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| | issue date = 08/12/1987 | | | issue date = 08/12/1987 |
| | title = LER 83-014/03L-1:on 830413 & 18,operating Loads on 2A 4kV & 460-volt Vital Buses Observed to Trip.Caused by Spurious Operation of Safeguards Equipment Control Sys Due to Design Deficiencies.Equipment restarted.W/870812 Ltr | | | title = LER 83-014/03L-1:on 830413 & 18,operating Loads on 2A 4kV & 460-volt Vital Buses Observed to Trip.Caused by Spurious Operation of Safeguards Equipment Control Sys Due to Design Deficiencies.Equipment restarted.W/870812 Ltr |
| | author name = FRAHM R, ZUPKO J M | | | author name = Frahm R, Zupko J |
| | 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:1*171 e LICENSEE EVENT REPORT e CONTROL BLOCK:!--! | | {{#Wiki_filter:1*171 e LICENSEE EVENT REPORT e CONTROL BLOCK:!--!__,.__.._........__...l.._..,l~l0 ('LEASE f'RINT DA TY'E ALL REQUIRED INFOAMATIONJ |
| ('LEASE f'RINT DA TY'E ALL REQUIRED INFOAMATIONJ | | *:ill] IN IJ Is IG Is 12 I@ ol ol -I ol ol ol ol ol -I DI ol(D[ 41 ll ll ll ll©L I 10. |
| *:ill] IN IJ Is IG Is 12 I@ ol ol -I ol ol ol ol ol -I DI ol(D[ 41 ll ll ll ll©L I 10. 8 LICENSEE CODE 1* 16 LICENSE NUMBER 2!> :26 LICENSE T'l''E JO !>7 CAT 58 \..:;,I CON'T TID II u.@ I ol s I o I o I o I 3 I 1 I 1 GI o I 4 11 '3 Is f 3 (!)I o I s h 12 I s I 7 10 90 a1 DOCKET NUMBER Ill S9 EVENT DATE 7* 71 fllEl'ORT DATE 10 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@ | | 8 ~ LICENSEE CODE 1* 16 LICENSE NUMBER 2!> :26 LICENSE T'l''E JO !>7 CAT 58 \..:;,I CON'T TID ::~: u.@ I ol sI oI oI oI 3 I 1 I 1 GI o I4 11 '3 Is f3 (!)I o I s h 12 I s I 7 10 II 90 a1 DOCKET NUMBER Ill S9 EVENT DATE 7* 71 fllEl'ORT DATE 10 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@ |
| ::£IIJ !On two separate occasions on April 13 and April 18, 1983, operating loads on the No. ]]]] 1 2A 4kv and 460V Vital Buses were observed to trip. In both cases, due to the de-]]1] 1 energization of No. 21 Residual Heat Removal (RHR) Pump, No. 21 RHR Loop was no longer I ]]]] lin operation, and Action Statement 3.4.l.4b-was entered. In each instance, the RHR ]]]] 1 r.oop was immediately returned to operationi no reduction in Reactor Coolant System III) I boron concentration occurred. | | ::£IIJ !On two separate occasions on April 13 and April 18, 1983, operating loads on the No. |
| The events constituted operation in a degraded mode in I accordance with Technical Specification 6.9.l.9b. | | )))) 2A 4kv and 460V Vital Buses were observed to trip. In both cases, due to the de-1 |
| ]:ID . B 9 SYSTEM CAUSE CAUSE COMP. CODE CODE SUBCODE COMPONENT CODE SUICOOE 1c1F1@ w@ Lfil@ 1I1N1s1T,R1u1e L!J 9 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE AE,ORT VALVE SUI CODE L!J@) 20 /;:;\ LE R 'RO LVENT YEAR RE,ORT NO. CODE TY'E' REPORT I e I 3 I I I I o I l f 4 I I,......, I o I 3 I l!!.j 1-1 NUMBER . 21 22 23 2* 26 27 28 29 30 31 REVISION NO. L2J 32 COMPOl\IEl\IT BO ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT Nl'RD-ol 'RIME COMI'. TAKEN ACTION ON 'LANT METHOD HOURS SUBMITTED FORM i>UB. SU"LIER i.!J@L!J@ | | ))1] 1energization of No. 21 Residual Heat Removal (RHR) Pump, No. 21 RHR Loop was no longer I |
| L2.J@ L!.J@ o Io Io Io I L!.J@ L!J@) MANUFACTURER 33 Joi 35 36 37 40 *1 *2 43 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ I A I 6 14 I 0 ' ... 47 . :I!2J I The root cause of the SEC events is attributed to equipment electrical design JJJJ !"deficiencies. | | )))) lin operation, and Action Statement 3.4.l.4b-was entered. In each instance, the RHR |
| These deficiencies have been corrected by the installation of equipment! | | )))) r.oop was immediately returned to operationi no reduction in Reactor Coolant System 1 |
