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| | issue date = 10/24/1995 | | | issue date = 10/24/1995 |
| | title = LER 95-023-00:on 950926,identified Eight SG Tubes Which Had Exceeded TS Plugging Criteria Due to Missed Eddy Current Indications.Structural Integrity Assessment Being Performed & Data Analyst Guidelines Being Developed | | | title = LER 95-023-00:on 950926,identified Eight SG Tubes Which Had Exceeded TS Plugging Criteria Due to Missed Eddy Current Indications.Structural Integrity Assessment Being Performed & Data Analyst Guidelines Being Developed |
| | author name = DULEE R | | | author name = Dulee R |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 14-951 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO. COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. REPORTED LESSONS LICENSEE EVENT REPORT (LER) LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. | | {{#Wiki_filter:NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 14-951 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO. COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED LICENSEE EVENT REPORT (LER) BACK TO INDUSTRY. FORWARD COMMENTS REGARDING. BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH IT-6 F331, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC (See reverse for required number of 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC digits/characters for each block! 20503. |
| FORWARD COMMENTS REGARDING. | | FACILITY NAME 111 DOCKET NUMBER 121 PAGE 131 SALEM GENERATING STATION UNIT 1 05000272 1 of 4 TITLE 141 FAILURE TO PLUG STEAM GENERATOR TUBES DUE TO MISSED EDDY CURRENT INDICATIONS EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER I |
| BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH IT-6 F331, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC (See reverse for required number of 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC digits/characters for each block! 20503. FACILITY NAME 111 DOCKET NUMBER 121 PAGE 131 SALEM GENERATING STATION UNIT 1 05000272 1 of 4 TITLE 141 FAILURE TO PLUG STEAM GENERATOR TUBES DUE TO MISSED EDDY CURRENT INDICATIONS EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER 01 06 94 95 023 00 10 24 95 FACILITY NAME DOCKET NUMBER ----OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 111 I MODE 191 4 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) | | 01 06 94 95 -- 023 -- 00 10 24 95 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 111 I MODE 191 4 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii) |
| : 50. 73(a)(2)(viii)
| | POWER 20.2203(a)(1 I 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(x) |
| POWER 20.2203(a)(1 I 20.2203(a)(3)(i) | | LEVEL (101 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iiil 73.71 20.2203(a)(2)(ii) 20.2203(a)(41 50. 73(a)(2)1iv) OTHER 20.2203(a)(2lliii) 50.36(c)( 11 50. 73(a)(2)(v) Specify In Abstract below or In NRC Form 366A 20.22031all211ivl 50.36(c)(2) 50. 73(a)(2)(vii) |
| : 50. 73(a)(2)(ii)
| | LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER (Include Area Codel Mr. Robert Dulee, Steam Generator Project Manager 609-339-5350 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| : 50. 73(a)(2)(x)
| | REPORTABLE REPORTABLE |
| LEVEL (101 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) | | ~f~f~~f~~I~1I~~~f CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 114) |
| : 50. 73(a)(2)(iiil 73.71 -20.2203(a)(2)(ii) 20.2203(a)(41
| | I |
| : 50. 73(a)(2)1iv)
| | ~:~:~:~=~ :~:~:~=~ =~=~ =~:~:~:: |
| OTHER 20.2203(a)(2lliii) 50.36(c)( 11 50. 73(a)(2)(v) | | EXPECTED MONTH DAY YEAR SUBMISSION IYES INO X (If yes, complete EXPECTED SUBMISSION DATE). DATE 1151 3 29 96 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (161 During a review of prior outage test data to support estimations of Steam Generator (S/G) tube indication growth rates, eight tubes were identified to have exceeded the Salem Technical Specification plugging criteria of 40% |
| Specify In Abstract below or In NRC Form 366A 20.22031all211ivl 50.36(c)(2) | | of tube wall as specified in the acceptance criteria of the surveillance requirements of Section 4 . 4 . 5 . 4 . Contrary to the Limiting Condition for Operations, Section 3.4.5, the unit was operated in modes 1 through 4 with steam generators that did not meet the operability requirements described in Section 4.4.5.4. |
| : 50. 73(a)(2)(vii)
| | The safety significance and root cause are unknown at this time. An investigation is underway and should be completed to permit a supplementary report by March 29, 1996. |
| LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER (Include Area Codel Mr. Robert Dulee, Steam Generator Project Manager 609-339-5350 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) ;:::::;:::::::::::::::::::::: | | This is reportable per 10CFR50.73 (a) ( 2) ( i) (B) I a condition prohibited by the plant's Technical Specifications. |
| CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS ::::::::::::::::::::::::::::. | | 9510300065 951024 NRC FORM 366 14-951 PDR ADOCK 05000272 S PDR |
