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| {{#Wiki_filter:REGULA Y INFORNATION DISTR IBUTI0 YSTEN (R IDS>;ACCESSION NBR: 8704130111 DOC.DATE: 87/04/06 NOTARIZED: | | {{#Wiki_filter:REGULA Y INFORNATION DISTR IBUTI0 YSTEN (R IDS> |
| NO FACIL: 50-400 Shearon Harris Nuclear Power Plant>Unit 1>Carolina AUTH.NANE AUTHOR AFF ILI AT I ON BCHWABENBAUER Carol in a P over 8c Light C o.WATSON>R.A.Carolina Poeer 5 Light Co..RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000400 | | ;ACCESSION NBR: 8704130111 DOC. DATE: 87/04/06 NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Power Plant> Unit 1> Carolina 05000400 AUTH. NANE AUTHOR AFF ILIAT I ON BCHWABENBAUER Carol in a P over 8c Light C o. |
| | WATSON> R. A. Carolina Poeer 5 Light Co.. |
| | RECIP. NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-011-00: | | LER 87-011-00: on 870307> auxiliary bus IE feedeY breaker 121 tripped open> causing de-energization of auxiliary bus IE 5 safety bus 1B-SB. Caused bg procedural inadequacy. Work tic ket initiated to replace diode. W/870406 ltr. |
| on 870307>auxiliary bus IE feedeY breaker 121 tripped open>causing de-energization of auxiliary bus IE 5 safety bus 1B-SB.Caused bg procedural inadequacy. | | DISTRIBUTION CODE: IESSD COPIES RECEIVED: LTR I ENCL I SIIE: |
| Work tic ket initiated to replace diode.W/870406 ltr.DISTRIBUTION CODE: IESSD COPIES RECEIVED: LTR I ENCL I SIIE: TITLE: 50.73 Licensee Event Report (LER)>Incident Rpt>etc.NOTES: App li cation for permit reneu'al f iled.05000400 RECIPIENT ID CODE/NANE PD2-1 L*BUCKLEY>B INTERNAL: ACRS MICHELSON ACRB WYLIE AEOD/DBP/ROAB NRR/ADT NRR/DEBT/ADS NRR/DEBT/ELB NRR/DEST/MEB NRR/DEBT/PSB NRR/DEBT/SGB NRR/DLPG/GAB NRR/DREP/EPB BR/ILRB REG FIL 02 RGN2 FILE 01 EXTERNAL: EQ8cG GROH>N LPDR NSI C HARRIS>J COPIEB LTTR ENCL 1 1 1 1 1 1 2 2 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ACRB NOELLER AEOD/DOA AEOD/DSP/TAPB NRR/DEBT/ADE ERR/DEBT/CEB ERR/DEBT/I CSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RAB NRR/PNAS/PTSB RES SPEIS>T H ST LOBBY WARD NRC PDR NSIC MAYS>G COPIES LTTR ENCL 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NU>HER OF COP IES REQUIRED: LTTR 41 ENCL 39 NRC Form 3FS (94)3)LICENSEE EVENT REPORT (LER)U rL NUCLEAR REQULATORY COMMISSION APPROVED OMB NO.31504104 EXPIRES)5/31/SS FACILITY NAME (I)SHEARON HARRIS PLANT UNIT 1 TITLE (4)"6.9 KV ONSITE DISTRIBUTION" DOCKET NUMBER (2)0 5 0 0 0 4 0 PA E 3I 1 QF 0 3 MONTH DAY YEAR EVENT DATE (5)YEAR LER NUMBER (6)SEQUENTIAL Mb NUMBER 5M Rt VISION NUMBER REPORT DATE (7)MONTH DAY YEAR DOCKET NUMBER(S)0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED IS)0 3 0 7 8 7 011 0 04 6 87 0 5 0 0 0 OPERATINQ MODE (9)POWER LEVEL 00)0 0 0 20A02(II)20.405[v)(I)(I)20A05(~)(I)(il)20.405(~)(1)(ill)20A05(~)(I)(I v)20.405 (e)(I)(v)20.405(c)50.35(c)(I)50.35(c)(2)50.73(e)(2)(l).50.73(s)(2)(Ii)50.73(s)(2)(lii)LICENSEE CONTACT FOR THIS LEA (12I 50.73 (e)(2)(Iv)50.73(e)(2)(v) 50,73(s)(2)(vii)50.73(e)(2)(vill)(A)50.7 3(e)(2)(vill)(5)50.73(~)(2)(s)THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (): (Check one or more of the follovy'npl (11)73.71(5)73 71(c)DTHER (specify ln Aortrect helow end ln Test, NRC Form 366A)NAME R.SCHWABENBAUER | | TITLE: 50. 73 Licensee Event Report (LER)> Incident Rpt> etc. |
| -REGULATORY TECHNICIAN TEI.EPHONE NUMBER AREA CODE 919 362-26 69 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCAIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC TVRER..EPOATABLE TO NPRDS!NM5 CAUSE SYSTEM COMPONENT MANUFAC.TVRER''PORTABLE i.TO NPADS h:.'..Ihr ARIx..B E E JX W12 0 N X hA:cNkprg~.whirr c N~.~.'" P hk h48X h, SVPPLEMENTAI.