| IIIJ !'design modifications. | | III) I boron concentration occurred. The events constituted operation in a degraded mode in accordance with Technical Specification 6.9.l.9b. |
| Since making these modifications, no similar SEC problems !J2J I have occurred. | | ]:ID I. |
| Im 8 9 FACILITY 13Q\ STATUS .. l'OWEA OTHER STATUS \:::::1 Im W@ I o! of ol@_I __ NA ___ _ 8 9 10 12 11 44
| | B 9 BO SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUICOOE SUI CODE 1c1F1@ w@ Lfil@ |
| * Q lltELEASE AMOUNT OF ACTIVITY ill] w l!.J@I NA I ; ; iO 11 M METHOD OF DISCOVERY DISCOVERY DESCRll'TION cs 46 LOCATION OF fllELEASE 10 NA iO ,E .. SONNELEX,OSU | | 9 10 11 12 1I1N1s1T,R1u1e 13 18 L!J L!J@) |
| .. ES t:::;-. NUUIEA It:::\ TY'E /.::\ DESCA1mON IT!] I d ol | | 19 20 SEQUENTIAL OCCURRENCE AE,ORT REVISION |
| ___
| | /;:;\ LE R 'RO LVENT YEAR RE,ORT NO. CODE TY'E' NO. |
| I I 11 12 13 ao 'EASONNEL INJU .. IES !:':\ NUMIE" ilIJ Idol
| | ~ REPORT Ie I I 3 I I I oIl f 4 I I,......, Io I3 I l!!.j 1-1 L2J NUMBER . 21 22 23 2* 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT Nl'RD-ol 'RIME COMI'. COMPOl\IEl\IT TAKEN ACTION ON 'LANT METHOD HOURS ~ SUBMITTED FORM i>UB. SU"LIER MANUFACTURER i.!J@L!J@ |
| ________________________________________ I 9 11 12 80 LOSS OF OA DAMAGE TD FACILITY J43' TYPE DESCA"TION | | 33 Joi L2.J@ |
| \:::I .:....L.!J W@I RA I 9 10 87 I l!"UeLICITV I::\ 08!90167 870812 PDR ADOCK 05000311 I I 10 ft -i:irlr ' ao NRC USE ONLY | | 35 L!.J@ |
| * liillllllllll! | | 36 37 o Io Io Io I L!.J@ |
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| | 43 IAI6 14 I 0 ' |
| | ... 47 . |
| | CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ |
| | :I!2J I The root cause of the SEC events is attributed to equipment electrical design JJJJ !"deficiencies. These deficiencies have been corrected by the installation of equipment! |
| | IIIJ !'design modifications. Since making these modifications, no similar SEC problems |
| | !J2J I have occurred. |
| | Im8 9 FACILITY 13Q\ |
| | \:::::1 METHOD OF ~ |
| | STATUS .. l'OWEA OTHER STATUS DISCOVERY DISCOVERY DESCRll'TION ~ |
| | Im W@ I o! of ol@_I__NA_ _ __ L!J~~'~~0p..._e_r_a_t_i_o_n_a_l~Ev~e_n_t~~~~~~~~~-- |
| | 8 9 10 12 11 44 cs 46 10 |
| | ~TIV~ ~U~ |
| | * Q "ELEASE~F lltELEASE ill]; w ~ l!.J@I |
| | ; iO 11 NA AMOUNT OF ACTIVITY M |
| | I NA LOCATION OF fllELEASE iO |
| | ,E..SONNELEX,OSU .. ES t:::;-. |
| | NUUIEA It:::\ TY'E /.::\ DESCA1mON IT!]I II d ol orLi~~I 11 12 13 |
| | ___Na:,;A~-----------------------~J ao |
| | 'EASONNEL INJU .. IES !:':\ |
| | r.;;DESCAIPTION~ |
| | ilIJ Idol NUMIE" d~~l___.J1Am:1.- ________________________________________~*1 I 9 11 12 80 LOSS OF OA DAMAGE TD FACILITY J43' |
| | ~ \:::I |
| | .:....L.!J TYPE W@I DESCA"TION RA ft -i:irlr I 9 10 87 08!90167 870812 ' ao I l!"UeLICITV I::\ |
| | ~ ISSUED~iSC:flllPTION~ PDR ADOCK 05000311 NRC USE ONLY * |
| | -~I l..zU~~----HA--~---------S---------------P-D~R,;__~~ |
| | I 10 1* |
| | liillllllllll! |
| | ae. ao ; |
| | flHONE:(609) 935-6000 Ext. 3078 ~ |
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| '"' & Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 | | C'"'~. PS~G 1~" & |
| | Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 12, 1987 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 August 12, 1987 LICENSEE EVENT REPORT SUPPLEMENT 83-014/03L-l This supplemental Licensee Event. Report is being submitted pursuant to the requirements of 10CFR 50.73 and Technical Specification 6.9.1.7. LP.F 83-014/03L has been revised to specify the root cause of the event and to detail the corrective actions taken. .MJP:pc Distribution The Energy People Sincerely | | |
