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| | issue date = 11/23/1993 | | | issue date = 11/23/1993 |
| | title = LER 93-012-00:on 931030,TS 3.0.3 Entered Due to Inoperability of 21 Bast Level Indication While 22 Bast Out of Svc.Caused by Design Deficiency.Design Change Installed. W/931123 Ltr | | | title = LER 93-012-00:on 931030,TS 3.0.3 Entered Due to Inoperability of 21 Bast Level Indication While 22 Bast Out of Svc.Caused by Design Deficiency.Design Change Installed. W/931123 Ltr |
| | author name = PASTVA M J, VONDRA C A | | | author name = Pastva M, Vondra C |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:. I e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station ** | | {{#Wiki_filter:. I e |
| * u. s. Nuclear Regulatory commission Document Control Desk . Washington, DC 20555 | | OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 23, 1993 |
| | ** |
| | * u. s. Nuclear Regulatory commission Document Control Desk |
| | . Washington, DC 20555 |
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| |
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| ==Dear Sir:== | | ==Dear Sir:== |
| SALEM GENERATING STATION LICENSE NO. DPR-75 November 23, 1993 ------*----DOCKET. N0 *.. | | |
| -------UNIT NO. 2 LICENSEE EVENT REPORT 93-012-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) | | SALEM GENERATING STATION LICENSE NO. DPR-75 |
| (2) (i) (B). This report is required to be issued within thirty (30) days of event discovery. | | ------*--- -DOCKET. N0 *.. 50~311 -- - ---- -- |
| MJPJ:pc Distribution 931123 S ADOCK 05000311 PDR The power is in your hands. Sincerely yours, c. A. Vondra General Manager -Salem Operations 95-2189 REV 7-92 NRC FORM 3i;& (6-891 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 LICENSEE EVENT REPORT (LER) FACILITY NAME (1) Salem Generating Station -Unit 2 TITLE (41 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-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO . THE PAPERWORK REDUCTION PROJECT (3150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. I DOCKET NUMBER (2) o I s I o I o I o I 31 1 11 I PAGE 111 1 loF o I 5 T/S 3.0.3 Entry; Inoperability of 21 BAST Level Indication While 22 BAST Out of Service. _EVENT DATE (6) LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl MONTH DAV YEAR VEAR :]( | | UNIT NO. 2 LICENSEE EVENT REPORT 93-012-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (B). |
| tt MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 1 I o 3 I o 9 3 91 *3 -o I 1 I 2 -o I o 1 I 1 2 I 3 9 I 3 . OPERATING MODE Ill THIS REPORT IS SUBMITTED PURSUANT TO THE Rt,QUIREMENTS OF 10 CFR §: ICh*ck ons or mora of th* followin1111111 1 20.402lbl 20.4051cl | | This report is required to be issued within thirty (30) days of event discovery. |
| .60.73(1112llivl | | Sincerely yours, |
| .. 73.71lbl . ....__ -....__ 20.40511111 IUI 60.38lcll11 | | : c. A. Vondra General Manager - |
| &0.73(11121M 73.711*1 ....__ -....__ 20.40511111 IUil 50.38lcll21 60.7311112llviil OTHER (Sr>>cify in Absrr*cr POWER I LEVEL 1101 11 0 10 -,..._ -b1tow *nd in T11xt. NRC Form 20.405(1111 llilil x 60.73111121111 60.73(11121 lvilll IAI 366AI -....__ 20.40611111lllvl 60.7311112)(iiJ | | Salem Operations MJPJ:pc Distribution |
| &0.7311112llvillllBI
| | ~~~2060021 931123 S ADOCK 05000311 PDR The power is in your hands. |
| --20.406(1111 IM 60.73(11121(111) 60.731111211*1 LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. -LER Coordinator 6 10 9 3 13 I 91-I 51116 I 5 CAUSE SYSTEM COMPONENT I I I I I I I I COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* TUR ER I I I I I I SYSTEM I I COMPONENT MANUFAC* TUR ER I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (141 MONTH DAY YEAR I EXPECTED SUBMISSION DATE 1151 n YES (If y11, comp/*!* EXPECTED SUBMISSION OATEI k-i NO I ABSTRACT (Limit to 1400 spac11s. i.t1 .* approxim1t11ly fifteen singl11-spsc11 typ11writt11n lin111} (161 At 0901 hours on 10/30/93, 21 Boric Acid Storage Tank (BAST) level indicator was declared inoperable due to false level indication.