| I :: SUPPLEMENTAL REPORT EXPECTED 114) EXPECTED MONTH DAY YEAR IYES INO SUBMISSION X (If yes, complete EXPECTED SUBMISSION DATE). DATE 1151 3 29 96 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (161 During a review of prior outage test data to support estimations of Steam Generator (S/G) tube indication growth rates, eight tubes were identified to have exceeded the Salem Technical Specification plugging criteria of 40% of tube wall as specified in the acceptance criteria of the surveillance requirements of Section 4 . 4 . 5 . 4 .
| | |
| Contrary to the Limiting Condition for Operations, Section 3.4.5, the unit was operated in modes 1 through 4 with steam generators that did not meet the operability requirements described in Section 4.4.5.4. The safety significance and root cause are unknown at this time. An investigation is underway and should be completed to permit a supplementary report by March 29, 1996. This is reportable per 10CFR50.73 (a) ( 2) ( i) (B) I a condition prohibited by the plant's Technical Specifications. | | NRC FORM 366A (4-96) |
| 9510300065 951024 NRC FORM 366 14-951 PDR ADOCK 05000272 S PDR | | LICENSEE EVENT REPORT (LER) |
| * NRC FORM 366A (4-96) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER SALEM GENERATING STATION UNIT 1 05000272 95 --023 --00 TEXT (If more epace is required, use additional copies of NRC Form 366AI 1171 PLANT .AND SYSTEM IDENTIFICATION Westinghouse
| | TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER SALEM GENERATING STATION UNIT 1 05000272 95 -- 023 -- 00 2 of 4 TEXT (If more epace is required, use additional copies of NRC Form 366AI 1171 PLANT .AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Reactor Coolant System/Steam Generator {AB/SG}* |
| -Pressurized Water Reactor Reactor Coolant System/Steam Generator | |
| {AB/SG}* | |
| * Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as {SS/CCC}. | | * Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as {SS/CCC}. |
| IDENTIFICATION OF OCCURRENCE PAGE 131 2 of 4 Missed Eddy Current Testing (ECT) indications during the 1993 Salem Unit #1 Refueling Outage (lRll) steam generator tube evaluations. | | IDENTIFICATION OF OCCURRENCE Missed Eddy Current Testing (ECT) indications during the 1993 Salem Unit #1 Refueling Outage (lRll) steam generator tube evaluations. |
| Event Date: January 6, 1994. Discovery Date: September 26, 1995. Report Date: October 25, 1995. CONDITIONS PRIOR TO OCCURRENCE Defueled -Reactor Power 0% DESCRIPTION OF OCCURRENCE To determine the growth rate of indications during the operating period between past outage lRll and current outage 1Rl2, a review of 1993 bobbin ECT data was performed. | | Event Date: January 6, 1994. |
| During this review, on September 26, 1995, bobbin probe indications with depths which exceed the Technical Specification plugging criteria of 40% of tube wall specified in section 4.4.5.4 were identified at Tube Support Plate (TSP) intersections for eight tubes (seven tubes with one indication each and the remaining tube with two indications) which were not plugged. In 1993 the primary and secondary analysts did not correctly identify, as pluggable, three indications which are now evaluated as having depths of 68%, 85%, and 96% through wall. Two indications now evaluated as 42% and 79% depth were evaluated in 1993 by both the primary and secondary analysts as distorted indications which should be examined by Rotating Pancake Coil (RPC); the resolution analyst concluded that neither indication was pluggable or required follow-up inspection by RPC. For the four other indications, differences between the primary and secondary analyst were evaluated by the resolution analyst as not pluggable. | | Discovery Date: September 26, 1995. |
| | Report Date: October 25, 1995. |
| | CONDITIONS PRIOR TO OCCURRENCE Defueled - Reactor Power 0% |
| | DESCRIPTION OF OCCURRENCE To determine the growth rate of indications during the operating period between past outage lRll and current outage 1Rl2, a review of 1993 bobbin ECT data was performed. During this review, on September 26, 1995, bobbin probe indications with depths which exceed the Technical Specification plugging criteria of 40% of tube wall specified in section 4.4.5.4 were identified at Tube Support Plate (TSP) intersections for eight tubes (seven tubes with one indication each and the remaining tube with two indications) which were not plugged. |
| | In 1993 the primary and secondary analysts did not correctly identify, as pluggable, three indications which are now evaluated as having depths of 68%, 85%, and 96% through wall. Two indications now evaluated as 42% and 79% depth were evaluated in 1993 by both the primary and secondary analysts as distorted indications which should be examined by Rotating Pancake Coil (RPC); the resolution analyst concluded that neither indication was pluggable or required follow-up inspection by RPC. For the four other indications, differences between the primary and secondary analyst were evaluated by the resolution analyst as not pluggable. |
| NRC FORM 366A (4-95) | | NRC FORM 366A (4-95) |
