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| {{#Wiki_filter:e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 26, 1993 u. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | {{#Wiki_filter:e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 26, 1993 |
| | : u. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 |
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| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 93-003-00 This Licensee Event requirements of the 50.73(a) (2) (i) (B). thirty (30) days of Report is being submitted pursuant to the Code of Federal Regulations lOCFR MJP:pc Distribution This report is required to be issued within event discovery. | | |
| 04f"Ol2 Sincerely yours, 1/dt? o-Lj-r-' /&---A. Vondra -General Manager -Salem Operations The Energy People 9303040157 930226 PDR ADOCK 05000311 . f-I ,jtJ I S PDR 95-2189 ( 1 OM) 12-89
| | SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 93-003-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B). This report is required to be issued within thirty (30) days of event discovery. |
| ' i
| | Sincerely yours, 1/dt? |
| * I NRC FQRM 366 (6-89) U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 LICENSEE EVENT REPORT (LERI EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME (1) 'DOCKET NUMBER (2) I PAGE (3) Salem Generating Station -Unit 2 o 15 I o Io I o I 31 111 1 loF 0 I 4 TITLE (4) Tech. Spec. 3.0.3 Entry; Inoperability of Both Boric Acid Storage Tank's Level Indication EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REVlSION MONTH NUMBER DAY YEAR FACILITY NAMES DOCKET NUMBER(S) 0 11 1 OPERATING MODE (9) 9: 3 2 0 15 Io I o 1 o I I I 913 -ala I 3 -a I a oj 216 913 2 o,s,o,o,o, I I THIS REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §: (Chock on* or mar* of th* following) | | /&--- A. Vondra o-Lj-r-' |
| (11) 20.402(b) 20.405(c) 50.73(*)(2)(iv) 73.71(b) --- | | ~ -General Manager - |
| ....... POWER I 20.406(*)(1
| | Salem Operations MJP:pc Distribution 04f"Ol2 |
| )(i) 50.38(c)(1) 50.73(*)(2)(v) 73.71(c) --r--50.38(c)(2) 50.73(*)(2)(vii) | | . f-The Energy People 9303040157 930226 PDR ADOCK 05000311 |
| OTHER in Abstroct 0 I 0 I 11--20.405(*)(1)(1i)
| | ,jtJ I I |
| NAME 20.4061*111 Hill) 20.406(*)(1)(iv) 20.406l*ll1lM
| | 95-2189 ( 1OM) 12-89 S PDR |
| ..__ ......... | | |
| x 50.73(*)(2)(i)
| | i |
| -,._ 50.73(*)(2)(ii)
| | * NRC FQRM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89) |
| ..__ ......... | | I EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| 50.7:il*H2Hiii) | | FACILITY NAME (1) DOCKET NUMBER (2) I PAGE (3) |
| LICENSEE CONTACT FOR THIS LER (12) r--below and in Text. NRC Form 50.73(*)(2)(viii)(A) 366A) 50.73(*112Hviii)(B) 50.73(*11211*)
| | Salem Generating Station - Unit 2 o 15 I o Io I o I 31 111 1 loF 0 I 4 TITLE (4) |
| TELEPHONE NUMBER AREA CODE M. J. Pollack -LER Coordinator 6 I 0 I 9 3 I 3 I 9 I-I 2 I 0 12 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT I I I I I I I I TURER I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) n YES (If YBS. compl*t* EXPECTED SUBMISSION DATE) ABSTRACT (Limit to 1400 spaces, i.e., approximately fiftaen single-space typewritten lines} (16) I I I I I I I I MANUFAC* TUR ER I I I I I I EXPECTED SUBMISSION DATE 1151 MONTH DAY YEAR I I I On 1/31/93, at 2220 hours, the level indicator of 21 BAST was declared inoperable due to false high level indications. | | Tech. Spec. 3.0.3 Entry; Inoperability of Both Boric Acid Storage Tank's Level Indication EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8) |
| 22 BAST was undergoing batching operation at the time. Therefore, Action 3 of Technical Specification Table 3.3-11 was not met, and the action associated with Technical Specification 3.0.3 was entered. Technical Specification 3.0.3 was exited on 1/31/93, at 2242 hours, upon restoration of 21 BAST level indication to service. The root cause of this event is "Design, Manufacturing, Construction/Installation" of the BAST level indication system. BAST level indication failures have been a recurring problem at both Salem Units. They have been determined to be due to bubbler tube blockage. | | :f~t~ ~t~t NUMBER SEQUENTIAL REVlSION FACILITY NAMES DOCKET NUMBER(S) |
| The Unit 2 21 BAST bubbler is scheduled for cleaning. | | MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER 0 15 Io I o 1 o I I I 0 11 ~ 1 9: 3 913 |
| The Unit 2 22 BAST bubbler has been cleaned. The corresponding Unit 1 11 and 12 BAST's and the bubbler tubes of each tank have been inspected and cleaned. In addition, the bubbler tube nitrogen flow rates of both Salem Units have been readjusted to 3 scfh, to minimize boric acid precipitation. | | - ala I 3 - a I a oj 2 216 913 o,s,o,o,o, I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF 10 CFR §: (Chock on* or mar* of th* following) (11) 1---~~~~~ |