| : yours, General Salem Operations 89 1Ml,2-84
| | SALEM GENERATING STATION LICENSE NO. DPR-75 DOCKET NO. 50-311 UNIT NO. 2 LICENSEE EVENT REPORT SUPPLEMENT 83-014/03L-l This supplemental Licensee Event. Report is being submitted pursuant to the requirements of 10CFR 50.73 and Technical Specification 6.9.1.7. LP.F 83-014/03L has been revised to specify the root cause of the event and to detail the corrective actions taken. |
| ---------------------*-
| | Sincerely yours, J.~tt.ft General Manager-Salem Operations |
| ----
| | .MJP:pc Distribution The Energy People 9~,-2* 89 I~ 1Ml,2-84 |
| Number: .e Report Date: 83-o:9o3L-l 08-12-87 04-13-83 Occurrence Date: Facility: | | |
| Salem Generating Station Unit 2 Public Service Electric & Gas Company Hancock's Bridge, N. 08038 IDENTIFICATION OF OCCURRENCE: | | ~eport Number: 83-o:9o3L-l .e Report Date: 08-12-87 Occurrence Date: 04-13-83 Facility: Salem Generating Station Unit 2 Public Service Electric & Gas Company Hancock's Bridge, N. J~ 08038 IDENTIFICATION OF OCCURRENCE: |
| Reactor Coolant System -Residual Heat Removal Loops -Loss of Operating Loop This report was initiated by Incident Reports 83-071 and 83-072. CONDITIONS PRIOR TO OCCURRENCE: | | Reactor Coolant System - Residual Heat Removal Loops - Loss of Operating Loop This report was initiated by Incident Reports 83-071 and 83-072. |
| Mode 5 -Rx Power 0% -Unit Load 0 MWe. DESCRIPTION OF OCCURRENCE: | | CONDITIONS PRIOR TO OCCURRENCE: |
| On two separate occasions, 1755 hours, April 13 and 1520 hours, April 18, 1983, operating loads on the No. 2A 4KV and 460V.Vital Buses were observed to trip. The only indications received in the Control Room were alarms assocated with the loss of the running equipment and flashing bezel stop pushbuttons. | | Mode 5 - Rx Power 0% - Unit Load 0 MWe. |
| Two different vital bus power sources were involved; on both occasions the infeed breaker remained closed. In both cases, due to the deenergization of 21 Residual Heat Removal (RHR) Pump, No. 21 RHR Loop was no longer in operation. | | DESCRIPTION OF OCCURRENCE: |
| Due to no RHR Loop being in operation, Technical Specification Action Statement 3.4.l.4b was entered. In each instance, the RHR loop was *immediately returned to operation, and no reduction in Reactor Coolant System (RCS) boron concentration occurred with the RHR loop out of service. APPARENT CAUSE OF OCCURRENCE: | | On two separate occasions, ~t 1755 hours, April 13 and 1520 hours, April 18, 1983, operating loads on the No. 2A 4KV and 460V.Vital Buses were observed to trip. The only indications received in the Control Room were alarms assocated with the loss of the running equipment and flashing bezel stop pushbuttons. Two different vital bus power sources were involved; on both occasions the infeed breaker remained closed. In both cases, due to the deenergization of No~ 21 Residual Heat Removal (RHR) Pump, No. 21 RHR Loop was no longer in operation. |
| Investigation revealed that the occurrences were evidently due to spurious operation of the Safeguards Equipment Control (SEC) System. Previous spurious actuations related to control circuitry noise (see LER 82-132/03L) had been addressed by installation of noise | | Due to no RHR Loop being in operation, Technical Specification Action Statement 3.4.l.4b was entered. In each instance, the RHR loop was |
| * suppression devices (per_ Design Change Request 2EC1387). | | *immediately returned to operation, and no reduction in Reactor Coolant System (RCS) boron concentration occurred with the RHR loop out of service. |