| | NOTES: App lication for permit reneu'al f iled. 05000400 RECIPIENT COPIEB RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 L* 1 1 PD2-1 PD 1 BUCKLEY> B 1 INTERNAL: ACRS MICHELSON 1 1 ACRB NOELLER 1 1 ACRB WYLIE 1 AEOD/DOA 1 1 AEOD/DBP/ROAB 2 2 AEOD/DSP/TAPB 1 NRR/ADT 1 NRR/DEBT/ADE 0 NRR/DEBT/ADS 1 0 ERR/DEBT/CEB 1 1 NRR/DEBT/ELB 1 1 ERR /DEBT/ I CSB 1 1 NRR/DEST/MEB 1 NRR/DEST/MTB 1 1 NRR/DEBT/PSB 1 1 NRR/DEST/RSB 1 NRR/DEBT/SGB 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/EPB 1 1 NRR/DREP/RAB 1 1 BR /ILRB 1 NRR/PNAS/PTSB 1 1 REG FIL 02 RES SPEIS> T 1 1 RGN2 FILE 01 1 EXTERNAL: EQ8cG GROH> N 5 5 H ST LOBBY WARD LPDR 1 NRC PDR NSI C HARRIS> J 1 1 NSIC MAYS> G TOTAL NU >HER OF COP IES REQUIRED: LTTR 41 ENCL 39 |
| REPORT EXPECTED (14)YES llf yet, complNe EXPECTED SUBMISSION DATE)ABsTRAGT ILlmlr to tcOO tpecer, l.e., epproxlmetely fifteen tfnpleepece typewritten linnl (15)EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR ABSTRACT On March 7, 1987, an Auxiliary Operator (AO)was performing a weekly surveillance test (OST-1023) which is for offsite power verification. | | |
| One of the requirements of the OST is to ensure the breaker release lever is in the neutral position with the breaker closed.When the AO checked Auxiliary Bus IE feeder breaker 121 the breaker was inadvertently tripped open causing the.de-energization of Auxiliary Bus IE and Safety Bus 1B-SB.This occurred at 2230 hours on March 7, 1987.The de-energization of Bus 1B-SB caused the 1B-SB Diesel Generator to start and the actuation of Sequencer lB-SB on Bus undervoltage. | | NRC Form 3FS U rL NUCLEAR REQULATORY COMMISSION (94)3) APPROVED OMB NO. 31504104 EXPIRES) 5/31/SS LICENSEE EVENT REPORT (LER) |
| The AO immediately closed the breaker cabinet and.notified the Control Room of the incident.The Senior Control Operator (SCO)then initiated AOP-025 for the loss of one emergency bus and all plant systems were then returned to normal.At the-time of the incident, the plant was in Mode 4 at 3450F and 350 psig.There were no adverse consequences due to this event and safety systems performed as required.To prevent recurrence, the applicable procedure has been revised.8704130111 870406 PDR*DOCI('5000400 S PDR NRC Form 355 (94)3) | | FACILITY NAME (I) DOCKET NUMBER (2) PA E 3I SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 0 1 QF 0 3 TITLE (4) |
| NRC Form 366A (94)3)FACILITY NAME (1)U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO, 3150-0)04 EX PIR ES: 8/31/BS'1'UMBER YEAR FACE (3)LER NUMBER (6):R+: SEQUENTIAL | | "6.9 KV ONSITE DISTRIBUTION" EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED IS) |
| ,8 NUMBER DOCKET NUMBER (2)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION SHEARON HARRIS PLANT UNIT 1 TEXT//F'moro FPoco/4/or/rokod, Iroo/I/Ooro///RC | | YEAR SEQUENTIAL Mb Rt VISION MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(S) |
| %%d 36649/(13 I 0 5 0 0 0 4 0 0 011 0 0 02"0 3 TEXT DESCRIPTION On March 7, 1987, an Auxiliary Operator (AO)was performing a weekly surveillance test OST-1023 entitled"OFFSITE POWER AVAILABILITY VERIFICATION WEEKLY INTERVAL MODES 1-2-3 6 4." One of the requirements of the OST is to ensure the breaker release lever is in the neutral position with the breaker closed.The AO did this by checking the release lever with his foot for freedom of movement.The AO had used this method without incident in the past.When the AO went to check the Auxiliary Bus 1E feeder breaker 121 the breaker tripped open causing the de-energization of Auxiliary Bus lE.This also de-energized the 1B-SB safety bus thereby activating the 1B-SB Sequencer and starting the 1B-SB Diesel Generator. | | MONTH DAY YEAR NUMBER 5M NUMBER 0 5 0 0 0 0 3 0 7 8 7 011 0 04 6 87 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (): (Check one or more of the follovy'npl (11) |
| The AO immediately closed the breaker cabinet and notified the Control Room.Upon notification, the Senior Control Operator (SCO)entered Abnormal Operating Procedure AOP-025, entitled"Loss of One Emergency AC Bus (6.9KV)or One Emergency DC (125V)Bus" for the loss of emergency bus and restored all plant systems to normal operation. | | OPERATINQ MODE (9) 20A02(II) 20.405(c) 50.73 (e) (2) (Iv) 73.71(5) |
| At the time of the incident, the plant was in Mode 4 at 345'F and 350 psig.The de-energization of non-safety related Auxiliary Bus 1E also caused the Charging Safety Injection Pumps (CSIP)suction source to automatically transfer from the Volume Control Tank (VCT)to the Refueling Water Storage Tank (RWST).This transfer occurs automatically when both VCT level channels (LT-115 and LT-112)are less than 5X (low low level)or when Safety Injection occurs.This transfer of suction source was due to the de-energization of relays K701 (for LT-115)and K706 (for LT-112)which caused the associated contacts to close and generate a signal to re-position the valves.Relay K701 lost power due to a 7.5 KVA Inverter (the normal power supply)being out of service for a maintenance function, the alternate power supply was via Auxiliary Bus lE.Relay K706 lost power due to a faulty diode which failed to pass the normal power from an uninterruptible source', the backup source was powered via the Auxiliary Bus lE.The VCT/RWST transfer was caused by a combination of both the 7.5 KVA Inverter being out of service, a defective diode in the power supply to the LT-112 relay, and the black out of power panels supplied via Auxiliary Bus 1E.CAUSE The incident was caused by a procedural inadequacy. | | POWER 20.405 [v) (I ) (I) 50.35(c) (I ) 50.73(e)(2)(v) 73 71(c) |