| A design change is being developed which includes reducing BAST boron concentration. | | MODE (9) |
| This will help minimize boron precipitation in the level indicator bubbler tubes. System Engineering is continuing to monitor BAST level indication failures to determine adequacy of current corrective action. NRC Form 366 (6-89) | | POWER L~~~L I 0 I 0 I 11-- |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 PLANT AND SYSTEM IDENTIFICATION: | | 2 |
| Westinghouse | | .......~~~ |
| -Pressurized Water Reactor LER NUMBER 93-003-00 PAGE 2 of 4 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE: | | 20.402(b) 20.406(*)(1 )(i) 20.405(*)(1)(1i) 20.405(c) 50.38(c)(1) 50.38(c)(2) 50.73(*)(2)(iv) 50.73(*)(2)(v) 50.73(*)(2)(vii) r-- |
| Technical Specification 3.0.3 entry; Inoperability of Both Boric Acid Storage Tanks' Level Indication Event Dates: Report Date: 1/31/93 2/26/93 This report was initiated by Incident Report No. 93-093. CONDITIONS PRIOR TO OCCURRENCE: | | 73.71(b) 73.71(c) |
| Mode 2 Reactor Power 1.5% -Unit Load O MWe 22 Boric Acid Storage Tank (BAST) was out of service in support of batching operations DESCRIPTION OF OCCURRENCES: | | OTHER IS~cify in Abstroct |
| At 2220 hours, on January 31, 1993, the level indicator of 21 BAST {CB} was declared due to false high level indications. | | - x r-- below and in Text. NRC Form 20.4061*111 Hill) 50.73(*)(2)(i) 50.73(*)(2)(viii)(A) 366A) 20.406(*)(1)(iv) 50.73(*)(2)(ii) 50.73(*112Hviii)(B) 20.406l*ll1lM 50.7:il*H2Hiii) 50.73(*11211*) |
| 22 BAST was undergoing batching operation at the time. Therefore, Action 3 of Technical Specification Table 3.3-11 was not met, and the action associated with Technical Specification 3.0.3 was entered. Technical Specification 3.0.3 was exited on January 31, 1993, at 2242 hours, upon restoration of 21 BAST level indication to service. In Modes 1, 2, and 3, Technical Specification 3.3.3.7 requires two (2) OPERABLE BAST solution level indicators (one/tank). | | LICENSEE CONTACT FOR THIS LER (12) |
| With one level indicator inoperable, Technical Specification Table 3.3-11 Action 3 applies: "With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of Specification 3.1.2.8.a." Technical Specification 3.1.2.6 states: "Each of the following borated water sources shall be OPERABLE: | | NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 6 I 0 I 9 3 I 3 I 9 I- I 2 I 0 12 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | MANUFAC- MANUFAC* |
| | CAUSE SYSTEM COMPONENT TURER TUR ER I I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED n YES (If YBS. compl*t* EXPECTED SUBMISSION DATE) |
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately fiftaen single-space typewritten lines} (16) |
| | SUBMISSION DATE 1151 I I I On 1/31/93, at 2220 hours, the level indicator of 21 BAST was declared inoperable due to false high level indications. 22 BAST was undergoing batching operation at the time. Therefore, Action 3 of Technical Specification Table 3.3-11 was not met, and the action associated with Technical Specification 3.0.3 was entered. Technical Specification 3.0.3 was exited on 1/31/93, at 2242 hours, upon restoration of 21 BAST level indication to service. The root cause of this event is "Design, Manufacturing, Construction/Installation" of the BAST level indication system. BAST level indication failures have been a recurring problem at both Salem Units. They have been determined to be due to bubbler tube blockage. The Unit 2 21 BAST bubbler is scheduled for cleaning. The Unit 2 22 BAST bubbler has been cleaned. The corresponding Unit 1 11 and 12 BAST's and the bubbler tubes of each tank have been inspected and cleaned. In addition, the bubbler tube nitrogen flow rates of both Salem Units have been readjusted to 3 scfh, to minimize boric acid precipitation. A design change is being developed which includes reducing BAST boron concentration. This will help minimize boron precipitation in the level indicator bubbler tubes. System Engineering is continuing to monitor BAST level indication failures to determine adequacy of current corrective action. |
| | NRC Form 366 (6-89) |
| | |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-003-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION: |
| | Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx} |
| | IDENTIFICATION OF OCCURRENCE: |
| | Technical Specification 3.0.3 entry; Inoperability of Both Boric Acid Storage Tanks' Level Indication Event Dates: 1/31/93 Report Date: 2/26/93 This report was initiated by Incident Report No. 93-093. |
| | CONDITIONS PRIOR TO OCCURRENCE: |
| | Mode 2 Reactor Power 1.5% - Unit Load O MWe 22 Boric Acid Storage Tank (BAST) was out of service in support of batching operations DESCRIPTION OF OCCURRENCES: |
| | At 2220 hours, on January 31, 1993, the level indicator of 21 BAST |
