from a relief valve on the transformer. He informed the Shift Supervisor and the decision was made to initiate a rampdown and, subsequently, a manual reactor trip to prevent trans.former damage due to overheating. The transformer local annunciator panel {EIIS-ANN} had failed to initiate a TROUBLE alarm on the control room annunciator panel.
Immediately following the trip, all control and protection systems functioned properly except:
One channel of source range nuclear instrumentation (SR NI) {EIIS-IG} did not automatically reinstate due to under-compensation of one channel of intermediate range (IR NI) {EIIS-IG}, and the 'A' main feedwater pump (MFP) {EIIS-P}
did not automatically trip and* the pump's minimum flow recirc. valve did not open on a low feedwater flow cond~tion.
2.0 Safety Consequences and Implications A manual reactor trip from full power is well within the bounds of the UFSAR safety and accident analyses and all safety related and other systems required to shut the plant down safely functioned as designed.
Therefore, this event did not constitute an unreviewed safety question and the health and safety of the public were not affected.
NRC FORM 3S6A
- U.S.GPO: 1988-0-624*538/466 19-831
~- ~ ... _,,,, __._,_ .... ~ *- ...._...... **-**-'**---*,:.. *-*-
POW 28-06-01 NRC Form 3118A e U.S. NUCLEAR REGULATORY ~OMMISSION 19-831 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVED 0MB NO. 3150~104 EXPIRES: 8/31/111 FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER (Ill PAGE (31 VEAR Surrv Power Station Unit 1 o 1s Io Io Io I 218 IO 81 7 - Ol 119 - OI C OI 3 OF O14 TEXT (If""""~ o ,eqund, u* IMldllioMI NRC Form :m.1'1/ 1171
- 3. 0 , Cause Power was lost to the 'B' Main Transformer cooling fans and oil circulating pumps when an undervoltage relay
{EIIS-RLY} in the cooling control circuit failed. The relay and annunciator panel failures are attributed to aging. Without cooling, the transformer began to overheat and oil pressure increased causing the relief valve to lift.
One channel of SR NI failed to reinstate due to under compensation of one channel of IR NI.
The 'A' MFP did not trip and its minimum flow recirc.
valve did not open because they failed to receive the low feedwater flow signal. The air regulator to the pneumatic pressure switch which senses main feedwater flow was found to have a ruptured diaphragm. This resulted in an erroneous high feedwater flow signal in the MFP/recirc. valve logic circuit.
4.0 Immediate Corrective Action Control room operators manually reinstated the SR NI and tripped the 'A' MFP. Appropriate plant procedures were followed .and the unit was quickly stabilized at hot shutdown conditions. The Shift Technical Advisor performed critical safety function status tree reviews to ensure plant parameters were observed and maintained within safe limits.
5.0 Additional Corrective Actions The Main Transformer cooling circuit under voltage relay and the local annunciator panel were replaced.
The transformer was checked for winding or other internal damage and was determined to be undamaged based on an oil analysis and a high potential winding continuity test.
- Compensating voltage was adjusted on the IR NI and the air regulator diaphragm for the feedwater flow pressure switch was replaced. The 'A' MFP trip and recirculation valve logic circuit was tested to ensure proper operation.
NRC FORM 366A
- U.S.GPO: 1988*0-1124*538/465 19-83)
. '.*,,,., .. ,.--.,-*,.~-* ,_,,,*..:.,.*.~-~--**---**:-. .... _; - ---**
NRC Form 3811A 19-831 FACILITY NAME 111 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER 121 e
POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION LER NUMIIER 1111 APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31 /BB PAGE (31 YEAR ********** SEQUENTIAL -:*:*:*:*:* REVISION
.......... NUMBER * ..... NUMIIER Surry Power Station. Unit 1 01s101010121slo1Rl7 -nl, b -1nh- nJllOFn ILI TEXT 1/f - - II ,equltw/, ua .,,,,,,.,,_ NRC .Fann .-.,.*,1 1171 6.0 *Actions Taken To Prevent Recurrence Preventive maintenance was performed on the three main transformers. Since the relay and annunciator failures were attributed to aging, additional transformer control and protection circuit components susceptible to failures due to their age will be identified and*
replaced.
7.0 Similar Events None.
8.0 Manufacturer/Model Number Transformer: General Electric Single ~hase Step-up Power Transformer Failed Relay: General Electric CR120E UV re-lay.
NRC FORM 366A 19-831
- U.S.GP0:19B6-0-624*536/4_55
\
e -
VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 315 Surry, Virginie 23883 September 4, 1987 U.S. Nuclear Regulatory Commission Serial No.: 87-021 Document Control Desk Docket No. : .50-280
.016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen:
Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1.
REPORT NUMBER 87-019-00 This report ha.s been reviewed by the Station Nuclear Safety and Operating COIIIJ!littee and will be reviewed by Safety Evaluation and Control.
- Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323
