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| | issue date = 04/30/1987 | | | issue date = 04/30/1987 |
| | title = LER 87-018-00:on 870403,manual Reactor Trip Initiated Due to Loss of Both Main Feedwater Pumps.Caused by Inadvertent Short of Test Leads in Process Instrumentation Cabinet & Incorrect Setpoint.Undocumented Leads removed.W/870430 Ltr | | | title = LER 87-018-00:on 870403,manual Reactor Trip Initiated Due to Loss of Both Main Feedwater Pumps.Caused by Inadvertent Short of Test Leads in Process Instrumentation Cabinet & Incorrect Setpoint.Undocumented Leads removed.W/870430 Ltr |
| | author name = HOWE A, WATSON R A | | | author name = Howe A, Watson R |
| | author affiliation = CAROLINA POWER & LIGHT CO. | | | author affiliation = CAROLINA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:REQUL Y INFORMATION DIBTRIBUTI SYSTEM<R IDS)i ACCESSION NBR: 87050b0271 DOC.DATE: 87/04/30 NOTARIZED: | | {{#Wiki_filter:REQUL Y INFORMATION DIBTRIBUTI SYSTEM <R IDS) i ACCESSION NBR: 87050b0271 DOC. DATE: 87/04/30 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Pover Plant> Unit 1P Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HOWE'. Carolina Power 8c Light Co. |
| NO FACIL: 50-400 Shearon Harris Nuclear Pover Plant>Unit 1P Carolina AUTH.NAME AUTHOR AFFILIATION HOWE'.Carolina Power 8c Light Co.WATSON>R.A.Carol ina Poller 8(Light Co.RECIP.NAME-RECIPIENT AFFILIATION DOCKET¹05000400 SUB JECT: LER 87-018-00: | | WATSON> R. A. Carol ina Poller 8( Light Co. |
| on 870403>manual reactor trip initiated due to loss of both main feedeater pumps.Caused bg inadvertent short of test leads in process instrumentation cabi,net 0 incorrect setpoint.Undocumented leads removed.W/870430 ltr.DISTRIBUTION CODE: IE22D COPIEB RECEIVED: LTR g ENCL Q SIZE: TITLE: 50.73 Licensee Event Report (LER)i Incident Rpti etc.NOTES: Application for permit reneual filed.05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY B INTERNAL: ACRS MICHELBON AEOD/DOA AEOD/DSP/TPAB NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEBT/PSB NRR/DEST/SQB NRR/DLPG/GAB NRR/DREP/EPB NRR/DREP/RPB NRR/PMAS/PTSB RES SPEIS T EXTERNAL: EQhQ QROH, M LPDR NSI C HARR IS>J COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1~1 1 2 2 1 1 1 1 5 5 1 1 1 REC IP I ENT ID CODE/NAME PD2-1 PD ACRS MOELLER AFOD/DSP/ROAB NRR/DEST/*DE NRR/DEST/CEB NRR/DEST/I CSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RAB RB REQ FILE 02 FILE 01 H BT LOBBY WARD NRC PDR NSIC MAYSi Q COP IEB LTTR ENCL 1 1 2 2 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTlR 41 ENCL 39 NRC Form 388 (943)LICENSEE EVENT REPORT (LER)U.S, NUCLEAA REOULATORY COMMISSION APPAOVED OMB NO.3150010k EXPIAESI 8/31/88 FACILITY NAME (I)Shearon Harris Plant-Unit 1 TITLE (8)Reactor Trip-Loss of Feedwater DOCKET NUMBER (2)0 5 0 0 0 PACE 3 1 OF MONTH DAY YEAR EVENT DATE (5)YEAR LFR NUMBER (5)SSOVENTIAL re)NUMBER S..I REVISION NVMSSR MONTH DAY YEAR REPORT DATE IT)DOCKET NUMBER(S)0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED (8)04 03 8 7 OPERATINO MODE (8)1 POWER LEVEL Ci~k@&E'7 0 1 8 0 0 50,73(e)(2)llr)50.73(e)(2)(r)THIS REPORT IS SUBMITTED PURSUANT 7 20A02(8)20AOS(e)(1)(O 20AOS(el(1) | | RECIP. NAME - RECIPIENT AFFILIATION SUB JECT: LER 87-018-00: on 870403> manual reactor trip initiated due to loss of both main feedeater pumps. Caused bg inadvertent short of test leads in process instrumentation cabi,net 0 incorrect setpoint. Undocumented leads removed. W/870430 ltr. |
| (4)20AOS(e)(l)(IB) 20AOB(e)l1)(lv) 20AOS(e))1)lrl 20AOS(cl SOM(c)(I)50.38(c)(2)50.73(~l(2)ll)50.73(el(2)(ll) 50.73(e l(2)(ill)50.73(el(2)(rill 50.73(el(2)(rill)(A)50.73(e)l2)(vill)(B) 50.73(~)(2)(x I I.ICENSEE CONTACT FOR THIS LER (12I 0 THE REOUIREMENTS OF 10 CFR (): ICneck one or more of the follorflnpl l11 73,71(8)73.71(cl 0 5 0 0 0 OTHER ISpeclfy In Abnrert INIow end ln Text, IVIIC Form 3SSAI NAME Andrew Howe-Re ulator Cpm 1 TELEPHONE NUMBER AREA CODE 919 362 27 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS AEPOAT (13)CAUSE SYSTEM COMPONENT MANUFAC-TURER REPORTABLE TO NPRDS Hp'I CAUSE".''C:)'x SYSTEM COMPONENT MANUFAC.TURER EPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED (18)YES Ilf yer, complete EXPECTED SUBSIISSION OATEI NO ABsTAAcT (Limit ro IcoO rpeceL l.e., epproxlmetely fifteen tlnple.tpece typewritten linn/(15)EXPECTED SU 5 M I SS ION DATE I'IS)MONTH DAY YEAR At 1126 on April 3, 1987, with the plant operating at 75K thermal power level and 560 MWe, a manual turbine trip and subsequent reactor trip was initiated. | | DISTRIBUTION CODE: IE22D COPIEB RECEIVED: LTR g TITLE: 50. 73 Licensee Event Report (LER) i Incident Rpti etc. |