| | {CB} was declared inop~rable due to false high level indications. 22 BAST was undergoing batching operation at the time. Therefore, Action 3 of Technical Specification Table 3.3-11 was not met, and the action associated with Technical Specification 3.0.3 was entered. |
| | Technical Specification 3.0.3 was exited on January 31, 1993, at 2242 hours, upon restoration of 21 BAST level indication to service. |
| | In Modes 1, 2, and 3, Technical Specification 3.3.3.7 requires two (2) |
| | OPERABLE BAST solution level indicators (one/tank). With one level indicator inoperable, Technical Specification Table 3.3-11 Action 3 applies: |
| | "With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of Specification 3.1.2.8.a." |
| | Technical Specification 3.1.2.6 states: |
| | "Each of the following borated water sources shall be OPERABLE: |
| : a. A boric acid storage system and at least one associated heat tracing system with: | | : a. A boric acid storage system and at least one associated heat tracing system with: |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 93-003-00 DESCRIPTION OF OCCURRENCE: (cont'd) b. 1. 2. 3. The A minimum contained volume of 5106 gallons, Between 20,000 and 22,500 ppm of boron, and, A minimum solution temperature of 145°F. refueling water storage tank with: 11 Technical Specification
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| ====3.0.3 states====
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-003-00 3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd) |
| PAGE 3 of 4 "When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: 1. At least HOT STANDBY within the next 6 hours, 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTDOWN within the subsequent 24 hours. Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation.
| | : 1. A minimum contained volume of 5106 gallons, |
| Exceptions to these requirements are stated in the individual specifications." APPARENT CAUSE OF OCCURRENCE: | | : 2. Between 20,000 and 22,500 ppm of boron, and, |
| | : 3. A minimum solution temperature of 145°F. |
| | : b. The refueling water storage tank with: 11 Technical Specification 3.0.3 states: |
| | "When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: |
| | : 1. At least HOT STANDBY within the next 6 hours, |
| | : 2. At least HOT SHUTDOWN within the following 6 hours, and |
| | : 3. At least COLD SHUTDOWN within the subsequent 24 hours. |
| | Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation. |
| | Exceptions to these requirements are stated in the individual specifications." |
| | APPARENT CAUSE OF OCCURRENCE: |
| The root cause of this event is "Design, Manufacturing, Construction/ | | The root cause of this event is "Design, Manufacturing, Construction/ |
| Installation" (per NUREG 1022, "Licensee Event Report System") of the BAST level indication system. BAST level indication failures have been a recurring problem at both Salem Units. The BAST level indicator sensing design employs a nitrogen flow bubbler tube, which opens near the tank bottom, and another tube which opens near the tank top. Resultant differential pressure between the tubes is used to determine level. The recurrent failures result from bubbler tube blockage. | | Installation" (per NUREG 1022, "Licensee Event Report System") of the BAST level indication system. BAST level indication failures have been a recurring problem at both Salem Units. |
| Several past corrective actions have been unsuccessful. | | The BAST level indicator sensing design employs a nitrogen flow bubbler tube, which opens near the tank bottom, and another tube which opens near the tank top. Resultant differential pressure between the tubes is used to determine level. |
| These included increasing the nitrogen purge flow rate from 6 to 8 standard cubic feet per hour (scfh), increasing the frequency of system blowdown from every 92 days to once every seven days, and snaking out and brush cleaning the bubbler tube. As addressed by LER 272/93-003-00, visual inspection and cleaning of Unit 1 12 BAST revealed boron slug accumulation in the bubbler tube bottom two inches. A pinhole passage through the slug had permitted sufficient nitrogen purge flow through the tube which allowed the indicator to function until complete blockage. | | The recurrent failures result from bubbler tube blockage. Several past corrective actions have been unsuccessful. These included increasing the nitrogen purge flow rate from 6 to 8 standard cubic feet per hour (scfh), increasing the frequency of system blowdown from every 92 days to once every seven days, and snaking out and brush cleaning the bubbler tube. |