| | 95-2189 REV 7-92 |
| At the time, 22 BAST was out of service therefore, Technical Specification (TS) Table 3.3-11, Action 3, was not met, and TS 3.0.3 was entered. TS 3.0.3 was exited, at 0930 hours (same day), upon return of 22 BAST to normal lineup. This event resulted from boron blockage in 21 BAST level indicator bubbler tube. The tube was blown down and at 1051 hours (same day), 21 BAST was returned to service. The root cause of this event is design of the BAST level indication system. A design change, including reducing the BAST boron concentration to 4% to minimize boron precipitation in the tank level indicator bubbler tube, is being installed during the current Unit 1 refueling outage and is scheduled for installation on Unit 2. NRC Form 366 16-891 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 2 DOCKET NUMBER 5000311 PLANT AND SYSTEM IDENTIFICATION: | | |
| Westinghouse | | NRC FORM 3i;& U.S. NUCLEAR REGULATORY COMMISSION (6-891 APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO . |
| -Pressurized Water Reactor LER NUMBER 93-012-00 PAGE 2 of 5 Energy Industry Identification System (EIIS) codes are shown in the text as {xx} IDENTIFICATION OF OCCURRENCE: | | THE PAPERWORK REDUCTION PROJECT (3150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. |
| Technical Specification 3.0.3 Entry; Inoperability of 21 Boric Acid Storage Tank (BAST) Level Indication While 22 BAST Out of Service .Event_Dates: | | I PAGE 111 I |
| _10/30/-93 Report Date: 11/23/93 This report was initiated by Incident Report Nos. 93-440. This event is reportable to the NRC per lOCFR 50.73(a) (2) (i) (B) due to entering Technical Specification (TS) 3.0.3. CONDITIONS PRIOR TO OCCURRENCE: | | FACILITY NAME (1) DOCKET NUMBER (2) |
| Mode 1 Reactor Power 100% -Unit Load 1170 MWe 22 BAST was out of service in support of boron batching operations. | | Salem Generating Station - Unit 2 TITLE (41 o I s I o I o I o I 31 1 11 1 loF o I 5 T/S 3.0.3 Entry; Inoperability of 21 BAST Level Indication While 22 BAST Out of Service. |
| | _EVENT DATE (6) LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl MONTH DAV YEAR VEAR :]( SE~~~~~~AL tt ~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 1 Io 3 I o 9 3 91 *3 - oI1 I 2 - o I o 1 I1 I 2 3 9 I3 |
| | . OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE Rt,QUIREMENTS OF 10 CFR §: ICh*ck ons or mora of th* followin1111111 MODE Ill 1 |
| | I 20.402lbl |
| | . ....__ 20.4051cl |
| | - .60.73(1112llivl .. ....__ 73.71lbl POWER LEVEL 1101 11 0 10 20.40511111 IUI 20.40511111 IUil |
| | -x 60.38lcll11 50.38lcll21 -,..._ &0.73(11121M 60.7311112llviil 73.711*1 OTHER (Sr>>cify in Absrr*cr b1tow *nd in T11xt. NRC Form 20.405(1111 llilil 60.73111121111 60.73(11121 lvilll IAI 366AI 20.40611111lllvl 20.406(1111 IM 60.7311112)(iiJ 60.73(11121(111) - |
| | LICENSEE CONTACT FOR THIS LER (121 |
| | &0.7311112llvillllBI 60.731111211*1 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER Coordinator 6 10 9 3 13 I 91- I 51116 I 5 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* MANUFAC* |
| | CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TUR ER 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 (141 MONTH DAY YEAR EXPECTED n YES (If y11, comp/*!* EXPECTED SUBMISSION OATEI k-i NO ABSTRACT (Limit to 1400 spac11s. i.t1.* approxim1t11ly fifteen singl11-spsc11 typ11writt11n lin111} (161 SUBMISSION DATE 1151 I I I At 0901 hours on 10/30/93, 21 Boric Acid Storage Tank (BAST) level indicator was declared inoperable due to false level indication. At the time, 22 BAST was out of service therefore, Technical Specification (TS) Table 3.3-11, Action 3, was not met, and TS 3.0.3 was entered. TS 3.0.3 was exited, at 0930 hours (same day), upon return of 22 BAST to normal lineup. This event resulted from boron blockage in 21 BAST level indicator bubbler tube. The tube was blown down and at 1051 hours (same day), 21 BAST was returned to service. |