| The procedure did not clearly state how the check was to be performed. | | LEVEL 20A05( ~ )(I ) (il) 50,73(s) (2) (vii) DTHER (specify ln Aortrect |
| The AO had performed this by using a,slight amount of pressure on the" release pedal.NRC FORM BBBA (94)3)*U.S.GPO;1986 0-624 538/455 NRC Form 366A (963)LICENSEE EVENT REPORT (LER)TEXT CONTIN'ION U.S.NUCLEAR RECULATORY COMMISSION APPROVEO OMB NO.3150&)04 EXPIRES: 8/31/88 FACILITY NAME (I)SHEARON HARRIS PLANT UNIT 1 DOCKET NUMBER (2)YEAR LER NUMBER (6)SEOVENTIAL NVMSER RroI/REVISION NUMBER PACE (3)TEXT/O'IRors 4/Moo/4 o/O/ISIL Iroo o//SooM/HRC Fo/RI 35546/((7)40 OS7 0 1 1 00 03 OF 0 ANALYSIS There were no adverse consequences due to this incident.The event resulted in actuation of components on the 1B-SB bus as required by plant design.The event is reportable per 10CFR50.73(a)(2)(iv) which requires reporting of manual or automatic initiation of any Engineered Safety Feature.CORRECTIVE ACTION A work ticket has been initiated to replace the faulty diode.ACTION TO PREVENT RECURRENCE To prevent a recurrence of this event, a change to OST-1023 has been completed. | | : 00) 0 0 0 50.35(c) (2) helow end ln Test, NRC Form 20.405( ~ ) (1)(ill) 50.73(e) (2)(l) 50.73(e) (2) (vill)(A) 366A) 20A05( ~ ) (I ) (I v) . 50.73(s) (2) (Ii) 50.7 3(e) (2) (vill)(5) 20.405 (e) (I ) (v) 50.73(s) (2) (lii) 50.73( ~ )(2)(s) |
| The procedure now contains the caution statement, NDo not depress the breaker release pedal when breaker is closed, pedal will trip breaker." NRC FORM SSSA (963)*U.S.CPO.'1986 0.624 538/455 | | LICENSEE CONTACT FOR THIS LEA (12I NAME TEI.EPHONE NUMBER AREA CODE R. SCHWABENBAUER REGULATORY TECHNICIAN 919 362 -26 69 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCAIBED IN THIS REPORT (13) i. |
| ~4/Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 APR 0 6 1987 File Number'SHF/10-13510C Letter Number'HO-870395 (0)U.S.Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO.50-400 LICENSE NO.NPF-63 LICENSEE EVENT REPORT 87-011"00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. | | MANUFAC EPOATABLE |
| This report fulfills the requirement for a written report within thirty (30)days of a reportable occurrence and.is in accordance with the format set forth in NUREG-1022, September, 1983.Very truly yours, R.A.Watson Vice President Harris Nuclear Project RAW:skm Enclosure cc.'r.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)}} | | !NM5 MANUFAC. |
| | '.. |
| | ''PORTABLE CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TVRER .. TO NPRDS TVRER TO NPADS h:. Ihr ARIx.. |
| | B E E JX W12 0 N c |
| | X N~.~. '"P hk hA:cNkprg ~. whirr h48X h, SVPPLEMENTAI. REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15) |
| | YES llf yet, complNe EXPECTED SUBMISSION DATE) |
| | ABsTRAGT ILlmlr to tcOO tpecer, l.e., epproxlmetely fifteen tfnpleepece typewritten linnl (15) |
| | ABSTRACT On March 7, 1987, an Auxiliary Operator (AO) was performing a weekly surveillance test (OST-1023) which is for offsite power verification. One of the requirements of the OST is to ensure the breaker release lever is in the neutral position with the breaker closed. When the AO checked Auxiliary Bus IE feeder breaker 121 the breaker was inadvertently tripped open causing the. |
| | de-energization of Auxiliary Bus IE and Safety Bus 1B-SB. This occurred at 2230 hours on March 7, 1987. |
| | The de-energization of Bus 1B-SB caused the 1B-SB Diesel Generator to start and the actuation of Sequencer lB-SB on Bus undervoltage. The AO immediately closed the breaker cabinet and.notified the Control Room of the incident. The Senior Control Operator (SCO) then initiated AOP-025 for the loss of one emergency bus and all plant systems were then returned to normal. |
| | At the- time of the incident, the plant was in Mode 4 at 3450F and 350 psig. |
| | There were no adverse consequences due to this event and safety systems performed as required. To prevent recurrence, the applicable procedure has been revised. |
| | 8704130111 870406 PDR *DOCI('5000400 S PDR NRC Form 355 (94)3) |
| | |
| | NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (94)3) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO, 3150-0)04 EX PIR ES: 8/31/BS FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) FACE (3) |
| | YEAR :R+: SEQUENTIAL |
| | ,8 NUMBER '1'UMBER SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 0 0 011 0 0 02 "0 3 TEXT //F'moro FPoco /4 /or/rokod, Iroo /I/Ooro///RC %%d 36649/ (13 I TEXT DESCRIPTION On March 7, 1987, an Auxiliary Operator (AO) was performing a weekly surveillance test OST-1023 entitled "OFFSITE POWER AVAILABILITYVERIFICATION WEEKLY INTERVAL MODES 1-2-3 6 4." One of the requirements of the OST is to ensure the breaker release lever is in the neutral position with the breaker closed. The AO did this by checking the release lever with his foot for freedom of movement. The AO had used this method without incident in the past. When the AO went to check the Auxiliary Bus 1E feeder breaker 121 the breaker tripped open causing the de-energization of Auxiliary Bus lE. This also de-energized the 1B-SB safety bus thereby activating the 1B-SB Sequencer and starting the 1B-SB Diesel Generator. |
| | The AO immediately closed the breaker cabinet and notified the Control Room. |