| Precipitation occurs when 22,000 ppm boron solution temperature decreases below 145° F. As such, it has been determined that lower nitrogen flow rates (i.e. less than 6 scfh) are desirable in the bubbler tube. | | As addressed by LER 272/93-003-00, visual inspection and cleaning of Unit 1 12 BAST revealed boron slug accumulation in the bubbler tube bottom two inches. A pinhole passage through the slug had permitted sufficient nitrogen purge flow through the tube which allowed the indicator to function until complete blockage. Precipitation occurs when 22,000 ppm boron solution temperature decreases below 145° F. |
| LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 ANALYSIS OF OCCURRENCE: | | As such, it has been determined that lower nitrogen flow rates (i.e. less than 6 scfh) are desirable in the bubbler tube. |
| DOCKET NUMBER 5000311 LER NUMBER 93-003-00 PAGE 4 of 4 This event did not affect the health and safety to the public. The boron injection system ensures that negative reactivity control is available during each mode of facility operation. | | |
| Required components include two (2) borated water sources, the two (2) BASTS and the Refueling Water Storage Tank. Either BAST contains sufficient volume to support one cold shutdown with the most reactive control rod withdrawn. | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-003-00 4 of 4 ANALYSIS OF OCCURRENCE: |
| These tanks contain 12 weight % boric acid maintained at a temperature of 175°F. During the events reported in this LER, the Refueling Water Storage Tank remained available. | | This event did not affect the health and safety to the public. The boron injection system ensures that negative reactivity control is available during each mode of facility operation. Required components include two (2) borated water sources, the two (2) BASTS and the Refueling Water Storage Tank. Either BAST contains sufficient volume to support one cold shutdown with the most reactive control rod withdrawn. These tanks contain 12 weight % boric acid maintained at a temperature of 175°F. |
| Also, although its level indication had failed, required level was maintained in No. 21 BAST. This event is reportable to the NRC per lOCFR 50.73(a) (2) (i) (B) due to entering Technical Specification 3.0.3. CORRECTIVE ACTION: The 21 BAST level indicator bubbler tube was blown down to remove blockage. | | During the events reported in this LER, the Refueling Water Storage Tank remained available. Also, although its level indication had failed, required level was maintained in No. 21 BAST. This event is reportable to the NRC per 10CFR 50.73(a) (2) (i) (B) due to entering Technical Specification 3.0.3. |
| The indicator was then determined "OPERABLE" and returned to service. The Unit 2 22 BAST bubbler has been cleaned. The Unit 2 21 BAST bubbler is scheduled for cleaning. | | CORRECTIVE ACTION: |
| The corresponding Unit 1 11 and 12 BAST's and the bubbler tubes of each tank have been inspected and cleaned. In addition, the bubbler tube nitrogen flow rates of both Salem Units have been readjusted to 3 scfh, to minimize boric acid precipitation. | | The 21 BAST level indicator bubbler tube was blown down to remove blockage. The indicator was then determined "OPERABLE" and returned to service. |
| A design change is being developed which includes reducing BAST boron concentration. | | The Unit 2 22 BAST bubbler has been cleaned. The Unit 2 21 BAST bubbler is scheduled for cleaning. The corresponding Unit 1 11 and 12 BAST's and the bubbler tubes of each tank have been inspected and cleaned. In addition, the bubbler tube nitrogen flow rates of both Salem Units have been readjusted to 3 scfh, to minimize boric acid precipitation. |
| This will help minimize boron precipitation in the level indicator bubbler tubes. System Engineering is continuing to monitor BAST level indication failures to determine adequacy of current corrective action and to determine additional actions, such as periodic steam cleaning, until implementation of the design change. MJP:pc SORC Mtg. 93-019 _1/d-t/c.L?? | | A design change is being developed which includes reducing BAST boron concentration. This will help minimize boron precipitation in the level indicator bubbler tubes. |
| Manager ---Salem Operations}} | | System Engineering is continuing to monitor BAST level indication failures to determine adequacy of current corrective action and to determine additional actions, such as periodic steam cleaning, until implementation of the design change. |
| | _1/d-t/c.L?? |
| | ~eneral Manager - |
| | ~ --Salem Operations MJP:pc SORC Mtg. 93-019}} |
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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: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] |
Text
e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station February 26, 1993
- u. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT 93-003-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B). This report is required to be issued within thirty (30) days of event discovery.
