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| {{#Wiki_filter:e ( 0 . Public _Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 2 3 1997 LR-N970456 U. S. Nuclear Regulatory Commission Document Contr61 Desk Washington, DC 20555 Gentlemen: | | {{#Wiki_filter:e |
| LER 311/97-007-00 SALEM GENERATING STATION -UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed 4.0.5 Testing of Check Valves 2CC195 and 2CC210," is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B). -Attachment BJT C Distribution LER File 3.7 9707300043 970723 PDR ADOCK 05000311 S PDR cror:ly David F. Garchow General Manager -Salem Operations | | ( 0 PS~G |
| \ \\\\\\ \\\\\ \\\\\ \\\\\ \\\\\ \\\\\ \\\\ \\\\ 95*2168 REV. 6/94
| | . Public _Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 2 3 1997 LR-N970456 U. S. Nuclear Regulatory Commission Document Contr61 Desk Washington, DC 20555 Gentlemen: |
| -NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY. | | LER 311/97-007-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed 4.0.5 Testing of Check Valves 2CC195 and 2CC210," is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B). |
| FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555--0001, AND TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT (3150--0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) SALEM GENERATING STATION UNIT 2 05000311 1 OF 4 TITLE(.() | | cror:ly |
| Missed 4.0.5 Testing of Check Valves 2CC195 and 2CC210 EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) I FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL I REVISION MONTH DAY YEAR NUMBER NUMBER 06 23 97 97 007 00 07 23 97 FACILITY NAME DOCKET NUMBER --OPERATING 4 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) | | - -~, |
| : 50. 73(a)(2)(viii)
| | David F. Garchow General Manager - |
| POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) | | Salem Operations Attachment BJT C Distribution LER File 3.7 9707300043 970723 PDR ADOCK 05000311 S PDR |
| : 50. 73(a)(2)(ii)
| | \\\\\\\ \\\\\ \\\\\ \\\\\\\\\\\\\\\ \\\\ \\\\ |
| : 50. 73(a)(2)(><)
| | 95*2168 REV. 6/94 |
| LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) | | |
| : 50. 73(a)(2)(iii) 73.71 -20.2203(a)(2)(ii) 20.2203(a)(4)
| | - |
| : 50. 73(a)(2)(iv)
| | NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. |
| OTHER 20.2203(a)(2)(iii) 50.36(c)(1) | | REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20555--0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150--0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| : 50. 73(a)(2)(v)
| | FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) |
| Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) | | SALEM GENERATING STATION UNIT 2 05000311 1 OF 4 TITLE(.() |
| : 50. 73(a)(2)(vii)
| | Missed 4.0.5 Testing of Check Valves 2CC195 and 2CC210 EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Area Code) Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR 'YES XINO SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE). DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) On June 23, 1997 ,-*the Technical Specification (TS) 4. 0. 5 Inservice Inspection (ISI) requirement to perform radiography of check valves 2CC195 and 2CC210 every 92 days was determined to have been missed. As a result of the missed surveillance, one loop of the component cooling water was declared inoperable until the surveillance testing (radiography) was completed. | | MONTH DAY YEAR YEAR SEQUENTIAL IREVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER I NUMBER NUMBER FACILITY NAME DOCKET NUMBER 06 23 97 97 - 007 - 00 07 23 97 OPERATING 4 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11) |
| Since the missed surveillance test exceeded the surveillance test interval, the 25% extension allowed by TS 4. 0. 2' and the Limiting Condition for Operation (LCO) statement time, this event is reportable in accordance with 10CFR50.73(a) | | MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii) |
| (2) (i) (B) as, "any condition prohibited by the plant's Technical Specifications." The cause of this occurrence is attributed to personnel error. The recurring task for performing the next 92 day surveillance was not generated prior to the expiration of the surveillance test interval. | | POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(><) |
| The check valves were subsequently tested and determined to be in their proper position. | | LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 |
| The personnel involved in this event have received appropriate disciplinary actions. NRC FORM 366 (4-95) t NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) SALEM GENERATING STATION UNIT 2 05000311 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 2 97 -007 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM IDENTIFICATION Westinghouse | | - |