| | Upon notification, the Senior Control Operator (SCO) entered Abnormal Operating Procedure AOP-025, entitled "Loss of One Emergency AC Bus (6.9KV) or One Emergency DC (125V) Bus" for the loss of emergency bus and restored all plant systems to normal operation. At the time of the incident, the plant was in Mode 4 at 345'F and 350 psig. |
| | The de-energization of non-safety related Auxiliary Bus 1E also caused the Charging Safety Injection Pumps (CSIP) suction source to automatically transfer from the Volume Control Tank (VCT) to the Refueling Water Storage Tank (RWST). This transfer occurs automatically when both VCT level channels (LT-115 and LT-112) are less than 5X (low low level) or when Safety Injection occurs. This transfer of suction source was due to the de-energization of relays K701 (for LT-115) and K706 (for LT-112) which caused the associated contacts to close and generate a signal to re-position the valves. Relay K701 lost power due to a 7.5 KVA Inverter (the normal power supply) being out of service for a maintenance function, the alternate power supply was via Auxiliary Bus lE. Relay K706 lost power due to a faulty diode which failed to pass the normal power from an uninterruptible source', the backup source was powered via the Auxiliary Bus lE. |
| | The VCT/RWST transfer was caused by a combination of both the 7.5 KVA Inverter being out of service, a defective diode in the power supply to the LT-112 relay, and the black out of power panels supplied via Auxiliary Bus 1E. |
| | CAUSE The incident was caused by a procedural inadequacy. The procedure did not clearly state how the check was to be performed. The AO had performed this by using a,slight amount of pressure on the" release pedal. |
| | NRC FORM BBBA *U.S.GPO;1986 0-624 538/455 (94)3) |
| | |
| | NRC Form 366A U.S. NUCLEAR RECULATORY COMMISSION (963) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTIN'ION APPROVEO OMB NO. 3150&)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (6) PACE (3) |
| | YEAR SEOVENTIAL REVISION NVMSER RroI/ NUMBER SHEARON HARRIS PLANT UNIT 1 40 OS7 0 1 1 00 03 OF 0 TEXT /O'IRors 4/Moo /4 o/O/ISIL Iroo o//SooM/HRC Fo/RI 35546/ ((7) |
| | ANALYSIS There were no adverse consequences due to this incident. The event resulted in actuation of components on the 1B-SB bus as required by plant design. |
| | The event is reportable per 10CFR50.73(a)(2)(iv) which requires reporting of manual or automatic initiation of any Engineered Safety Feature. |
| | CORRECTIVE ACTION A work ticket has been initiated to replace the faulty diode. |
| | ACTION TO PREVENT RECURRENCE To prevent a recurrence of this event, a change to OST-1023 has been completed. The procedure now contains the caution statement, NDo not depress the breaker release pedal when breaker is closed, pedal will trip breaker." |
| | NRC FORM SSSA *U.S.CPO.'1986 0.624 538/455 (963) |
| | |
| | ~4/ |
| | Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 APR 0 6 1987 File Number'SHF/10-13510C Letter Number'HO-870395 (0) |
| | U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-011"00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and .is in accordance with the format set forth in NUREG-1022, September, 1983. |
| | Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW:skm Enclosure cc.'r. J. Nelson Grace (NRC RII) |
| | Mr. B. Buckley (NRR) |
| | Mr. G. Maxwell (NRC SHNPP)}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:RO)
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18022B0551998-05-20020 May 1998
LER 98-005-00:on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim manner.W/980520 Ltr
ML18016A4061998-04-30030 April 1998
LER 98-002-01:on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
ML18016A3841998-04-13013 April 1998
LER 98-004-00:on 980313,design Deficiency Related to Indequate Runout Protection for Turbine Driven AFW Pump Was Identified.Caused by Inadequate Original AFW Sys Design. Evaluation (ESR 98-00100) Will Be completed.W/980409 Ltr
ML18016A3441998-03-12012 March 1998
LER 97-021-02:on 980210,identified Failure to Properly Test non-safety Related Pressurizer Porv.Caused by Inadequate Surveillance Test Procedures.Revised Operations Surveillance Test OST-1117 to Include Testing of Subject PORV
ML18016A3291998-02-27027 February 1998
LER 98-003-00:on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures revised.W/980227 Ltr
ML18016A3211998-02-20020 February 1998
LER 98-002-00:on 980121,solid State Protection Sys Testing Deficiency Occurred.Caused by Inadequate Review of Initial Tech Specs.Ts Testing Frequency for P-11 Permissive Revised. W/980217 Ltr
ML18016A3131998-02-0909 February 1998
LER 98-001-00:on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
ML18016A2641997-12-18018 December 1997
LER 97-024-00:on 971118,SSPS Testing Deficiency Was Noted. Caused by Inadequate Testing Scheme Provided by Ssps Vendor. Revised procedure.W/971218 Ltr
ML18016A2501997-11-24024 November 1997
LER 97-023-00:on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction factor.W/971124 Ltr
ML18016A2201997-10-22022 October 1997
LER 97-021-01:on 970922,discovered That Spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements.Revised Daily Surveillance Procedures
ML18016A2081997-10-14014 October 1997
LER 97-016-01:on 970608,reactor Trip Occurred,Due to Personnel Error While Attempting to Adjust Power Range Nuclear Instrumentation Channel Following Performance of Calorimetric.Procedures revised.W/971014 Ltr
ML18016A2111997-10-14014 October 1997
LER 96-008-02:on 960425,turbine Trip/Reactor Trip Occurred. Caused by High Resistance Connection Resulting from a Phase Switch Jaw & Blade Contacts.Failed a Phase Disconnect Switch on Breaker 52-7 Replaced