| | The root cause of this event is design of the BAST level indication system. A design change, including reducing the BAST boron concentration to 4% to minimize boron precipitation in the tank level indicator bubbler tube, is being installed during the current Unit 1 refueling outage and is scheduled for installation on Unit 2. |
| | NRC Form 366 16-891 |
| | |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION: |
| | Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are shown in the text as {xx} |
| | IDENTIFICATION OF OCCURRENCE: |
| | Technical Specification 3.0.3 Entry; Inoperability of 21 Boric Acid Storage Tank (BAST) Level Indication While 22 BAST Out of Service |
| | .Event_Dates: _10/30/-93 Report Date: 11/23/93 This report was initiated by Incident Report Nos. 93-440. This event is reportable to the NRC per 10CFR 50.73(a) (2) (i) (B) due to entering Technical Specification (TS) 3.0.3. |
| | CONDITIONS PRIOR TO OCCURRENCE: |
| | Mode 1 Reactor Power 100% - Unit Load 1170 MWe 22 BAST was out of service in support of boron batching operations. |
| DESCRIPTION OF OCCURRENCE: | | DESCRIPTION OF OCCURRENCE: |
| At 0901 hours on October 30, 1993, the level indicator of 21 BAST {CB} was declared inoperable due to false level indication. | | At 0901 hours on October 30, 1993, the level indicator of 21 BAST {CB} |
| Since 22 BAST was out of service, Action 3 of TS Table 3.3-11 was not met, and action associated with TS 3.0.3 was entered. TS 3.0.3 was exited, at 0930 hours (same day), upon return of 22 BAST to normal lineup. In MODES 1, 2, AND 3, TS 3.3.3.7 requires two (2) OPERABLE BAST solution level indicators (one/tank). | | was declared inoperable due to false level indication. Since 22 BAST was out of service, Action 3 of TS Table 3.3-11 was not met, and action associated with TS 3.0.3 was entered. |
| With one level indicator inoperable, Action 3 of TS Table applies: "With the number of OPERABLE channels one less than the Required Number of Channels shown in TS Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of TS 3.1.2.8.a." | | TS 3.0.3 was exited, at 0930 hours (same day), upon return of 22 BAST to normal lineup. |
| ** *l | | In MODES 1, 2, AND 3, TS 3.3.3.7 requires two (2) OPERABLE BAST solution level indicators (one/tank). With one level indicator inoperable, Action 3 of TS Table ~.3-11 applies: |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 93-012-00 PAGE 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) TS 3.1.2.8 states: "Each of the following borated water sources shall be OPERABLE:
| | "With the number of OPERABLE channels one less than the Required Number of Channels shown in TS Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of TS 3.1.2.8.a." |
| : a. A boric acid storage system and at least one associated heat tracing system with: b. 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. The refueling water storage tank with: " TS 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." ANALYSIS OF OCCURRENCE: | | ** *l LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd) |
| The BAST (with the transfer pumps) are part of the boration subsystem of the Chemical and Volume Control System (CVCS). This subsystem ensures negative reactivity control during each mode of facility operation. | | TS 3.1.2.8 states: |
| Required components include two (2) borated water sources, two (2) BASTS and the Refueling Water Storage Tank (RWST). Either BAST contains sufficient volume to support one cold shutdown with the most reactive control rod withdrawn. | | "Each of the following borated water sources shall be OPERABLE: |
| These tanks contain 12 weight % boric acid maintained at a temperature of 175°F. 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 | | : a. A boric acid storage system and at least one associated heat tracing system with: |
| -A . . | | : 1. A minimum contained volume of 5106 gallons, |
| * LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 93-012-00 PAGE 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd) used to determine level. Use of a bubbler in a 12% boric acid solution results in indication failures when boron precipitation within the bubbler blocks the flow of nitrogen.