| -Pressurized Water Reactor Component Cooling Water System {CB/-}* | | 20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) Spec~in Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50. 73(a)(2)(vii) |
| * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC} in the text. CONDITIONS PRIOR TO OCCURRENCE The plant was in Mode 4 prior to the event. DESCRIPTION OF OCCURRENCE OF 4 On June 23, 1997, the Technical Specification (TS) 4.0.5 Inservice Inspection (ISI) requirement to perform radiography of check valves 2CC195 and 2CC210 every 92 days was determined to have been missed. The 92 day surveillance plus the 25% surveillance extension provided by TS 4.0.2 was due on June 15, 1997. Upon identification of the overdue surveillance for the 2CC195 and 2CC210 valves, the check valves were radiographed on June 23, 1997, and were determined to be in their proper position (closed). | | LICENSEE CONTACT FOR THIS LER (12) |
| As a result of the missed surveillance, one loop of the component cooling water was declared inoperable until the surveillance testing (radiography) was completed. | | NAME TELEPHONE NUMBER (Include Area Code) |
| Since the missed surveillance test exceeded the surveillance test interval, the 25% extension allowed by TS 4.0.2, and the Limiting Condition for Operation (LCO) statement time, this event is reportable in accordance with 10CFR50.73(a) | | Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| (2) (i) (B) as, "any condition prohibited by the plant's Technical Specifications." ANALYSIS OF OCCURRENCE In February of 19if7, the Inservice Testing (IST) group identified that check valves 1(2)CC195 and 1(2)CC210 for the component cooling system were required to be tested in the reverse direction for ASME Class 3 boundary isolation on a 92 day frequency.
| | CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSION |
| As a result of the identification of the requirement to test check valves CC195 and CC210 in the closed position, valves 2CC195 and 2CC210 were radiographed on February 21, 1997 to verify that they were fully closed and fulfilling their function as the ASME Class 3 boundary. | | 'YES (If yes, EXPECTED SUBMISSION DATE). XINO complete DATE (15) |
| Completion of the radiography on February 21 then started the 92 day surveillance interval for the next surveillance test. The past reportability for failure to perform surveillance testing of the CC195 and CC2LO valves prior to February of 1997 will be addressed in Supplemental LER 272/97-001-01. | | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) |
| | On June 23, 1997 ,- *the Technical Specification (TS) 4. 0. 5 Inservice Inspection (ISI) requirement to perform radiography of check valves 2CC195 and 2CC210 every 92 days was determined to have been missed. As a result of the missed surveillance, one loop of the component cooling water was declared inoperable until the surveillance testing (radiography) was completed. Since the missed surveillance test exceeded the surveillance test interval, the 25% extension allowed by TS 4. 0. 2' and the Limiting Condition for Operation (LCO) statement time, this event is reportable in accordance with 10CFR50.73(a) (2) (i) (B) as, "any condition prohibited by the plant's Technical Specifications." |
| | The cause of this occurrence is attributed to personnel error. The recurring task for performing the next 92 day surveillance was not generated prior to the expiration of the surveillance test interval. The check valves were subsequently tested and determined to be in their proper position. The personnel involved in this event have received appropriate disciplinary actions. |
| | NRC FORM 366 (4-95) |
| | |
| | ~ t NRC FORM 366A (4-95) |
| | U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000311 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 2 OF 4 SALEM GENERATING STATION UNIT 2 97 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Component Cooling Water System {CB/-}* |
| | * Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC} in the text. |
| | CONDITIONS PRIOR TO OCCURRENCE The plant was in Mode 4 prior to the event. |