ML18016A1931997-09-29029 September 1997
LER 97-022-00:on 970829,TS Required Shutdown Due to Expiration of AFW Lco.Caused by Personnel Error.Completed Repairs TDAFW Pump & Returned Plant to Svc on 970831. W/970926 Ltr
ML18016A1891997-09-12012 September 1997
LER 97-020-00:on 970814,inadequate Fire Protection Provided for safety-related EDG Fuel Oil Transfer Pump Cables Resulted in Operation Outside Design Basis.Caused by Engineering Oversight.Established Fire watches.W/970912 Ltr
ML18016A1881997-09-12012 September 1997
LER 97-021-00:on 970814,spent Fuel Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Misinterpretation of Ts.Directions Provided to Operations.W/970912 Ltr
ML18012A8641997-08-18018 August 1997
LER 97-019-00:on 970720,turbine Trip/Reactor Trip Occurred. Caused by Three Phase Fault That Collapsed Excitation Field in Main Generator,Resulting in Generator Lockout.Exciter Rotor Assembly Was replaced.W/970818 Ltr
ML18012A8581997-08-0808 August 1997
LER 96-018-01:on 960903,manual Reactor Trip Occurred Due to Loss of Normal Sw.Caused by Mechanical Failure of B Water Pump & a Normal SW to Remain Running Once Manually Started.Restored a Normal SW Pump to Svc
ML18012A8551997-08-0808 August 1997
LER 96-013-02:on 961028,condition Outside of Design Basis Where RWST Had Been Aligned w/non-seismically Qualified Sys Was Identified.Caused by Failure to Reconcile Operating Procedure Lineups.Established Administrative Controls
ML18012A8471997-07-31031 July 1997
LER 97-018-00:on 970701,determined That Plant Procedures Had Not Received Proper Reviews & Approvals.Caused by Failure to Comply W/Plant Administrative Procedure AP-006.Counseled Involved individuals.W/970731 Ltr
ML18012A8371997-07-24024 July 1997
LER 97-S01-00:on 970405,unescorted Access Inappropriately Granted to Contract Outage Workers Was Determined.Caused by Personnel Error.Access Files for Individuals Inappropriately Granted Unescorted Access Were Placed on Access Hold
ML18012A8291997-07-11011 July 1997
LER 97-017-00:on 970612,failed to Recognize Inoperable Reactor Afd Monitor.Caused by Personnel Error.Operators Involved in Event Will Be Counseled Prior to Assuming Shift duties.W/970711 Ltr
ML18012A8301997-07-0808 July 1997
LER 97-016-00:on 970608,reactor Trip Occurred Due to Personnel Error in Adjusting Power Range (Pr) Nuclear Instrumentation (Ni).Issued Night Order Prohibiting Pr Ni Adjustment When Redundant Channel inoperable.W/970708 Ltr
ML18012A8241997-07-0202 July 1997
LER 97-015-00:on 970602,inadequate Auxiliary Feedwater Sys Flow Control Valve Surveillance Testing Deficiency Was Identified.Caused by Failure to Recognize Impact on TS 4.7.1.2.1.Readjusted AFW FCV Actuator spring.W/970702 Ltr
ML18022B0181997-06-13013 June 1997
LER 97-014-00:on 970514,SI Occurred During Ssps Surveillance Testing.Caused by Inattention to Detail During Recent Rev to Surveillance Test Procedure Being Used.Revised Deficient Surveillance procedures.W/970613 Ltr
ML18012A8081997-06-0909 June 1997
LER 97-013-00:on 970508,entry Into Mode-6 Without Operable Components,Resulting in TS 3.0.4 Violation Occurred.Caused by Personnel Error.Personnel Involved counseled.W/970609 Ltr
ML18012A8021997-06-0606 June 1997
LER 97-023-02:on 961114,design Deficiency Was Identified in Emergency DG Protection Circuitry.Caused by Inadequate Plant Design.Revised Surveillance Test Procedures OST-1013 & OST-1073.W/970606 Ltr
ML18012A8011997-06-0404 June 1997
LER 97-012-00:on 970505,determined That Previous Auxiliary Control Panel Had Not Verified Operability of Interposing Relays.Caused by Misinterpretation of Tss.Reviewed Other Remote Shutdown Panel Transfer circuitry.W/970604 Ltr
ML18012A7951997-05-29029 May 1997
LER 96-023-01:on 961114,design Deficiency in EDG Protection Circuitry Was Identified.Caused by Inadequate Original Plant Design.Surveillance Test Procedures OST-1013 & OST-1073 revised.W/970529 Ltr
ML18012A7891997-05-22022 May 1997
LER 97-011-00:on 970422,inappropriate TS Interpretation Resulted in Violations of ECCS Accumulator TS & Entry Into TS 3.0.3.Caused by Procedural Inadequacy.Tsi 88-001 Cancelled 970508 & Procedures revised.W/970522 Ltr
ML18012A7871997-05-19019 May 1997
LER 97-010-00:on 970418,design Deficiency Determined Re Reactor Coolant Pump Motor Oil Collection Sys.Caused by RCP Ocs Design Detail.Rcp Ocs Enclosures for Each of Three Installed RCP Motors Have Been modified.W/970519 Ltr
ML18012A7761997-05-0707 May 1997
LER 97-009-00:on 970407,fuse Was Removed from CR Ventilation Isolation Signal Power Supply Circuitry Due to Personnel Error.Individuals Involved Were counseled.W/970507 Ltr
ML18012A7751997-05-0505 May 1997
LER 97-008-00:on 970404,safety-related AHU Not Declared Inoperable During Maintenance on Associated Temperature Switches Resulting in Violation of Ts.Caused by Incorrect Interpretation.Operations Night Order issued.W/970505 Ltr
ML18012A6291997-04-24024 April 1997
LER 97-007-00:on 970325,inoperable CCW Sys TS 3.0.3 Entry Made.Caused by Combination of Procedural Inadequacies, Improper Use of Procedure Guidance & Poor Communication. Applicable Individuals counseled.W/970423 Ltr
ML18022B0151997-04-17017 April 1997
LER 97-006-00:on 970318,breach Was Identified in Thermo-Lag Fire Barrier Wall Due to Inadequate Initial Design,Poor Construction Methods & Incomplete as-built Design.Visual Insp of Thermo-Lag Barrier Walls performed.W/970417 Ltr
ML18012A6041997-04-0303 April 1997