| *However, investigation has shown*these problems to be unrelated. | | APPARENT CAUSE OF OCCURRENCE: |
| | Investigation revealed that the occurrences were evidently due to spurious operation of the Safeguards Equipment Control (SEC) System. |
| | Previous spurious actuations related to control circuitry noise (see LER 82-132/03L) had been addressed by installation of noise |
| | * suppression devices (per_ Design Change Request 2EC1387). *However, investigation has shown*these problems to be unrelated. |
| The root cause of the SEC related events addressed in this LER and | | The root cause of the SEC related events addressed in this LER and |
| * Unit 2 LER's 83-025/93L, 83-031/B3L, 83-941/03L, 83-04.7/03L, and 83-059/03L was equipment design deficiencies. | | * Unit 2 LER's 83-025/93L, 83-031/B3L, 83-941/03L, 83-04.7/03L, and 83-059/03L was equipment design deficiencies. Investigation of these SEC related events revealed: |
| Investigation of these SEC related events revealed: | |
| : 1. The. SEC is very susceptible to voltage transients due to the design of its electronics; | | : 1. The. SEC is very susceptible to voltage transients due to the design of its electronics; |
| : 2. Because the SEC doe.s not have surge suppression components across the DC reactive components, such as the breaker-closing coils, large voltage transient.s | | : 2. Because the SEC doe.s not have surge suppression components across the DC reactive components, such as the breaker-closing coils, large voltage transient.s *are induced in the SEC by DC currents that interface with it; |
| *are induced in the SEC by DC currents that interface with it; -3. Occassionally, the .AC .power source to the SEC experiences transients in voltage; | | - 3. Occassionally, the .AC .power source to the SEC experiences transients in voltage; |
| * LER 83-014/03L-l APPARENT CAUSE OF OCCURRENCE: (cont'd) 4. The SEC has an auto-test-feature which eventually causes the relays to wear out. The test involves the relays flexing their armature and' rubbing contacts approximately every second, which taxes them; and S. Radio frequencies (RF), such as from hand held radio transmissions used by Security and Fire Protection, can interfere with the SEC's electronics. | | * LER 83-014/03L-l APPARENT CAUSE OF OCCURRENCE: (cont'd) |
| | : 4. The SEC has an auto-test-feature which eventually causes the relays to wear out. The test involves the relays flexing their armature and' rubbing contacts approximately every second, which taxes them; and S. Radio frequencies (RF), such as from hand held radio transmissions used by Security and Fire Protection, can interfere with the SEC's electronics. |
| ANALYSIS OF OCCURRENCE: | | ANALYSIS OF OCCURRENCE: |
| Operability of the RHR loops is required to provide heat removal capability for removing decay heat. A single loop sufficient capability; single failure considerations require that two loops be operable. | | Operability of the RHR loops is required to provide heat removal capability for removing decay heat. A single loop provid~s sufficient capability; single failure considerations require that two loops be operable. A single RHR pump also provides adequate flow to ensure mixing; prevent stratification and-produce gradual reactivity changes during RCS boron concentration reductions. |
| A single RHR pump also provides adequate flow to ensure mixing; prevent stratification and-produce gradual reactivity changes during RCS boron concentration reductions. | | As noted, in both instances, RHR flow was immediately restored and no reduction.in boron concentration occurred. The events therefore - |