| | DESCRIPTION OF OCCURRENCE On June 23, 1997, the Technical Specification (TS) 4.0.5 Inservice Inspection (ISI) requirement to perform radiography of check valves 2CC195 and 2CC210 every 92 days was determined to have been missed. The 92 day surveillance plus the 25% surveillance extension provided by TS 4.0.2 was due on June 15, 1997. Upon identification of the overdue surveillance for the 2CC195 and 2CC210 valves, the check valves were radiographed on June 23, 1997, and were determined to be in their proper position (closed). As a result of the missed surveillance, one loop of the component cooling water was declared inoperable until the surveillance testing (radiography) was completed. Since the missed surveillance test exceeded the surveillance test interval, the 25% extension allowed by TS 4.0.2, and the Limiting Condition for Operation (LCO) statement time, this event is reportable in accordance with 10CFR50.73(a) (2) (i) (B) as, "any condition prohibited by the plant's Technical Specifications." |
| | ANALYSIS OF OCCURRENCE In February of 19if7, the Inservice Testing (IST) group identified that check valves 1(2)CC195 and 1(2)CC210 for the component cooling system were required to be tested in the reverse direction for ASME Class 3 boundary isolation on a 92 day frequency. As a result of the identification of the requirement to test check valves CC195 and CC210 in the closed position, valves 2CC195 and 2CC210 were radiographed on February 21, 1997 to verify that they were fully closed and fulfilling their function as the ASME Class 3 boundary. Completion of the radiography on February 21 then started the 92 day surveillance interval for the next surveillance test. The past reportability for failure to perform surveillance testing of the CC195 and CC2LO valves prior to February of 1997 will be addressed in Supplemental LER 272/97-001-01. |
| NRC FORM 366A (4-95) | | NRC FORM 366A (4-95) |
| NRC FORM 366A '* (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) SALEM GENERATING STATION UNIT 2 0 5 0 0 0 311 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 97 -007 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) ANALYSIS OF OCCURRENCE (cont'd) PAGE (3) 3 OF 4 As a result of the identification of the need to perform surveillance testing of check valves CC195 and CC210, a Business Process Action Request (BPAR) was generated by the ISI group, on April 2, 1997, to request that surveillance test recurring tasks (RT) for valves 2CC195 and 2CC210 be generated to test these check valves on a 92 day frequency. | | |
| The valves were then added to the ISI procedure for radiography on April 4, 1997. Although the request for generation of the surveillance test RTs was generated in April, the request was not received by the Technical Specification Administrator, who is responsible for implementing changes to the surveillance testing RT, until May 6. The surveillance test recurring task request generated by the ISI group did not identify when the previous surveillance test was performed or when the next surveillance test was required to be performed in accordance with the administrative procedure. | | NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION |
| Although the date for required completion of the next surveillance test was not specified in the description of the BPAR, the Technical Specification Administrator, by coincidence, assigned a completion date for creation of the new surveillance testing RT of June 15, 1997 (this date corresponds to the 92 day surveillance interval plus the 25% extension allowed by TS 4.0.2). However, the task for completion of the new surveillance testing RT was extended by the Technical Specification Administrator to June 27, 1997, without the recognition that the surveillance test would go overdue. Upon generation of the request for creation of the new surveillance test RT, the ISI group also did not verify that the recurring task would be issued prior to the due date of the next required surveillance test. Upon identification that the 4.0.5 surveillance testing for 2CC195 and 2CC210 was overdue, the check valves were radiographed on June 23, 1997 and the new surveillance testing RT was generated on June 25, 1997. CAUSE OF OCCURRENCE | | '* (4-95) |
| -The cause of this occurrence is attributed to personnel error. The ISI group did not verify that the new surveillance testing RT would be generated prior to the due date of the next surveillance test. Also, the Technical Specification Administrator extended the task for generation of the new surveillance testing RT without recognizing that the next surveillance test would go overdue. PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 submitted in the past two years did not identify any additional reportable occurrences as a result of the failure to generate a recurring task for creation of surveillance testing work orders. Although numerous LERs have been written in the past two years for missed surveillance testing, these incidents have been attributed to a lack of adequate controls on the development and maintenance of Technical Specification surveillance procedures.