| NRC FORM 366A (4-961 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER SALEM GENERATING STATION UNIT 1 05000272 95 --023 --00 TEXT (If more apace is required. | | |
| use additional copies of NRC Form 366AJ 11 71 APPARENT CAUSE OF OCCURRENCE .PAGE 131 3 of 4 The cause of the missed bobbin coil probe indications is not known at this time. PRIOR SIMILAR OCCURRENCES There is no prior similar occurrence at Salem of the identification of an ECT indication which should have been called at a previous inspection. | | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-961 LICENSEE EVENT REPORT (LER) |
| A review of events previously reported to the NRC by other plants indicates that missed bobbin coil probe pluggable indications have been experienced at Sequoyah Unit 1, ANO Unit 2, North Anna Unit 1, Ginna, Yankee Rowe, and Maine Yankee. SAFETY SIGNIFICANCE A structural integrity assessment is being performed by Westinghouse to demonstrate that the requirements of Reg. Guide 1.121 are met by the tubes with their as-found flaw configuration. | | TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 .PAGE 131 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER SALEM GENERATING STATION UNIT 1 05000272 3 of 4 95 -- 023 -- 00 TEXT (If more apace is required. use additional copies of NRC Form 366AJ 11 71 APPARENT CAUSE OF OCCURRENCE The cause of the missed bobbin coil probe indications is not known at this time. |
| Ultrasonic testing is being performed to verify the crack configuration, and in-situ pressure testing will be performed to support the structural integrity assessment. | | PRIOR SIMILAR OCCURRENCES There is no prior similar occurrence at Salem of the identification of an ECT indication which should have been called at a previous inspection. A review of events previously reported to the NRC by other plants indicates that missed bobbin coil probe pluggable indications have been experienced at Sequoyah Unit 1, ANO Unit 2, North Anna Unit 1, Ginna, Yankee Rowe, and Maine Yankee. |
| If the strcuctural integrity assessment demonstrates that the requirements of Reg. Guide 1.121 have been met, this event will have no safety significance. | | SAFETY SIGNIFICANCE A structural integrity assessment is being performed by Westinghouse to demonstrate that the requirements of Reg. Guide 1.121 are met by the tubes with their as-found flaw configuration. Ultrasonic testing is being performed to verify the crack configuration, and in-situ pressure testing will be performed to support the structural integrity assessment. If the strcuctural integrity assessment demonstrates that the requirements of Reg. |
| CORRECTIVE ACTIONS Salem Unit #1 1. A structural integrity assessment is being performed to confirm that affected tubes in their as-found condition meet the requirements of Reg. Guide 1.121. 2. A number of corrective actions are being taken to assure that all tubes with ECT depth indications greater than 40% are plugged and to minimize any future missed call of a pluggable ECT indication. | | Guide 1.121 have been met, this event will have no safety significance. |
| These corrective actions include: a. An independent assessment of the training and qualification of analysts involved in the 1993 and 1995 analyses of Salem Unit 1 ECT data has been performed. | | CORRECTIVE ACTIONS Salem Unit #1 |
| This assessment indicates that there are no apparent procedural or regulatory violations. | | : 1. A structural integrity assessment is being performed to confirm that affected tubes in their as-found condition meet the requirements of Reg. |
| However, specific areas where the program for training and qualification of analysts could be improved were noted. Each of these areas has been discussed with the contractor. | | Guide 1.121. |
| | : 2. A number of corrective actions are being taken to assure that all tubes with ECT depth indications greater than 40% are plugged and to minimize any future missed call of a pluggable ECT indication. These corrective actions include: |
| | : a. An independent assessment of the training and qualification of analysts involved in the 1993 and 1995 analyses of Salem Unit 1 ECT data has been performed. This assessment indicates that there are no apparent procedural or regulatory violations. However, specific areas where the program for training and qualification of analysts could be improved were noted. Each of these areas has been discussed with the contractor. |
| NRC FORM 366A (4-95) | | NRC FORM 366A (4-95) |
| * NRC FORM 366A 14-951 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 YEAR I SEQUENTIAL I RIMSION NUMBER NUMBER SALEM GENERATING STATION UNIT 1 05000272 95 --023 --00 TEXT (If more space is required, use additional copies of NRC Form 366AI 11 71 CORRECTIVE ACTIONS (cont'd) PAGE 131 4 of 4 b. Data analyst guidelines specific to Salem Units 1 and 2 are being developed.
| | |
| to performing any S/G ECT inspections in either Unit #1 or Unit #2, all analysts will be trained and tested to demonstrate proficiency in the use of the guidelines. | | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 14-951 |