| | : 2. Between 20,000 and 22,500 ppm of boron, and, |
| A contributing factor to the precipitation is lower than desirable temperature within the bubbler tube. (Boron precipitation occurs when the 22,000 ppm boron solution temperature decreases below 145° F.) Past corrective actions (addressed most recently by LER 272/93-015-00) include adjustments to the nitrogen flow rate, increasing the frequency of system blowdown to once every seven days, and use .of.Control Air for blowdown. | | : 3. A minimum solution temperature of 145°F. |
| In addition, the BASTs and respective bubbler tubes of both units have been inspected and cleaned as necessary. | | : b. The refueling water storage tank with: " |
| These actions have proven to be marginally effective. | | TS 3.0.3 states: |
| Communications with other utilities, regarding BAST level bubbler failures in a boron solution, indicate boron precipitation will be eliminated by using a 4% boric acid solution. | | "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: |
| A design change, which includes reducing the BAST boron concentration to 4% to help minimize boron precipitation in the tank level indicator bubbler tube, is scheduled to be implemented. | | : 1. At least HOT STANDBY within the next 6 hours, |
| A similar Unit 1 design change will also be implemented. | | : 2. At least HOT SHUTDOWN within the following 6 hours, and |
| At approximately 0901 hours on October 30, 1993, the level indication of 21 BAST failed. At the time 22 BAST was out of service for boric acid batching. | | : 3. At least COLD SHUTDOWN within the subsequent 24 hours. |
| Due to inoperability of 21 BAST level indication and pre-existing unavailability of 22 BAST, TS 3.0.3 was entered. At 0930 hours (same day), 22 BAST was returned to service and TS 3.0.3 was exited. The false level indication of 21 BAST resulted from boron blockage of the indicator bubbler tube, attributed to design of the BAST level indication system. The tube was blown down to reestablish indication and at 1051 hours (same day), 21 BAST was returned to service and action associated with TS 3.3.3.7 was exited. APPARENT CAUSE OF OCCURRENCE: | | 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." |
| | ANALYSIS OF OCCURRENCE: |
| | The BAST (with the transfer pumps) are part of the boration subsystem of the Chemical and Volume Control System (CVCS). This subsystem ensures negative reactivity control during each mode of facility operation. Required components include two (2) borated water sources, two (2) BASTS and the Refueling Water Storage Tank (RWST). |
| | 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. 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 |
| | |
| | - A .. |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd) used to determine level. |
| | Use of a bubbler in a 12% boric acid solution results in indication failures when boron precipitation within the bubbler blocks the flow of nitrogen. A contributing factor to the precipitation is lower than desirable temperature within the bubbler tube. (Boron precipitation occurs when the 22,000 ppm boron solution temperature decreases below 145° F.) Past corrective actions (addressed most recently by LER 272/93-015-00) include adjustments to the nitrogen flow rate, increasing the frequency of system blowdown to once every seven days, and use .of.Control Air for blowdown. In addition, the BASTs and respective bubbler tubes of both units have been inspected and cleaned as necessary. These actions have proven to be marginally effective. Communications with other utilities, regarding BAST level bubbler failures in a boron solution, indicate boron precipitation will be eliminated by using a 4% boric acid solution. A design change, which includes reducing the BAST boron concentration to 4% to help minimize boron precipitation in the tank level indicator bubbler tube, is scheduled to be implemented. A similar Unit 1 design change will also be implemented. |
| | At approximately 0901 hours on October 30, 1993, the level indication of 21 BAST failed. At the time 22 BAST was out of service for boric acid batching. Due to inoperability of 21 BAST level indication and pre-existing unavailability of 22 BAST, TS 3.0.3 was entered. At 0930 hours (same day), 22 BAST was returned to service and TS 3.0.3 was exited. |