| | LICENSEE EVENT REPORT (LER) |
| NRG FORM 366A (4-95) | | TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 0 5 0 0 0 311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 3 OF 4 SALEM GENERATING STATION UNIT 2 97 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| -f NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) SALEM GENERATING STATION UNIT 2 05000311 YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 4 OF 97 -007 -00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) SAFETY SIGNIFICANCE The testing of check valves 2CC195 and 2CC210 on June 23, 1997, demonstrated that the check valves were closed and provided the proper ASME Code boundary. | | ANALYSIS OF OCCURRENCE (cont'd) |
| Therefore there was no impact to the health and safety of the public. CORRECTIVE ACTIONS 1. Check valves 2CC195 and 2CC210 were radiographed on June 23, 1997 and determined to be in their proper position (closed position). | | As a result of the identification of the need to perform surveillance testing of check valves CC195 and CC210, a Business Process Action Request (BPAR) was generated by the ISI group, on April 2, 1997, to request that surveillance test recurring tasks (RT) for valves 2CC195 and 2CC210 be generated to test these check valves on a 92 day frequency. The valves were then added to the ISI procedure for radiography on April 4, 1997. Although the request for generation of the surveillance test RTs was generated in April, the request was not received by the Technical Specification Administrator, who is responsible for implementing changes to the surveillance testing RT, until May 6. The surveillance test recurring task request generated by the ISI group did not identify when the previous surveillance test was performed or when the next surveillance test was required to be performed in accordance with the administrative procedure. Although the date for required completion of the next surveillance test was not specified in the description of the BPAR, the Technical Specification Administrator, by coincidence, assigned a completion date for creation of the new surveillance testing RT of June 15, 1997 (this date corresponds to the 92 day surveillance interval plus the 25% extension allowed by TS 4.0.2). However, the task for completion of the new surveillance testing RT was extended by the Technical Specification Administrator to June 27, 1997, without the recognition that the surveillance test would go overdue. Upon generation of the request for creation of the new surveillance test RT, the ISI group also did not verify that the recurring task would be issued prior to the due date of the next required surveillance test. |
| : 2. The recurring task for generation of the next surveillance tests for 2CC195 and 2CC210 on a 92 day frequency was issued on June 25, 1997. 3. A review of outstanding surveillance testing recurring task change requests was performed to determine if any further surveillance testing was overdue. The review identified that no other surveillance testing was overdue. 4. A review of the administrative controls for creation and revision to surveillance testing recurring tasks is being performed to determine if further enhancements to the administrative controls are required. | | Upon identification that the 4.0.5 surveillance testing for 2CC195 and 2CC210 was overdue, the check valves were radiographed on June 23, 1997 and the new surveillance testing RT was generated on June 25, 1997. |
| This review will be completed by October 31, 1997. 5. A Station Key Message will be distributed to NBU department personnel, reemphasizing the information required by NC.NA-AP.ZZ-0012, "Technical Specifications Surveillance Program," for generation of surveillance testing recurring task changes. This Key Message will be distributed by July 28, 1997. 6. Appropriate disciplinary actions were taken in accordance with PSE&G's policies for the Technical Specification Administrator. | | CAUSE OF OCCURRENCE - -~ |
| -7. Appropriate disciplinary actions were taken in accordance with PSE&G'S policies for the ISI personnel involved in this event. NRC FORM 366A (4-95) 4}}
| | The cause of this occurrence is attributed to personnel error. The ISI group did not verify that the new surveillance testing RT would be generated prior to the due date of the next surveillance test. Also, the Technical Specification Administrator extended the task for generation of the new surveillance testing RT without recognizing that the next surveillance test would go overdue. |
| | PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 submitted in the past two years did not identify any additional reportable occurrences as a result of the failure to generate a recurring task for creation of surveillance testing work orders. |
| | Although numerous LERs have been written in the past two years for missed surveillance testing, these incidents have been attributed to a lack of adequate controls on the development and maintenance of Technical Specification surveillance procedures. |
| | NRG FORM 366A (4-95) |
| | |
| | -f NRC FORM 366A (4-95) |
| | U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 4 OF 4 SALEM GENERATING STATION UNIT 2 97 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) |
| | SAFETY SIGNIFICANCE The testing of check valves 2CC195 and 2CC210 on June 23, 1997, demonstrated that the check valves were closed and provided the proper ASME Code boundary. |
| | Therefore there was no impact to the health and safety of the public. |
| | CORRECTIVE ACTIONS |
| | : 1. Check valves 2CC195 and 2CC210 were radiographed on June 23, 1997 and determined to be in their proper position (closed position). |
| | : 2. The recurring task for generation of the next surveillance tests for 2CC195 and 2CC210 on a 92 day frequency was issued on June 25, 1997. |
| | : 3. A review of outstanding surveillance testing recurring task change requests was performed to determine if any further surveillance testing was overdue. |
| | The review identified that no other surveillance testing was overdue. |
| | : 4. A review of the administrative controls for creation and revision to surveillance testing recurring tasks is being performed to determine if further enhancements to the administrative controls are required. This review will be completed by October 31, 1997. |
| | : 5. A Station Key Message will be distributed to NBU department personnel, reemphasizing the information required by NC.NA-AP.ZZ-0012, "Technical Specifications Surveillance Program," for generation of surveillance testing recurring task changes. This Key Message will be distributed by July 28, 1997. |
| | : 6. Appropriate disciplinary actions were taken in accordance with PSE&G's policies for the - -~ |
| | Technical Specification Administrator. |
| | : 7. Appropriate disciplinary actions were taken in accordance with PSE&G'S policies for the ISI personnel involved in this event. |
| | NRC FORM 366A (4-95)}} |
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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: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
[Table view] |
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( 0 PS~G
. Public _Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 2 3 1997 LR-N970456 U. S. Nuclear Regulatory Commission Document Contr61 Desk Washington, DC 20555 Gentlemen:
LER 311/97-007-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed 4.0.5 Testing of Check Valves 2CC195 and 2CC210," is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).