LER 97-004-00:on 970304,in-plant Spent Fuel Cask Handling Activities Conducted Outside Design Basis.Caused by Lack of Understanding of Requirements.Operations Placed on Hold Pending NRC Review & Approval of procedures.W/970331 Ltr
ML18012A6031997-03-31031 March 1997
LER 97-003-00:on 970227,steam Generator Low Level Protection Circuitry Outside Design Basis Occurred.Caused by Inadequate Failure Modes & Effects Analysis Performed as-built Piping Configuration for S/G Level.Review performed.W/970331 Ltr
1999-09-10
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18017A9181999-10-0808 October 1999
LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr
ML18017A9151999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18017A8671999-09-10010 September 1999
LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr
ML18017A8621999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr
ML18016B0481999-08-0404 August 1999
LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised
ML18017A8361999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Shearon Harris Nuclear Power Plant.With 990811 Ltr
ML18016B0151999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Shearon Harris Npp. with 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18016A9801999-06-0404 June 1999
LER 99-006-00:on 981124,failed to Comply with TS 4.0.4 & TS 3/4.6.3, Civ. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Will Be Revised.With 990604 Ltr
ML18016A9851999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990614 Ltr
ML18017A8981999-05-12012 May 1999
Technical Rept Entitled, Harris Nuclear Plant-Bacteria Detection in Water from C&D Spent Fuel Pool Cooling Lines.
ML18016A9581999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Shearon Harris Nuclear Plant,Unit 1.With 990513 Ltr
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML18016A9111999-04-12012 April 1999
LER 99-005-00:on 990313,plant Exceeded ESFAS TS 3.3.2,Action 21.Caused by Inadequate Procedure Rev Preparation.Licensee Revised Applicable Maint Surveillance Test Procedure (MST-10072) to Identify TS Required Actions.With 990412 Ltr
ML18016A8971999-04-0808 April 1999
LER 99-004-00:on 990312,unit Trip Was Noted.Caused by Degraded Condition of SG Water Level Flow Control Valve. Replaced Positioners on All Three FW Regulating Valves.With 990408 Ltr
ML18016A8941999-04-0505 April 1999
Revised Pages 20-25 to App 4A of non-proprietary Version of Rev 3 to HI-971760
ML18016A9101999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Shearon Harris Nuclear Power Plant.With 990413 Ltr
ML18016A8661999-03-31031 March 1999
Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept.
ML18017A8931999-02-28028 February 1999
Risks & Alternative Options Associated with Spent Fuel Storage at Shearon Harris Nuclear Power Plant.
ML18016A8551999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Shearon Harris Npp. with 990312 Ltr
ML18016A8261999-02-22022 February 1999
LER 99-003-00:on 990123,noted That Plant Was Outside Design Basis Due to Isolation of Fire Protection Containment Sprinkler Sys.Caused by Human Error.Restored Containment Sprinkler Sys to Operable Status.With 990222 Ltr
ML18016A8531999-02-18018 February 1999
Non-proprietary Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFP 'C' & 'D'.
ML18016A8111999-02-12012 February 1999
LER 99-002-00:on 990114,RT Due to Not Removing Temporary Device from Relay Following Calibration Was Noted.Caused by Human Error.Counseled Personnel Involved in Event.With 990212 Ltr
ML18016A7971999-02-0505 February 1999
LER 99-001-00:on 990106,SF Pool Water Level Was Not Maintained Greater than 23 Feet Above Stored BWR Fuel Assemblies.Caused by Fasteners Bending Under Specific Circumstances.Increased Water Level.With 990205 Ltr
ML18022B0631999-02-0404 February 1999
Rev 0 to Nuclear NDE Manual. with 28 Oversize Uncodable Drawings of Alternative Plan Scope & 4 Oversize Codable Drawings
ML20202J1161999-02-0101 February 1999
SER Accepting Relief Requests Associated with Second 10-year Interval Inservice Testing Program
ML18016A8041999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Shearon Harris Nuclear Power Plant.With 990211 Ltr
ML18016A7941999-01-29029 January 1999
LER 98-004-01:on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
ML18016A7801998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Shearon Harris Npp. with 990113 Ltr
ML18016A7671998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Shnpp,Unit 1.With 981215 Ltr
ML18016A9731998-11-28028 November 1998
Changes,Tests & Experiments, for Harris Nuclear Plant.Rept Provides Brief Description of Changes to Facility & Summary & of SE for Each Item That Was Implemented Under 10CFR50.59 Between 970608-981128.With 990527 Ltr
ML18016A8351998-11-28028 November 1998
ISI Summary 8th Refueling Outage for Shearon Harris Power Plant,Unit 1.
ML18016A7411998-11-25025 November 1998
Rev 1 to Shnpp Cycle 9 Colr.
ML18016A7211998-11-17017 November 1998
LER 98-007-00:on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With 981117 Ltr
ML18016A7071998-11-0303 November 1998
Rev 0 to Harris Unit 1 Cycle 9 Colr.
ML18016A7201998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Shearon Harris Nuclear Power Plant.With 981113 Ltr
ML20154F8701998-10-0606 October 1998
Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves
ML18016A6201998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Harris Nuclear Power Plant.With 981012 Ltr
ML18016A5971998-09-21021 September 1998
Rev 1 to Harris Unit 1 Cycle 8 Colr.