| : c. A full length bobbin coil ECT inspection expansion of all unplugged tubes in all steam generators from the current 20% sample size will be performed to assure that all bobbin coil probe indications are analyzed during the current outage. The 1993 bobbin coil probe data will be reviewed for any additional pluggable indications identified in the current outage to assess the apparent growth rate of indications. | | * LICENSEE EVENT REPORT (LER) |
| This expanded inspection scope may identify additional bobbin coil probe indications which should have been analyzed as pluggable in 1993. This task will be completed by March 29, 1996. d. All bobbin coil inspection data already taken will be reanalyzed. | | TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 YEAR I SEQUENTIAL NUMBER I RIMSION NUMBER SALEM GENERATING STATION UNIT 1 05000272 4 of 4 95 -- 023 -- 00 TEXT (If more space is required, use additional copies of NRC Form 366AI 11 71 CORRECTIVE ACTIONS (cont'd) |
| A PSE&G Level III examiner will provide oversight of this reanalysis effort. This task will be completed by March 29, 1996. e. Steam generator tubes requiring plugging will be plugged based upon the results of tasks 2c and 2d prior to restart of Unit #1. Salem Unit #2 3. The corrective action described in item 2b above for site specific training and testing will be implemented prior to performing ECT on Salem Unit #2. 4. Salem Unit #2's steam generators will have completed 100% tube inspections prior to Unit #2 restart. If a defective tube was missed in a prior outage, the planned inspection program should detect the defective tube and a supplement to this LER will be issued. NRC FORM 366A (4-95)}} | | : b. Data analyst guidelines specific to Salem Units 1 and 2 are being developed. P~ior to performing any S/G ECT inspections in either Unit #1 or Unit #2, all analysts will be trained and tested to demonstrate proficiency in the use of the guidelines. |
| | : c. A full length bobbin coil ECT inspection expansion of all unplugged tubes in all steam generators from the current 20% sample size will be performed to assure that all bobbin coil probe indications are analyzed during the current outage. The 1993 bobbin coil probe data will be reviewed for any additional pluggable indications identified in the current outage to assess the apparent growth rate of indications. This expanded inspection scope may identify additional bobbin coil probe indications which should have been analyzed as pluggable in 1993. This task will be completed by March 29, 1996. |
| | : d. All bobbin coil inspection data already taken will be reanalyzed. A PSE&G Level III examiner will provide oversight of this reanalysis effort. This task will be completed by March 29, 1996. |
| | : e. Steam generator tubes requiring plugging will be plugged based upon the results of tasks 2c and 2d prior to restart of Unit #1. |
| | Salem Unit #2 |
| | : 3. The corrective action described in item 2b above for site specific training and testing will be implemented prior to performing ECT on Salem Unit #2. |
| | : 4. Salem Unit #2's steam generators will have completed 100% tube inspections prior to Unit #2 restart. If a defective tube was missed in a prior outage, the planned inspection program should detect the defective tube and a supplement to this LER will be issued. |
| | NRC FORM 366A (4-95)}} |
LER 95-023-00:on 950926,identified Eight SG Tubes Which Had Exceeded TS Plugging Criteria Due to Missed Eddy Current Indications.Structural Integrity Assessment Being Performed & Data Analyst Guidelines Being Developed| ML18101B077 |
| Person / Time |
|---|
| Site: |
Salem  |
|---|
| Issue date: |
10/24/1995 |
|---|
| From: |
Dulee R
Public Service Enterprise Group |
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| To: |
|
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| Shared Package |
|---|
| ML18101B076 |
List: |
|---|
| References |
|---|
| LER-95-023, LER-95-23, NUDOCS 9510300065 |
| Download: ML18101B077 (4) |
|
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|---|
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LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr
ML18106A8821998-09-21021 September 1998
LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr
ML18106A8791998-09-16016 September 1998
LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr
ML18106A8801998-09-0808 September 1998
LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr
ML18106A8531998-08-27027 August 1998
LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr
ML18106A8521998-08-27027 August 1998
LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr
ML18106A8421998-08-24024 August 1998
LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr
ML18106A8431998-08-24024 August 1998
LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr
ML18106A8141998-08-13013 August 1998
LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr
ML18106A8201998-08-13013 August 1998
LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr
ML18106A6931998-06-29029 June 1998
LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged
ML18106A6471998-06-0404 June 1998
LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr
ML18106A6421998-06-0101 June 1998
LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr
ML18106A6431998-05-29029 May 1998
LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr
ML18106A6141998-05-18018 May 1998
LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr
ML18106A5901998-05-0101 May 1998
LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr
ML18106A5611998-04-20020 April 1998
LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected
ML18106A6061998-04-0101 April 1998
Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences
ML18106A4451998-04-0101 April 1998
LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr
ML18106A4351998-03-30030 March 1998
LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr
ML18106A3961998-03-20020 March 1998
LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr
ML18106A5781998-03-20020 March 1998
Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs
ML18106A4021998-03-20020 March 1998
LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr
ML18106A4031998-03-20020 March 1998
LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr
1999-08-26
[Table view]
Category:RO)
MONTHYEARML18107A5031999-08-26026 August 1999
LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr
ML18107A4691999-07-28028 July 1999
LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr
ML18107A4441999-07-0606 July 1999
LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr
ML18107A4211999-07-0202 July 1999
LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr
ML18107A4321999-07-0101 July 1999
LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr
ML18107A4331999-07-0101 July 1999
LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr
ML18107A3951999-06-17017 June 1999
LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr
ML18107A3661999-06-0909 June 1999
LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr
ML18107A3551999-06-0202 June 1999
LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr
ML18107A3541999-06-0101 June 1999
LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr
ML18107A2931999-05-12012 May 1999
LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr
ML18107A2781999-05-10010 May 1999
LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr
ML18107A2791999-05-0404 May 1999
LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr
ML18107A2741999-05-0303 May 1999
LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr
ML18107A2351999-04-23023 April 1999
LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr
ML18106B1471999-03-29029 March 1999
LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr
ML18106B0701999-02-16016 February 1999
LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr
ML18106B0491999-01-28028 January 1999
LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr
ML18106B0401999-01-18018 January 1999
LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr
ML18106B0081998-12-24024 December 1998
LER 97-001-01:on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With 981224 Ltr
ML18106B0021998-12-17017 December 1998
LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr
ML18106A9551998-11-0303 November 1998
LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr
ML18106A9451998-10-30030 October 1998
LER 97-004-01:on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With 981022 Ltr
ML18106A9491998-10-22022 October 1998
LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr
ML18106A9301998-10-21021 October 1998
LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr
ML18106A9071998-10-0101 October 1998
LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr
ML18106A8951998-09-28028 September 1998
LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr
ML18106A8821998-09-21021 September 1998
LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr
ML18106A8791998-09-16016 September 1998
LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr
ML18106A8801998-09-0808 September 1998
LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr
ML18106A8531998-08-27027 August 1998
LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr
ML18106A8521998-08-27027 August 1998
LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr
ML18106A8421998-08-24024 August 1998
LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr
ML18106A8431998-08-24024 August 1998
LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr
ML18106A8141998-08-13013 August 1998
LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr
ML18106A8201998-08-13013 August 1998
LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr
ML18106A6931998-06-29029 June 1998
LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged
ML18106A6471998-06-0404 June 1998
LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr
ML18106A6421998-06-0101 June 1998
LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr
ML18106A6431998-05-29029 May 1998
LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr
ML18106A6141998-05-18018 May 1998
LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr
ML18106A5901998-05-0101 May 1998
LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr
ML18106A5611998-04-20020 April 1998
LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected
ML18106A6061998-04-0101 April 1998
Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences
ML18106A4451998-04-0101 April 1998
LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr
ML18106A4351998-03-30030 March 1998
LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr
ML18106A3961998-03-20020 March 1998
LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr
ML18106A5781998-03-20020 March 1998
Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs
ML18106A4021998-03-20020 March 1998
LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr
ML18106A4031998-03-20020 March 1998
LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr
1999-08-26
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18107A5581999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr
ML18107A5571999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr
ML18107A5301999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr
ML18107A5311999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913
ML18107A5031999-08-26026 August 1999
LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr
ML18107A5201999-08-12012 August 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF).
ML18107A4811999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr
ML18107A4821999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr
ML18107A4691999-07-28028 July 1999
LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr
ML18107A4441999-07-0606 July 1999
LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr
ML18107A4211999-07-0202 July 1999
LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr
ML18107A4331999-07-0101 July 1999
LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr
ML18107A4321999-07-0101 July 1999
LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr
ML18107A5211999-07-0101 July 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF).
ML18107A4351999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr
ML18107A4341999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18107A3951999-06-17017 June 1999
LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr
ML18107A3661999-06-0909 June 1999
LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr
ML18107A3551999-06-0202 June 1999
LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr
ML18107A3441999-06-0101 June 1999
Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716
ML18107A3541999-06-0101 June 1999
LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr
ML18107A3681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr
ML18107A3721999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr
ML18107A2931999-05-12012 May 1999
LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr
ML18107A2781999-05-10010 May 1999
LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr
ML18107A2791999-05-0404 May 1999
LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr
ML18107A2741999-05-0303 May 1999
LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr
ML18107A3711999-04-30030 April 1999
Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
ML18107A2991999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr
ML18107A2971999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr
ML18107A2351999-04-23023 April 1999
LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr
ML18107A2881999-04-0707 April 1999
Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11.
ML18107A1821999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr
ML18107A1831999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr
ML18106B1471999-03-29029 March 1999
LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr
ML18106B1021999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr
ML18106B1011999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr
ML18106B0931999-02-25025 February 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified
ML18106B0701999-02-16016 February 1999
LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr
ML18106B0551999-02-0101 February 1999
Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl
ML18106B0561999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr
ML18106B0571999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr
ML20205P1671999-01-31031 January 1999
a POST-PLUME Phase, Federal Participation Exercise
ML18106B0441999-01-29029 January 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables
ML18106B0491999-01-28028 January 1999
LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr
ML18106B0401999-01-18018 January 1999
LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr
ML18106B0251998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr
1999-09-30
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 14-951 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO. COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED LICENSEE EVENT REPORT (LER) BACK TO INDUSTRY. FORWARD COMMENTS REGARDING. BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH IT-6 F331, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC (See reverse for required number of 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT 13150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC digits/characters for each block! 20503.