cror:ly
- -~,
David F. Garchow General Manager -
Salem Operations Attachment BJT C Distribution LER File 3.7 9707300043 970723 PDR ADOCK 05000311 S PDR
\\\\\\\ \\\\\ \\\\\ \\\\\\\\\\\\\\\ \\\\ \\\\
95*2168 REV. 6/94
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NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) 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 LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20555--0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150--0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3)
SALEM GENERATING STATION UNIT 2 05000311 1 OF 4 TITLE(.()
Missed 4.0.5 Testing of Check Valves 2CC195 and 2CC210 EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR SEQUENTIAL IREVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER I NUMBER NUMBER FACILITY NAME DOCKET NUMBER 06 23 97 97 - 007 - 00 07 23 97 OPERATING 4 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)
MODE (9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii)
POWER 000 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(><)
LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71
-
20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) Spec~in Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50. 73(a)(2)(vii)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TONPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSION
'YES (If yes, EXPECTED SUBMISSION DATE). XINO complete DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On June 23, 1997 ,- *the Technical Specification (TS) 4. 0. 5 Inservice Inspection (ISI) requirement to perform radiography of check valves 2CC195 and 2CC210 every 92 days was determined to have been missed. As a result of the missed surveillance, one loop of the component cooling water was declared inoperable until the surveillance testing (radiography) was completed. Since the missed surveillance test exceeded the surveillance test interval, the 25% extension allowed by TS 4. 0. 2' and the Limiting Condition for Operation (LCO) statement time, this event is reportable in accordance with 10CFR50.73(a) (2) (i) (B) as, "any condition prohibited by the plant's Technical Specifications."
The cause of this occurrence is attributed to personnel error. The recurring task for performing the next 92 day surveillance was not generated prior to the expiration of the surveillance test interval. The check valves were subsequently tested and determined to be in their proper position. The personnel involved in this event have received appropriate disciplinary actions.
NRC FORM 366 (4-95)
~ t NRC FORM 366A (4-95)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000311 YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 2 OF 4 SALEM GENERATING STATION UNIT 2 97 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Component Cooling Water System {CB/-}*
- Energy Industry Identification System (EIIS) codes and component function identifier codes appear as {SS/CCC} in the text.
CONDITIONS PRIOR TO OCCURRENCE The plant was in Mode 4 prior to the event.
DESCRIPTION OF OCCURRENCE On June 23, 1997, the Technical Specification (TS) 4.0.5 Inservice Inspection (ISI) requirement to perform radiography of check valves 2CC195 and 2CC210 every 92 days was determined to have been missed. The 92 day surveillance plus the 25% surveillance extension provided by TS 4.0.2 was due on June 15, 1997. Upon identification of the overdue surveillance for the 2CC195 and 2CC210 valves, the check valves were radiographed on June 23, 1997, and were determined to be in their proper position (closed). As a result of the missed surveillance, one loop of the component cooling water was declared inoperable until the surveillance testing (radiography) was completed. Since the missed surveillance test exceeded the surveillance test interval, the 25% extension allowed by TS 4.0.2, and the Limiting Condition for Operation (LCO) statement time, this event is reportable in accordance with 10CFR50.73(a) (2) (i) (B) as, "any condition prohibited by the plant's Technical Specifications."
ANALYSIS OF OCCURRENCE In February of 19if7, the Inservice Testing (IST) group identified that check valves 1(2)CC195 and 1(2)CC210 for the component cooling system were required to be tested in the reverse direction for ASME Class 3 boundary isolation on a 92 day frequency. As a result of the identification of the requirement to test check valves CC195 and CC210 in the closed position, valves 2CC195 and 2CC210 were radiographed on February 21, 1997 to verify that they were fully closed and fulfilling their function as the ASME Class 3 boundary. Completion of the radiography on February 21 then started the 92 day surveillance interval for the next surveillance test. The past reportability for failure to perform surveillance testing of the CC195 and CC2LO valves prior to February of 1997 will be addressed in Supplemental LER 272/97-001-01.