ML18016A5881998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Shnpp,Unit 1.With 980914 Ltr
ML18016A5071998-07-31031 July 1998
Monthly Operating Rept for Jul 1998 for Shearon Harris Nuclear Plant.W/980811 Ltr
ML18016A9431998-07-0707 July 1998
Rev 1 to QAP Manual.
ML18016A4841998-07-0707 July 1998
LER 97-002-01:on 970207,determined That Cold Weather Conditions Resulted in Mfiv Being Potentially Inoperable During Period 970117-20.Caused by Inadequate Design of HVAC Sys.Implemented Mods to Steam Tunnel HVAC Sys
ML18016A9371998-06-30030 June 1998
Technical Rept on Matl Identification of Spent Fuel Piping Welds at Hnp.
ML18016A4861998-06-30030 June 1998
Monthly Operating Rept for June 1998 for SHNPP.W/980715 Ltr
ML18016A4701998-06-30030 June 1998
LER 97-021-03:on 980210,discovered That SFP Water Level Had Not Been Verified Greater than 23 Feet Above BWR Fuel Assemblies.Caused by Misinterpretation of TS Requirements. Will Submit TS Change Request to Revise TS 3.9.1.11
ML18016A4491998-06-0808 June 1998
LER 98-006-00:on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling each.W/980608 Ltr
ML18016A4521998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Shearon Harris Nuclear Power Plant.W/980612 Ltr
ML18016A7711998-05-26026 May 1998
Non-proprietary Rev 2 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris Spent Fuel Pools 'C' & 'D'.
1999-09-30
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Text
REGULA Y INFORNATION DISTR IBUTI0 YSTEN (R IDS>
- ACCESSION NBR
- 8704130111 DOC. DATE: 87/04/06 NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Power Plant> Unit 1> Carolina 05000400 AUTH. NANE AUTHOR AFF ILIAT I ON BCHWABENBAUER Carol in a P over 8c Light C o.
WATSON> R. A. Carolina Poeer 5 Light Co..
RECIP. NAME RECIPIENT AFFILIATION
SUBJECT:
LER 87-011-00: on 870307> auxiliary bus IE feedeY breaker 121 tripped open> causing de-energization of auxiliary bus IE 5 safety bus 1B-SB. Caused bg procedural inadequacy. Work tic ket initiated to replace diode. W/870406 ltr.
DISTRIBUTION CODE: IESSD COPIES RECEIVED: LTR I ENCL I SIIE:
TITLE: 50. 73 Licensee Event Report (LER)> Incident Rpt> etc.
NOTES: App lication for permit reneu'al f iled. 05000400 RECIPIENT COPIEB RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 L* 1 1 PD2-1 PD 1 BUCKLEY> B 1 INTERNAL: ACRS MICHELSON 1 1 ACRB NOELLER 1 1 ACRB WYLIE 1 AEOD/DOA 1 1 AEOD/DBP/ROAB 2 2 AEOD/DSP/TAPB 1 NRR/ADT 1 NRR/DEBT/ADE 0 NRR/DEBT/ADS 1 0 ERR/DEBT/CEB 1 1 NRR/DEBT/ELB 1 1 ERR /DEBT/ I CSB 1 1 NRR/DEST/MEB 1 NRR/DEST/MTB 1 1 NRR/DEBT/PSB 1 1 NRR/DEST/RSB 1 NRR/DEBT/SGB 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/EPB 1 1 NRR/DREP/RAB 1 1 BR /ILRB 1 NRR/PNAS/PTSB 1 1 REG FIL 02 RES SPEIS> T 1 1 RGN2 FILE 01 1 EXTERNAL: EQ8cG GROH> N 5 5 H ST LOBBY WARD LPDR 1 NRC PDR NSI C HARRIS> J 1 1 NSIC MAYS> G TOTAL NU >HER OF COP IES REQUIRED: LTTR 41 ENCL 39
NRC Form 3FS U rL NUCLEAR REQULATORY COMMISSION (94)3) APPROVED OMB NO. 31504104 EXPIRES) 5/31/SS LICENSEE EVENT REPORT (LER)
FACILITY NAME (I) DOCKET NUMBER (2) PA E 3I SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 0 1 QF 0 3 TITLE (4)
"6.9 KV ONSITE DISTRIBUTION" EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED IS)
YEAR SEQUENTIAL Mb Rt VISION MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(S)
MONTH DAY YEAR NUMBER 5M NUMBER 0 5 0 0 0 0 3 0 7 8 7 011 0 04 6 87 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (): (Check one or more of the follovy'npl (11)
OPERATINQ MODE (9) 20A02(II) 20.405(c) 50.73 (e) (2) (Iv) 73.71(5)
POWER 20.405 [v) (I ) (I) 50.35(c) (I ) 50.73(e)(2)(v) 73 71(c)
LEVEL 20A05( ~ )(I ) (il) 50,73(s) (2) (vii) DTHER (specify ln Aortrect
- 00) 0 0 0 50.35(c) (2) helow end ln Test, NRC Form 20.405( ~ ) (1)(ill) 50.73(e) (2)(l) 50.73(e) (2) (vill)(A) 366A) 20A05( ~ ) (I ) (I v) . 50.73(s) (2) (Ii) 50.7 3(e) (2) (vill)(5) 20.405 (e) (I ) (v) 50.73(s) (2) (lii) 50.73( ~ )(2)(s)
LICENSEE CONTACT FOR THIS LEA (12I NAME TEI.EPHONE NUMBER AREA CODE R. SCHWABENBAUER REGULATORY TECHNICIAN 919 362 -26 69 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCAIBED IN THIS REPORT (13) i.
MANUFAC EPOATABLE
!NM5 MANUFAC.
'..
PORTABLE CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT TVRER .. TO NPRDS TVRER TO NPADS h:. Ihr ARIx..