| As noted, in both instances, RHR flow was immediately restored and no reduction.in boron concentration occurred. | | * involved no undu~ risk to the health of safety of the public. The occurrences constituted operation in a degraded mode permitted by a limiting condition for operation and are reportable in accordance with Technical Specification 6.9~1.9b. |
| The events therefore | | Action Statement 3.4.l.4b requires: |
| -* involved no risk to the health of safety of the public. The occurrences constituted operation in a degraded mode permitted by a limiting condition for operation and are reportable in accordance with Technical Specification Action Statement 3.4.l.4b requires:
| |
| With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the RCS and immediately initiate corrective action to return the required RHR loop to operation. | | With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the RCS and immediately initiate corrective action to return the required RHR loop to operation. |
| CORRECTIVE ACTION: ln both cases, after a survey of the control board showed no other _abnormalities, the Control Room Operator restarted appropriate equipment. | | CORRECTIVE ACTION: |
| In each instance, No. 21 RHR Pump was restarted to restore an RHR loop to operation, and Action Statement | | ln both cases, after a survey of the control board showed no other |
| *was terminated_ | | _abnormalities, the Control Room Operator restarted appropriate equipment. In each instance, No. 21 RHR Pump was restarted to restore an RHR loop to operation, and Action Statement 3.4~1.4b *was terminated_ |
| at 1756 hours, April 13 and at 1520 hours, April 18,. 1983. New 24V and 15V power supplies were installed (per DCR 2EC-1778). | | at 1756 hours, April 13 and at 1520 hours, April 18,. 1983. |
| These power supplies are more reliable and steadier than the previous ones. Additionally, the supply voltage was raised from 15 to 16 volts for all SEC Cabinets. | | New 24V and 15V power supplies were installed (per DCR 2EC-1778). |
| Time delay relays were installed (per Design Change Request 2EC-1778) to offer protection from brief, spurious voltage transients. | | These power supplies are more reliable and steadier than the previous ones. Additionally, the supply voltage was raised from 15 to 16 volts for all SEC Cabinets. Time delay relays were installed (per Design Change Request 2EC-1778) to offer protection from brief, spurious voltage transients. The cables between the SEC electronics and the input relays were shielded (via Design Change Request 2EC-1898) to minimize spurious activity and RF interference concerns. |
| The cables between the SEC electronics and the input relays were shielded (via Design Change Request 2EC-1898) to minimize spurious activity and RF interference concerns. | |
| Administrative Controls prohibit the use of radio transmitters in the vicinity of the SEC. | | Administrative Controls prohibit the use of radio transmitters in the vicinity of the SEC. |
| * Engineering Field Directive S-SC-Rl30-CFD-251, nMaintenance of Safeguards Equipment Controller (SEC) Relaysn recommendations were implemented. | | * Engineering Field Directive S-SC-Rl30-CFD-251, nMaintenance of Safeguards Equipment Controller (SEC) Relaysn recommendations were implemented. These recommendations include checking the SEC relays every refueling outage utilizing a nrelay testern. Those relays which |
| These recommendations include checking the SEC relays every refueling outage utilizing a nrelay testern. Those relays which | | |
| ! . I LER 83-014/03L-l CORRECTIVE ACTION: (cont'd) demonstrate degraded performance are replaced.