Sincerely yours, 1/dt?
/&--- A. Vondra o-Lj-r-'
~ -General Manager -
Salem Operations MJP:pc Distribution 04f"Ol2
. f-The Energy People 9303040157 930226 PDR ADOCK 05000311
,jtJ I I
95-2189 ( 1OM) 12-89 S PDR
i
- NRC FQRM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89)
I EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LERI COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) I PAGE (3)
Salem Generating Station - Unit 2 o 15 I o Io I o I 31 111 1 loF 0 I 4 TITLE (4)
Tech. Spec. 3.0.3 Entry; Inoperability of Both Boric Acid Storage Tank's Level Indication EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
- f~t~ ~t~t NUMBER SEQUENTIAL REVlSION FACILITY NAMES DOCKET NUMBER(S)
MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER 0 15 Io I o 1 o I I I 0 11 ~ 1 9: 3 913
- ala I 3 - a I a oj 2 216 913 o,s,o,o,o, I I OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTS OF 10 CFR §: (Chock on* or mar* of th* following) (11) 1---~~~~~
MODE (9)
POWER L~~~L I 0 I 0 I 11--
2
.......~~~
20.402(b) 20.406(*)(1 )(i) 20.405(*)(1)(1i) 20.405(c) 50.38(c)(1) 50.38(c)(2) 50.73(*)(2)(iv) 50.73(*)(2)(v) 50.73(*)(2)(vii) r--
73.71(b) 73.71(c)
OTHER IS~cify in Abstroct
- x r-- below and in Text. NRC Form 20.4061*111 Hill) 50.73(*)(2)(i) 50.73(*)(2)(viii)(A) 366A) 20.406(*)(1)(iv) 50.73(*)(2)(ii) 50.73(*112Hviii)(B) 20.406l*ll1lM 50.7:il*H2Hiii) 50.73(*11211*)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE M. J. Pollack - LER Coordinator 6 I 0 I 9 3 I 3 I 9 I- I 2 I 0 12 I 2 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANUFAC- MANUFAC*
CAUSE SYSTEM COMPONENT TURER TUR ER I I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED n YES (If YBS. compl*t* EXPECTED SUBMISSION DATE)
ABSTRACT (Limit to 1400 spaces, i.e., approximately fiftaen single-space typewritten lines} (16)
SUBMISSION DATE 1151 I I I On 1/31/93, at 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, the level indicator of 21 BAST was declared inoperable due to false high level indications. 22 BAST was undergoing batching operation at the time. Therefore, Action 3 of Technical Specification Table 3.3-11 was not met, and the action associated with Technical Specification 3.0.3 was entered. Technical Specification 3.0.3 was exited on 1/31/93, at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br />, upon restoration of 21 BAST level indication to service. The root cause of this event is "Design, Manufacturing, Construction/Installation" of the BAST level indication system. BAST level indication failures have been a recurring problem at both Salem Units. They have been determined to be due to bubbler tube blockage. The Unit 2 21 BAST bubbler is scheduled for cleaning. The Unit 2 22 BAST bubbler has been cleaned. The corresponding Unit 1 11 and 12 BAST's and the bubbler tubes of each tank have been inspected and cleaned. In addition, the bubbler tube nitrogen flow rates of both Salem Units have been readjusted to 3 scfh, to minimize boric acid precipitation. A design change is being developed which includes reducing BAST boron concentration. This will help minimize boron precipitation in the level indicator bubbler tubes. System Engineering is continuing to monitor BAST level indication failures to determine adequacy of current corrective action.