B E E JX W12 0 N c
X N~.~. '"P hk hA:cNkprg ~. whirr h48X h, SVPPLEMENTAI. REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (15)
YES llf yet, complNe EXPECTED SUBMISSION DATE)
ABsTRAGT ILlmlr to tcOO tpecer, l.e., epproxlmetely fifteen tfnpleepece typewritten linnl (15)
ABSTRACT On March 7, 1987, an Auxiliary Operator (AO) was performing a weekly surveillance test (OST-1023) which is for offsite power verification. One of the requirements of the OST is to ensure the breaker release lever is in the neutral position with the breaker closed. When the AO checked Auxiliary Bus IE feeder breaker 121 the breaker was inadvertently tripped open causing the.
de-energization of Auxiliary Bus IE and Safety Bus 1B-SB. This occurred at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br /> on March 7, 1987.
The de-energization of Bus 1B-SB caused the 1B-SB Diesel Generator to start and the actuation of Sequencer lB-SB on Bus undervoltage. The AO immediately closed the breaker cabinet and.notified the Control Room of the incident. The Senior Control Operator (SCO) then initiated AOP-025 for the loss of one emergency bus and all plant systems were then returned to normal.
At the- time of the incident, the plant was in Mode 4 at 3450F and 350 psig.
There were no adverse consequences due to this event and safety systems performed as required. To prevent recurrence, the applicable procedure has been revised.
8704130111 870406 PDR *DOCI('5000400 S PDR NRC Form 355 (94)3)
NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (94)3)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO, 3150-0)04 EX PIR ES: 8/31/BS FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) FACE (3)
YEAR :R+: SEQUENTIAL
,8 NUMBER '1'UMBER SHEARON HARRIS PLANT UNIT 1 0 5 0 0 0 4 0 0 011 0 0 02 "0 3 TEXT //F'moro FPoco /4 /or/rokod, Iroo /I/Ooro///RC %%d 36649/ (13 I TEXT DESCRIPTION On March 7, 1987, an Auxiliary Operator (AO) was performing a weekly surveillance test OST-1023 entitled "OFFSITE POWER AVAILABILITYVERIFICATION WEEKLY INTERVAL MODES 1-2-3 6 4." One of the requirements of the OST is to ensure the breaker release lever is in the neutral position with the breaker closed. The AO did this by checking the release lever with his foot for freedom of movement. The AO had used this method without incident in the past. When the AO went to check the Auxiliary Bus 1E feeder breaker 121 the breaker tripped open causing the de-energization of Auxiliary Bus lE. This also de-energized the 1B-SB safety bus thereby activating the 1B-SB Sequencer and starting the 1B-SB Diesel Generator.
The AO immediately closed the breaker cabinet and notified the Control Room.
Upon notification, the Senior Control Operator (SCO) entered Abnormal Operating Procedure AOP-025, entitled "Loss of One Emergency AC Bus (6.9KV) or One Emergency DC (125V) Bus" for the loss of emergency bus and restored all plant systems to normal operation. At the time of the incident, the plant was in Mode 4 at 345'F and 350 psig.
The de-energization of non-safety related Auxiliary Bus 1E also caused the Charging Safety Injection Pumps (CSIP) suction source to automatically transfer from the Volume Control Tank (VCT) to the Refueling Water Storage Tank (RWST). This transfer occurs automatically when both VCT level channels (LT-115 and LT-112) are less than 5X (low low level) or when Safety Injection occurs. This transfer of suction source was due to the de-energization of relays K701 (for LT-115) and K706 (for LT-112) which caused the associated contacts to close and generate a signal to re-position the valves. Relay K701 lost power due to a 7.5 KVA Inverter (the normal power supply) being out of service for a maintenance function, the alternate power supply was via Auxiliary Bus lE. Relay K706 lost power due to a faulty diode which failed to pass the normal power from an uninterruptible source', the backup source was powered via the Auxiliary Bus lE.
The VCT/RWST transfer was caused by a combination of both the 7.5 KVA Inverter being out of service, a defective diode in the power supply to the LT-112 relay, and the black out of power panels supplied via Auxiliary Bus 1E.
CAUSE The incident was caused by a procedural inadequacy. The procedure did not clearly state how the check was to be performed. The AO had performed this by using a,slight amount of pressure on the" release pedal.
NRC FORM BBBA *U.S.GPO;1986 0-624 538/455 (94)3)
NRC Form 366A U.S. NUCLEAR RECULATORY COMMISSION (963)
LICENSEE EVENT REPORT (LER) TEXT CONTIN'ION APPROVEO OMB NO. 3150&)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER (6) PACE (3)
YEAR SEOVENTIAL REVISION NVMSER RroI/ NUMBER SHEARON HARRIS PLANT UNIT 1 40 OS7 0 1 1 00 03 OF 0 TEXT /O'IRors 4/Moo /4 o/O/ISIL Iroo o//SooM/HRC Fo/RI 35546/ ((7)
ANALYSIS There were no adverse consequences due to this incident. The event resulted in actuation of components on the 1B-SB bus as required by plant design.
The event is reportable per 10CFR50.73(a)(2)(iv) which requires reporting of manual or automatic initiation of any Engineered Safety Feature.
CORRECTIVE ACTION A work ticket has been initiated to replace the faulty diode.
ACTION TO PREVENT RECURRENCE To prevent a recurrence of this event, a change to OST-1023 has been completed. The procedure now contains the caution statement, NDo not depress the breaker release pedal when breaker is closed, pedal will trip breaker."
NRC FORM SSSA *U.S.CPO.'1986 0.624 538/455 (963)
~4/
Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 APR 0 6 1987 File Number'SHF/10-13510C Letter Number'HO-870395 (0)
U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-011"00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and .is in accordance with the format set forth in NUREG-1022, September, 1983.
Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW:skm Enclosure cc.'r. J. Nelson Grace (NRC RII)
Mr. B. Buckley (NRR)
Mr. G. Maxwell (NRC SHNPP)