| | LER 83-014/03L-l CORRECTIVE ACTION: (cont'd) demonstrate degraded performance are replaced. Upon completion of relay testing the SEC js tested for operability (Operations Department procedure SP(0)4.3.2.l(a)). |
| Upon completion of relay testing the SEC js tested for operability (Operations Department procedure SP(0)4.3.2.l(a)). | | After implementation of the above corrective actions, the 2A SEC Cabinet was monitored for approximately six (6) n1onths. No addi~ional similar spurious actuations were identified. |
| After implementation of the above corrective actions, the 2A SEC Cabinet was monitored for approximately six (6) n1onths. No similar spurious actuations were identified. | | FAILURE DATA: |
| FAILURE DATA: Automation Industries, Inc. Safeguards Equipment Control System MJP/pc SORC f.1tg. 87-061 Salem Operations}} | | Automation Industries, Inc. |
| | Safeguards Equipment Control System GeY:::~ |
| | Salem Operations MJP/pc SORC f.1tg. 87-061 I}} |
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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
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Text
1*171 e LICENSEE EVENT REPORT e CONTROL BLOCK:!--!__,.__.._........__...l.._..,l~l0 ('LEASE f'RINT DA TY'E ALL REQUIRED INFOAMATIONJ
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- £IIJ !On two separate occasions on April 13 and April 18, 1983, operating loads on the No.
)))) 2A 4kv and 460V Vital Buses were observed to trip. In both cases, due to the de-1
))1] 1energization of No. 21 Residual Heat Removal (RHR) Pump, No. 21 RHR Loop was no longer I
)))) lin operation, and Action Statement 3.4.l.4b-was entered. In each instance, the RHR
)))) r.oop was immediately returned to operationi no reduction in Reactor Coolant System 1
III) I boron concentration occurred. The events constituted operation in a degraded mode in accordance with Technical Specification 6.9.l.9b.
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- I!2J I The root cause of the SEC events is attributed to equipment electrical design JJJJ !"deficiencies. These deficiencies have been corrected by the installation of equipment!
IIIJ !'design modifications. Since making these modifications, no similar SEC problems
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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station August 12, 1987 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 SUPPLEMENT 83-014/03L-l This supplemental Licensee Event. Report is being submitted pursuant to the requirements of 10CFR 50.73 and Technical Specification 6.9.1.7. LP.F 83-014/03L has been revised to specify the root cause of the event and to detail the corrective actions taken.
Sincerely yours, J.~tt.ft General Manager-Salem Operations
.MJP:pc Distribution The Energy People 9~,-2* 89 I~ 1Ml,2-84
~eport Number: 83-o:9o3L-l .e Report Date: 08-12-87 Occurrence Date: 04-13-83 Facility: Salem Generating Station Unit 2 Public Service Electric & Gas Company Hancock's Bridge, N. J~ 08038 IDENTIFICATION OF OCCURRENCE:
Reactor Coolant System - Residual Heat Removal Loops - Loss of Operating Loop This report was initiated by Incident Reports83-071 and 83-072.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 5 - Rx Power 0% - Unit Load 0 MWe.
DESCRIPTION OF OCCURRENCE:
On two separate occasions, ~t 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br />, April 13 and 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />, April 18, 1983, operating loads on the No. 2A 4KV and 460V.Vital Buses were observed to trip. The only indications received in the Control Room were alarms assocated with the loss of the running equipment and flashing bezel stop pushbuttons. Two different vital bus power sources were involved; on both occasions the infeed breaker remained closed. In both cases, due to the deenergization of No~ 21 Residual Heat Removal (RHR) Pump, No. 21 RHR Loop was no longer in operation.