FACILITY NAME 111 DOCKET NUMBER 121 PAGE 131 SALEM GENERATING STATION UNIT 1 05000272 1 of 4 TITLE 141 FAILURE TO PLUG STEAM GENERATOR TUBES DUE TO MISSED EDDY CURRENT INDICATIONS EVENT DATE 151 LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER I
01 06 94 95 -- 023 -- 00 10 24 95 FACILITY NAME DOCKET NUMBER OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 111 I MODE 191 4 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii)
POWER 20.2203(a)(1 I 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(x)
LEVEL (101 000 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iiil 73.71 20.2203(a)(2)(ii) 20.2203(a)(41 50. 73(a)(2)1iv) OTHER 20.2203(a)(2lliii) 50.36(c)( 11 50. 73(a)(2)(v) Specify In Abstract below or In NRC Form 366A 20.22031all211ivl 50.36(c)(2) 50. 73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER (Include Area Codel Mr. Robert Dulee, Steam Generator Project Manager 609-339-5350 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
REPORTABLE REPORTABLE
~f~f~~f~~I~1I~~~f CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED 114)
I
~:~:~:~=~ :~:~:~=~ =~=~ =~:~:~::
EXPECTED MONTH DAY YEAR SUBMISSION IYES INO X (If yes, complete EXPECTED SUBMISSION DATE). DATE 1151 3 29 96 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (161 During a review of prior outage test data to support estimations of Steam Generator (S/G) tube indication growth rates, eight tubes were identified to have exceeded the Salem Technical Specification plugging criteria of 40%
of tube wall as specified in the acceptance criteria of the surveillance requirements of Section 4 . 4 . 5 . 4 . Contrary to the Limiting Condition for Operations, Section 3.4.5, the unit was operated in modes 1 through 4 with steam generators that did not meet the operability requirements described in Section 4.4.5.4.
The safety significance and root cause are unknown at this time. An investigation is underway and should be completed to permit a supplementary report by March 29, 1996.
This is reportable per 10CFR50.73 (a) ( 2) ( i) (B) I a condition prohibited by the plant's Technical Specifications.
9510300065 951024 NRC FORM 366 14-951 PDR ADOCK 05000272 S PDR
NRC FORM 366A (4-96)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER SALEM GENERATING STATION UNIT 1 05000272 95 -- 023 -- 00 2 of 4 TEXT (If more epace is required, use additional copies of NRC Form 366AI 1171 PLANT .AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Reactor Coolant System/Steam Generator {AB/SG}*
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear in the text as {SS/CCC}.
IDENTIFICATION OF OCCURRENCE Missed Eddy Current Testing (ECT) indications during the 1993 Salem Unit #1 Refueling Outage (lRll) steam generator tube evaluations.
Event Date: January 6, 1994.
Discovery Date: September 26, 1995.
Report Date: October 25, 1995.
CONDITIONS PRIOR TO OCCURRENCE Defueled - Reactor Power 0%
DESCRIPTION OF OCCURRENCE To determine the growth rate of indications during the operating period between past outage lRll and current outage 1Rl2, a review of 1993 bobbin ECT data was performed. During this review, on September 26, 1995, bobbin probe indications with depths which exceed the Technical Specification plugging criteria of 40% of tube wall specified in section 4.4.5.4 were identified at Tube Support Plate (TSP) intersections for eight tubes (seven tubes with one indication each and the remaining tube with two indications) which were not plugged.