NRC FORM 366A (4-95)
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION
'* (4-95)
LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 0 5 0 0 0 311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 3 OF 4 SALEM GENERATING STATION UNIT 2 97 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
ANALYSIS OF OCCURRENCE (cont'd)
As a result of the identification of the need to perform surveillance testing of check valves CC195 and CC210, a Business Process Action Request (BPAR) was generated by the ISI group, on April 2, 1997, to request that surveillance test recurring tasks (RT) for valves 2CC195 and 2CC210 be generated to test these check valves on a 92 day frequency. The valves were then added to the ISI procedure for radiography on April 4, 1997. Although the request for generation of the surveillance test RTs was generated in April, the request was not received by the Technical Specification Administrator, who is responsible for implementing changes to the surveillance testing RT, until May 6. The surveillance test recurring task request generated by the ISI group did not identify when the previous surveillance test was performed or when the next surveillance test was required to be performed in accordance with the administrative procedure. Although the date for required completion of the next surveillance test was not specified in the description of the BPAR, the Technical Specification Administrator, by coincidence, assigned a completion date for creation of the new surveillance testing RT of June 15, 1997 (this date corresponds to the 92 day surveillance interval plus the 25% extension allowed by TS 4.0.2). However, the task for completion of the new surveillance testing RT was extended by the Technical Specification Administrator to June 27, 1997, without the recognition that the surveillance test would go overdue. Upon generation of the request for creation of the new surveillance test RT, the ISI group also did not verify that the recurring task would be issued prior to the due date of the next required surveillance test.
Upon identification that the 4.0.5 surveillance testing for 2CC195 and 2CC210 was overdue, the check valves were radiographed on June 23, 1997 and the new surveillance testing RT was generated on June 25, 1997.
CAUSE OF OCCURRENCE - -~
The cause of this occurrence is attributed to personnel error. The ISI group did not verify that the new surveillance testing RT would be generated prior to the due date of the next surveillance test. Also, the Technical Specification Administrator extended the task for generation of the new surveillance testing RT without recognizing that the next surveillance test would go overdue.
PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 submitted in the past two years did not identify any additional reportable occurrences as a result of the failure to generate a recurring task for creation of surveillance testing work orders.
Although numerous LERs have been written in the past two years for missed surveillance testing, these incidents have been attributed to a lack of adequate controls on the development and maintenance of Technical Specification surveillance procedures.
NRG FORM 366A (4-95)
-f NRC FORM 366A (4-95)
U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 4 OF 4 SALEM GENERATING STATION UNIT 2 97 - 007 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
SAFETY SIGNIFICANCE The testing of check valves 2CC195 and 2CC210 on June 23, 1997, demonstrated that the check valves were closed and provided the proper ASME Code boundary.
Therefore there was no impact to the health and safety of the public.
CORRECTIVE ACTIONS
- 1. Check valves 2CC195 and 2CC210 were radiographed on June 23, 1997 and determined to be in their proper position (closed position).
- 2. The recurring task for generation of the next surveillance tests for 2CC195 and 2CC210 on a 92 day frequency was issued on June 25, 1997.
- 3. A review of outstanding surveillance testing recurring task change requests was performed to determine if any further surveillance testing was overdue.
The review identified that no other surveillance testing was overdue.
- 4. A review of the administrative controls for creation and revision to surveillance testing recurring tasks is being performed to determine if further enhancements to the administrative controls are required. This review will be completed by October 31, 1997.
- 5. A Station Key Message will be distributed to NBU department personnel, reemphasizing the information required by NC.NA-AP.ZZ-0012, "Technical Specifications Surveillance Program," for generation of surveillance testing recurring task changes. This Key Message will be distributed by July 28, 1997.
- 6. Appropriate disciplinary actions were taken in accordance with PSE&G's policies for the - -~
Technical Specification Administrator.
- 7. Appropriate disciplinary actions were taken in accordance with PSE&G'S policies for the ISI personnel involved in this event.
NRC FORM 366A (4-95)