| | The false level indication of 21 BAST resulted from boron blockage of the indicator bubbler tube, attributed to design of the BAST level indication system. The tube was blown down to reestablish indication and at 1051 hours (same day), 21 BAST was returned to service and action associated with TS 3.3.3.7 was exited. |
| | 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. The event resulted from boron blockage in the 21 BAST level indicator bubbler tube, while 22 BAST was out of service. PREVIOUS OCCURRENCES: | | Installation" per NUREG-1022, (Licensee Event Report system) of the BAST level indication system. The event resulted from boron blockage in the 21 BAST level indicator bubbler tube, while 22 BAST was out of service. |
| The following LERs address TS 3.0.3 entries due to BAST level | | PREVIOUS OCCURRENCES: |
| . I * .. t LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 2 DOCKET NUMBER 5000311 LER NUMBER 93-012-00 PAGE 5 of 5 PREVIOUS OCCURRENCES: (cont'd) indication events: 272/92-023-00; 272/93-003-00; 272/93-009-00; 272/93-015-00; and 311/93-003-00. | | The following LERs address TS 3.0.3 entries due to BAST level |
| The root cause of this most recent event is the same as identified in the referenced LERs. ---SAFETY SIGNIFICANCE: | | |
| This event did not affect the health and safety of the public. Although 21 BAST level indication had failed required tank level was maintained and the associated Boric Acid Transfer pumps and valves were maintained in normal alignment for use if required. | | . I t |
| In _________ | | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 5 of 5 PREVIOUS OCCURRENCES: (cont'd) indication events: 272/92-023-00; 272/93-003-00; 272/93-009-00; 272/93-015-00; and 311/93-003-00. The root cause of this most recent event is the same as identified in the referenced LERs. |
| addition, __ during this_ event_the Refueling Water Storage Tarlk (RWST) remained available.
| | SAFETY SIGNIFICANCE: |
| CORRECTIVE ACTION: Following this event, the 21 BAST level indicator bubbler tube was blown down to remove blockage and level indication returned to its previous reading. A design change, including reducing the BAST boron concentration to 4% to minimize boron precipitation in the tank level indicator bubbler tube, is being installed during the current Unit 1 refueling outage and is scheduled for installation on Unit 2. MJPJ:pc SORC Mtg. 93-103 General Manager -Salem Operations}} | | This event did not affect the health and safety of the public. |
| | Although 21 BAST level indication had failed required tank level was maintained and the associated Boric Acid Transfer pumps and valves were maintained in normal alignment for use if required. In |
| | _________addition, __ during this_ event_the Refueling Water Storage Tarlk (RWST) remained available. |
| | CORRECTIVE ACTION: |
| | Following this event, the 21 BAST level indicator bubbler tube was blown down to remove blockage and level indication returned to its previous reading. |
| | A design change, including reducing the BAST boron concentration to 4% to minimize boron precipitation in the tank level indicator bubbler tube, is being installed during the current Unit 1 refueling outage and is scheduled for installation on Unit 2. |
| | General Manager - |
| | Salem Operations MJPJ:pc SORC Mtg. 93-103}} |
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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:RO)
MONTHYEARML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0081998-12-24024 December 1998 LER 97-001-01:on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With 981224 Ltr ML18106B0021998-12-17017 December 1998 LER 98-015-01:on 980924,improper Installation of Test Equipment to RPS Occurred.Caused by Inadequate 10CFR50.59 Applicability Reviews During Past Revs.Revised Procedures. with 981217 Ltr ML18106A9551998-11-0303 November 1998 LER 96-013-01:on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With 981105 Ltr ML18106A9451998-10-30030 October 1998 LER 97-004-01:on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With 