In 1993 the primary and secondary analysts did not correctly identify, as pluggable, three indications which are now evaluated as having depths of 68%, 85%, and 96% through wall. Two indications now evaluated as 42% and 79% depth were evaluated in 1993 by both the primary and secondary analysts as distorted indications which should be examined by Rotating Pancake Coil (RPC); the resolution analyst concluded that neither indication was pluggable or required follow-up inspection by RPC. For the four other indications, differences between the primary and secondary analyst were evaluated by the resolution analyst as not pluggable.
NRC FORM 366A (4-95)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-961 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 .PAGE 131 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER SALEM GENERATING STATION UNIT 1 05000272 3 of 4 95 -- 023 -- 00 TEXT (If more apace is required. use additional copies of NRC Form 366AJ 11 71 APPARENT CAUSE OF OCCURRENCE The cause of the missed bobbin coil probe indications is not known at this time.
PRIOR SIMILAR OCCURRENCES There is no prior similar occurrence at Salem of the identification of an ECT indication which should have been called at a previous inspection. A review of events previously reported to the NRC by other plants indicates that missed bobbin coil probe pluggable indications have been experienced at Sequoyah Unit 1, ANO Unit 2, North Anna Unit 1, Ginna, Yankee Rowe, and Maine Yankee.
SAFETY SIGNIFICANCE A structural integrity assessment is being performed by Westinghouse to demonstrate that the requirements of Reg. Guide 1.121 are met by the tubes with their as-found flaw configuration. Ultrasonic testing is being performed to verify the crack configuration, and in-situ pressure testing will be performed to support the structural integrity assessment. If the strcuctural integrity assessment demonstrates that the requirements of Reg.
Guide 1.121 have been met, this event will have no safety significance.
CORRECTIVE ACTIONS Salem Unit #1
- 1. A structural integrity assessment is being performed to confirm that affected tubes in their as-found condition meet the requirements of Reg.
Guide 1.121.
- 2. A number of corrective actions are being taken to assure that all tubes with ECT depth indications greater than 40% are plugged and to minimize any future missed call of a pluggable ECT indication. These corrective actions include:
- a. An independent assessment of the training and qualification of analysts involved in the 1993 and 1995 analyses of Salem Unit 1 ECT data has been performed. This assessment indicates that there are no apparent procedural or regulatory violations. However, specific areas where the program for training and qualification of analysts could be improved were noted. Each of these areas has been discussed with the contractor.
NRC FORM 366A (4-95)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 14-951
- LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE 131 YEAR I SEQUENTIAL NUMBER I RIMSION NUMBER SALEM GENERATING STATION UNIT 1 05000272 4 of 4 95 -- 023 -- 00 TEXT (If more space is required, use additional copies of NRC Form 366AI 11 71 CORRECTIVE ACTIONS (cont'd)
- b. Data analyst guidelines specific to Salem Units 1 and 2 are being developed. P~ior to performing any S/G ECT inspections in either Unit #1 or Unit #2, all analysts will be trained and tested to demonstrate proficiency in the use of the guidelines.
- c. A full length bobbin coil ECT inspection expansion of all unplugged tubes in all steam generators from the current 20% sample size will be performed to assure that all bobbin coil probe indications are analyzed during the current outage. The 1993 bobbin coil probe data will be reviewed for any additional pluggable indications identified in the current outage to assess the apparent growth rate of indications. This expanded inspection scope may identify additional bobbin coil probe indications which should have been analyzed as pluggable in 1993. This task will be completed by March 29, 1996.
- d. All bobbin coil inspection data already taken will be reanalyzed. A PSE&G Level III examiner will provide oversight of this reanalysis effort. This task will be completed by March 29, 1996.
- e. Steam generator tubes requiring plugging will be plugged based upon the results of tasks 2c and 2d prior to restart of Unit #1.
Salem Unit #2
- 3. The corrective action described in item 2b above for site specific training and testing will be implemented prior to performing ECT on Salem Unit #2.
- 4. Salem Unit #2's steam generators will have completed 100% tube inspections prior to Unit #2 restart. If a defective tube was missed in a prior outage, the planned inspection program should detect the defective tube and a supplement to this LER will be issued.
NRC FORM 366A (4-95)