NRC Form 366 (6-89)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-003-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Technical Specification 3.0.3 entry; Inoperability of Both Boric Acid Storage Tanks' Level Indication Event Dates: 1/31/93 Report Date: 2/26/93 This report was initiated by Incident Report No.93-093.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 2 Reactor Power 1.5% - Unit Load O MWe 22 Boric Acid Storage Tank (BAST) was out of service in support of batching operations DESCRIPTION OF OCCURRENCES:
At 2220 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.4471e-4 months <br />, on January 31, 1993, the level indicator of 21 BAST
{CB} was declared inop~rable due to false high level indications. 22 BAST was undergoing batching operation at the time. Therefore, Action 3 of Technical Specification Table 3.3-11 was not met, and the action associated with Technical Specification 3.0.3 was entered.
Technical Specification 3.0.3 was exited on January 31, 1993, at 2242 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.53081e-4 months <br />, upon restoration of 21 BAST level indication to service.
In Modes 1, 2, and 3, Technical Specification 3.3.3.7 requires two (2)
OPERABLE BAST solution level indicators (one/tank). With one level indicator inoperable, Technical Specification Table 3.3-11 Action 3 applies:
"With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of Specification 3.1.2.8.a."
Technical Specification 3.1.2.6 states:
"Each of the following borated water sources shall be OPERABLE:
- a. A boric acid storage system and at least one associated heat tracing system with:
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-003-00 3 of 4 DESCRIPTION OF OCCURRENCE: (cont'd)
- 1. A minimum contained volume of 5106 gallons,
- 2. Between 20,000 and 22,500 ppm of boron, and,
- 3. A minimum solution temperature of 145°F.
- b. The refueling water storage tank with: 11 Technical Specification 3.0.3 states:
"When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
- 1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- 2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition of Operation.
Exceptions to these requirements are stated in the individual specifications."
APPARENT CAUSE OF OCCURRENCE:
The root cause of this event is "Design, Manufacturing, Construction/
Installation" (per NUREG 1022, "Licensee Event Report System") of the BAST level indication system. BAST level indication failures have been a recurring problem at both Salem Units.
The BAST level indicator sensing design employs a nitrogen flow bubbler tube, which opens near the tank bottom, and another tube which opens near the tank top. Resultant differential pressure between the tubes is used to determine level.
The recurrent failures result from bubbler tube blockage. Several past corrective actions have been unsuccessful. These included increasing the nitrogen purge flow rate from 6 to 8 standard cubic feet per hour (scfh), increasing the frequency of system blowdown from every 92 days to once every seven days, and snaking out and brush cleaning the bubbler tube.
As addressed by LER 272/93-003-00, visual inspection and cleaning of Unit 1 12 BAST revealed boron slug accumulation in the bubbler tube bottom two inches. A pinhole passage through the slug had permitted sufficient nitrogen purge flow through the tube which allowed the indicator to function until complete blockage. Precipitation occurs when 22,000 ppm boron solution temperature decreases below 145° F.
As such, it has been determined that lower nitrogen flow rates (i.e. less than 6 scfh) are desirable in the bubbler tube.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-003-00 4 of 4 ANALYSIS OF OCCURRENCE:
This event did not affect the health and safety to the public. The boron injection system ensures that negative reactivity control is available during each mode of facility operation. Required components include two (2) borated water sources, the two (2) BASTS and the Refueling Water Storage Tank. Either BAST contains sufficient volume to support one cold shutdown with the most reactive control rod withdrawn. These tanks contain 12 weight % boric acid maintained at a temperature of 175°F.
During the events reported in this LER, the Refueling Water Storage Tank remained available. Also, although its level indication had failed, required level was maintained in No. 21 BAST. This event is reportable to the NRC per 10CFR 50.73(a) (2) (i) (B) due to entering Technical Specification 3.0.3.
CORRECTIVE ACTION:
The 21 BAST level indicator bubbler tube was blown down to remove blockage. The indicator was then determined "OPERABLE" and returned to service.
The Unit 2 22 BAST bubbler has been cleaned. The Unit 2 21 BAST bubbler is scheduled for cleaning. The corresponding Unit 1 11 and 12 BAST's and the bubbler tubes of each tank have been inspected and cleaned. In addition, the bubbler tube nitrogen flow rates of both Salem Units have been readjusted to 3 scfh, to minimize boric acid precipitation.
A design change is being developed which includes reducing BAST boron concentration. This will help minimize boron precipitation in the level indicator bubbler tubes.
System Engineering is continuing to monitor BAST level indication failures to determine adequacy of current corrective action and to determine additional actions, such as periodic steam cleaning, until implementation of the design change.
_1/d-t/c.L??
~eneral Manager -
~ --Salem Operations MJP:pc SORC Mtg.93-019