Due to no RHR Loop being in operation, Technical Specification Action Statement 3.4.l.4b was entered. In each instance, the RHR loop was
APPARENT CAUSE OF OCCURRENCE:
Investigation revealed that the occurrences were evidently due to spurious operation of the Safeguards Equipment Control (SEC) System.
Previous spurious actuations related to control circuitry noise (see LER 82-132/03L) had been addressed by installation of noise
- suppression devices (per_ Design Change Request 2EC1387). *However, investigation has shown*these problems to be unrelated.
The root cause of the SEC related events addressed in this LER and
- Unit 2 LER's 83-025/93L, 83-031/B3L, 83-941/03L, 83-04.7/03L, and 83-059/03L was equipment design deficiencies. Investigation of these SEC related events revealed:
- 1. The. SEC is very susceptible to voltage transients due to the design of its electronics;
- 2. Because the SEC doe.s not have surge suppression components across the DC reactive components, such as the breaker-closing coils, large voltage transient.s *are induced in the SEC by DC currents that interface with it;
- 3. Occassionally, the .AC .power source to the SEC experiences transients in voltage;
- LER 83-014/03L-l APPARENT CAUSE OF OCCURRENCE: (cont'd)
- 4. The SEC has an auto-test-feature which eventually causes the relays to wear out. The test involves the relays flexing their armature and' rubbing contacts approximately every second, which taxes them; and S. Radio frequencies (RF), such as from hand held radio transmissions used by Security and Fire Protection, can interfere with the SEC's electronics.
ANALYSIS OF OCCURRENCE:
Operability of the RHR loops is required to provide heat removal capability for removing decay heat. A single loop provid~s sufficient capability; single failure considerations require that two loops be operable. A single RHR pump also provides adequate flow to ensure mixing; prevent stratification and-produce gradual reactivity changes during RCS boron concentration reductions.
As noted, in both instances, RHR flow was immediately restored and no reduction.in boron concentration occurred. The events therefore -
- involved no undu~ risk to the health of safety of the public. The occurrences constituted operation in a degraded mode permitted by a limiting condition for operation and are reportable in accordance with Technical Specification 6.9~1.9b.
Action Statement 3.4.l.4b requires:
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the RCS and immediately initiate corrective action to return the required RHR loop to operation.
CORRECTIVE ACTION:
ln both cases, after a survey of the control board showed no other
_abnormalities, the Control Room Operator restarted appropriate equipment. In each instance, No. 21 RHR Pump was restarted to restore an RHR loop to operation, and Action Statement 3.4~1.4b *was terminated_
at 1756 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.68158e-4 months <br />, April 13 and at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />, April 18,. 1983.
New 24V and 15V power supplies were installed (per DCR 2EC-1778).
These power supplies are more reliable and steadier than the previous ones. Additionally, the supply voltage was raised from 15 to 16 volts for all SEC Cabinets. Time delay relays were installed (per Design Change Request 2EC-1778) to offer protection from brief, spurious voltage transients. The cables between the SEC electronics and the input relays were shielded (via Design Change Request 2EC-1898) to minimize spurious activity and RF interference concerns.
Administrative Controls prohibit the use of radio transmitters in the vicinity of the SEC.
- Engineering Field Directive S-SC-Rl30-CFD-251, nMaintenance of Safeguards Equipment Controller (SEC) Relaysn recommendations were implemented. These recommendations include checking the SEC relays every refueling outage utilizing a nrelay testern. Those relays which
LER 83-014/03L-l CORRECTIVE ACTION: (cont'd) demonstrate degraded performance are replaced. Upon completion of relay testing the SEC js tested for operability (Operations Department procedure SP(0)4.3.2.l(a)).
After implementation of the above corrective actions, the 2A SEC Cabinet was monitored for approximately six (6) n1onths. No addi~ional similar spurious actuations were identified.
FAILURE DATA:
Automation Industries, Inc.
Safeguards Equipment Control System GeY:::~
Salem Operations MJP/pc SORC f.1tg.87-061 I