981022 Ltr ML18106A9491998-10-22022 October 1998 LER 98-015-00:on 980924,identified Improper Installation of Test Equipment to Rps.Cause Indeterminate.Procedures for Installation of Test Equipment for Collection of State Point Data Were Placed on Administrative Hold.With 981022 Ltr ML18106A9301998-10-21021 October 1998 LER 98-014-00:on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With 981019 Ltr ML18106A9071998-10-0101 October 1998 LER 98-014-00:on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With 981001 Ltr ML18106A8951998-09-28028 September 1998 LER 98-012-01:on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With 980928 Ltr ML18106A8821998-09-21021 September 1998 LER 98-013-00:on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With 980921 Ltr ML18106A8791998-09-16016 September 1998 LER 96-006-01:on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With 980916 Ltr ML18106A8801998-09-0808 September 1998 LER 98-013-00:on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With 980908 Ltr ML18106A8531998-08-27027 August 1998 LER 98-007-00:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected tubing.W/980827 Ltr ML18106A8521998-08-27027 August 1998 LER 98-011-00:on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised procedure.W/980827 Ltr ML18106A8421998-08-24024 August 1998 LER 98-012-00:on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to svc.W/980824 Ltr ML18106A8431998-08-24024 August 1998 LER 98-009-00:on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke detectors.W/980824 Ltr ML18106A8141998-08-13013 August 1998 LER 98-010-00:on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve repaired.W/980813 Ltr ML18106A8201998-08-13013 August 1998 LER 98-012-00:on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been revised.W/980813 Ltr ML18106A6931998-06-29029 June 1998 LER 98-003-00:on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged ML18106A6471998-06-0404 June 1998 LER 98-011-00:on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative hold.W/980604 Ltr ML18106A6421998-06-0101 June 1998 LER 98-010-00:on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2.W/980601 Ltr ML18106A6431998-05-29029 May 1998 LER 98-006-01:on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database info.W/980529 Ltr ML18106A6141998-05-18018 May 1998 LER 98-008-00:on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised procedure.W/980518 Ltr ML18106A5901998-05-0101 May 1998 LER 98-009-00:on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was performed.W/980501 Ltr ML18106A5611998-04-20020 April 1998 LER 98-008-00:on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected ML18106A6061998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences ML18106A4451998-04-0101 April 1998 LER 98-004-00:on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety factors.W/980401 Ltr ML18106A4351998-03-30030 March 1998 LER 98-006-00:on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure transmitters.W/980330 Ltr ML18106A3961998-03-20020 March 1998 LER 98-005-00:on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP.W/980320 Ltr ML18106A5781998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs ML18106A4021998-03-20020 March 1998 LER 98-007-00:on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves identified.W/980320 Ltr ML18106A4031998-03-20020 March 1998 LER 98-006-00:on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water levels.W/980320 Ltr 1999-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station November 23, 1993
- u. s. Nuclear Regulatory commission Document Control Desk
. Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-75
*--- -DOCKET. N0 *.. 50~311 -- - ---- --
UNIT NO. 2 LICENSEE EVENT REPORT 93-012-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (B).
This report is required to be issued within thirty (30) days of event discovery.
Sincerely yours,
- c. A. Vondra General Manager -
Salem Operations MJPJ:pc Distribution
~~~2060021 931123 S ADOCK 05000311 PDR The power is in your hands.
95-2189 REV 7-92
NRC FORM 3i;& U.S. NUCLEAR REGULATORY COMMISSION (6-891 APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-5301, U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO .
THE PAPERWORK REDUCTION PROJECT (3150-01041, OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
I PAGE 111 I
FACILITY NAME (1) DOCKET NUMBER (2)
Salem Generating Station - Unit 2 TITLE (41 o I s I o I o I o I 31 1 11 1 loF o I 5 T/S 3.0.3 Entry; Inoperability of 21 BAST Level Indication While 22 BAST Out of Service.
_EVENT DATE (6) LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED (Bl MONTH DAV YEAR VEAR :]( SE~~~~~~AL tt ~~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBERISI 1 Io 3 I o 9 3 91 *3 - oI1 I 2 - o I o 1 I1 I 2 3 9 I3
. OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE Rt,QUIREMENTS OF 10 CFR §: ICh*ck ons or mora of th* followin1111111 MODE Ill 1
I 20.402lbl
. ....__ 20.4051cl
- .60.73(1112llivl .. ....__ 73.71lbl POWER LEVEL 1101 11 0 10 20.40511111 IUI 20.40511111 IUil
-x 60.38lcll11 50.38lcll21 -,..._ &0.73(11121M 60.7311112llviil 73.711*1 OTHER (Sr>>cify in Absrr*cr b1tow *nd in T11xt. NRC Form 20.405(1111 llilil 60.73111121111 60.73(11121 lvilll IAI 366AI 20.40611111lllvl 20.406(1111 IM 60.7311112)(iiJ 60.73(11121(111) -
LICENSEE CONTACT FOR THIS LER (121
&0.7311112llvillllBI 60.731111211*1 NAME TELEPHONE NUMBER AREA CODE M. J. Pastva, Jr. - LER Coordinator 6 10 9 3 13 I 91- I 51116 I 5 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* MANUFAC*
CAUSE SYSTEM COMPONENT SYSTEM COMPONENT TUR ER 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 (141 MONTH DAY YEAR EXPECTED n YES (If y11, comp/*!* EXPECTED SUBMISSION OATEI k-i NO ABSTRACT (Limit to 1400 spac11s. i.t1.* approxim1t11ly fifteen singl11-spsc11 typ11writt11n lin111} (161 SUBMISSION DATE 1151 I I I At 0901 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.428305e-4 months <br /> on 10/30/93, 21 Boric Acid Storage Tank (BAST) level indicator was declared inoperable due to false level indication. At the time, 22 BAST was out of service therefore, Technical Specification (TS) Table 3.3-11, Action 3, was not met, and TS 3.0.3 was entered. TS 3.0.3 was exited, at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> (same day), upon return of 22 BAST to normal lineup. This event resulted from boron blockage in 21 BAST level indicator bubbler tube. The tube was blown down and at 1051 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.999055e-4 months <br /> (same day), 21 BAST was returned to service.
The root cause of this event is design of the BAST level indication system. A design change, including reducing the BAST boron concentration to 4% to minimize boron precipitation in the tank level indicator bubbler tube, is being installed during the current Unit 1 refueling outage and is scheduled for installation on Unit 2.
NRC Form 366 16-891
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 2 of 5 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are shown in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Technical Specification 3.0.3 Entry; Inoperability of 21 Boric Acid Storage Tank (BAST) Level Indication While 22 BAST Out of Service
.Event_Dates: _10/30/-93 Report Date: 11/23/93 This report was initiated by Incident Report Nos.93-440. This event is reportable to the NRC per 10CFR 50.73(a) (2) (i) (B) due to entering Technical Specification (TS) 3.0.3.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 1 Reactor Power 100% - Unit Load 1170 MWe 22 BAST was out of service in support of boron batching operations.
DESCRIPTION OF OCCURRENCE:
At 0901 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.428305e-4 months <br /> on October 30, 1993, the level indicator of 21 BAST {CB}
was declared inoperable due to false level indication. Since 22 BAST was out of service, Action 3 of TS Table 3.3-11 was not met, and action associated with TS 3.0.3 was entered.
TS 3.0.3 was exited, at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> (same day), upon return of 22 BAST to normal lineup.
In MODES 1, 2, AND 3, TS 3.3.3.7 requires two (2) OPERABLE BAST solution level indicators (one/tank). With one level indicator inoperable, Action 3 of TS Table ~.3-11 applies:
"With the number of OPERABLE channels one less than the Required Number of Channels shown in TS Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of TS 3.1.2.8.a."
- *l LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 3 of 5 DESCRIPTION OF OCCURRENCE: (cont'd)
TS 3.1.2.8 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:
- 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: "
TS 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."
ANALYSIS OF OCCURRENCE:
The BAST (with the transfer pumps) are part of the boration subsystem of the Chemical and Volume Control System (CVCS). This subsystem ensures negative reactivity control during each mode of facility operation. Required components include two (2) borated water sources, two (2) BASTS and the Refueling Water Storage Tank (RWST).
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. 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
- A ..
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 4 of 5 ANALYSIS OF OCCURRENCE: (cont'd) used to determine level.
Use of a bubbler in a 12% boric acid solution results in indication failures when boron precipitation within the bubbler blocks the flow of nitrogen. A contributing factor to the precipitation is lower than desirable temperature within the bubbler tube. (Boron precipitation occurs when the 22,000 ppm boron solution temperature decreases below 145° F.) Past corrective actions (addressed most recently by LER 272/93-015-00) include adjustments to the nitrogen flow rate, increasing the frequency of system blowdown to once every seven days, and use .of.Control Air for blowdown. In addition, the BASTs and respective bubbler tubes of both units have been inspected and cleaned as necessary. These actions have proven to be marginally effective. Communications with other utilities, regarding BAST level bubbler failures in a boron solution, indicate boron precipitation will be eliminated by using a 4% boric acid solution. A design change, which includes reducing the BAST boron concentration to 4% to help minimize boron precipitation in the tank level indicator bubbler tube, is scheduled to be implemented. A similar Unit 1 design change will also be implemented.
At approximately 0901 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.428305e-4 months <br /> on October 30, 1993, the level indication of 21 BAST failed. At the time 22 BAST was out of service for boric acid batching. Due to inoperability of 21 BAST level indication and pre-existing unavailability of 22 BAST, TS 3.0.3 was entered. At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> (same day), 22 BAST was returned to service and TS 3.0.3 was exited.
The false level indication of 21 BAST resulted from boron blockage of the indicator bubbler tube, attributed to design of the BAST level indication system. The tube was blown down to reestablish indication and at 1051 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.999055e-4 months <br /> (same day), 21 BAST was returned to service and action associated with TS 3.3.3.7 was exited.
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. The event resulted from boron blockage in the 21 BAST level indicator bubbler tube, while 22 BAST was out of service.
PREVIOUS OCCURRENCES:
The following LERs address TS 3.0.3 entries due to BAST level
. I t
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 2 5000311 93-012-00 5 of 5 PREVIOUS OCCURRENCES: (cont'd) indication events: 272/92-023-00; 272/93-003-00; 272/93-009-00; 272/93-015-00; and 311/93-003-00. The root cause of this most recent event is the same as identified in the referenced LERs.
SAFETY SIGNIFICANCE:
This event did not affect the health and safety of the public.
Although 21 BAST level indication had failed required tank level was maintained and the associated Boric Acid Transfer pumps and valves were maintained in normal alignment for use if required. In
_________addition, __ during this_ event_the Refueling Water Storage Tarlk (RWST) remained available.
CORRECTIVE ACTION:
Following this event, the 21 BAST level indicator bubbler tube was blown down to remove blockage and level indication returned to its previous reading.
A design change, including reducing the BAST boron concentration to 4% to minimize boron precipitation in the tank level indicator bubbler tube, is being installed during the current Unit 1 refueling outage and is scheduled for installation on Unit 2.
General Manager -
Salem Operations MJPJ:pc SORC Mtg.93-103