| The trip was required due to a loss of both main feedwater pumps and the subsequent decrease in steam generator levels.The motor driven auxiliary feedwater pumps started automatically as required upon loss of both main feedwater pumps.Subsequent to the trip the main steamline isolation valves were manually closed to limit the cooldown transient on the Reactor Coolant System (RCS).The plant was stabilized in Mode 3 at the'zero-load RCS Tavg of 557'F.87050b027i 870430 PDR (E)DOCK 05000400 S PDR 5 GRZ l~NRC Form 388 NRC Fotm 366A (94)3)LICENSEE EVENT REPORT{LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150&104 EXPIRES: 8/3)/(8 FACILITY NAME (1)OOCKET NUMBER (2)LER NUMBER (6)YEAR i%A SEQUENTIAL
| | ENCL Q SIZE: |
| ?4 REVISION NUMBER':?A NUMBER PAGE (3)Shearon Harris Plant-'TEXT///mFm 4/>>ce/4/Eqv/FF/
| | NOTES: Application for permit reneual filed. 05000400 RECIPIENT COPIES REC IP I ENT COP IEB ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 BUCKLEY B 1 1 INTERNAL: ACRS MICHELBON 1 1 ACRS MOELLER 1 AEOD/DOA 1 1 AFOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 NRR/DEST/*DE 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB NRR/DEST/ I CSB 1 1 NRR/DEST/MEB 1 NRR/DEST/MTB 1 1 NRR/DEBT/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SQB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB 1 1 NRR/DREP/EPB ~ |
| 1>>4/I/EEV>>/HRC F4mI 3884'4/(17)0 5 0 0 0 018 0 0 02 DESCRIPTION On April 3, 1987, the plant was operating at approximately 75X thermal power level and 560 MWe.Plant conditions were being maintained in steady state following a reactor startup on April 1 (Reference LER-87-017-0) to allow stabilization of Xenon in the core in preparation for further power ascension testing.At approximately 1123, a low flow annunciator for condensate booster pump 1B alarmed, and at 1125 condensate booster pump 1B tripped, followed by main feedwater pump 1B.Automatic turbine runback to 50X power did not automatically occur as expected, and the operators manually reduced turbine load.At 1126, both heater drain pumps tripped, and before turbine load could be reduced significantly, the second main feedwater pump tripped.,Both motor-driven auxiliary feedwater pumps automatically started due to trip of both main feedwater pumps.Since feedwater could not be immediately restored, a manual trip was initiated.
| | 1 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 RB 1 NRR/PMAS/PTSB 1 1 REQ FILE 02 RES SPEIS T 1 1 FILE 01 1 EXTERNAL: EQhQ QROH, M 5 5 H BT LOBBY WARD 1 LPDR 1 1 NRC PDR 1 NSI C HARR IS> J 1 NSIC MAYSi Q 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTlR 41 ENCL 39 |
| The manual turbine trip was initiated prior to a manual reactor trip, so the reactor trip occurred due to the turbine trip with reactor power above the P-7 interlock setpoint of 10X power.Subsequent to the trip, the plant was stabilized in Mode 3 at the zero-load RCS Tavg of 557'F with the main steamline isolation valves manually closed to limit the initial cooldown transient.
| | |
| The cause of the trip was investigated and resolved, and the plant was returned to service on April 4, 1987.CAUSE The initiating event was the trip of condensate booster pump 1B due to a low flow trip caused when test leads connected into the flow instrumentation card in the process instrumentation cabinet (PIC)were inadvertently shorted together.These test leads were being used to provide additional data for evaluating main feedwater and condensate pump trips (Refer'ence LERs 87-008-0, 87-013-0, 87-017-0). | | NRC Form 388 U.S, NUCLEAA REOULATORY COMMISSION (943) APPAOVED OMB NO. 3150010k EXPIAESI 8/31/88 LICENSEE EVENT REPORT (LER) |
| A decision had been made by plant management to connect a personal computer to various condensate and feedwater instrumentation points.During installation, it was determined that additional isolation resistors were necessary between the computer and the plant instrumentation loops.The leads were to be removed from the PIC for the installation of these resistors; however, for one lead, this was not done.As a result, when the resistors were being soldered into the circuit where the lead had not been removed, the circuit was grounded or shorted, causing a low flow annunciator and trip of the condensate booster pump.The PIC where the test leads were installed was physically separated from the area where the isolation resistors were being installed.
| | FACILITY NAME (I) DOCKET NUMBER (2) PACE 3 Shearon Harris Plant Unit 1 0 5 0 0 0 1 OF TITLE (8) |
| The technician working on the isolation resistors could not view the connected test leads and in fact thought all test leads had been disconnected. | | Reactor Trip Loss of Feedwater EVENT DATE (5) LFR NUMBER (5) REPORT DATE IT) OTHER FACILITIES INVOLVED (8) |
| 'NRC FORM 366A (943)+U.S.GPO;1988.0.824 538/455 NRC Form 368A (983)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVEO OMB NO, 3150M(OS EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)gag SEQUENTIAL 4%m NUMBER~+: REVISION NUMBER PACE (3)Shearon Harris Plant-Unit 1 TEXT///morB B/roce/B r/U/IBI/Uw B//dOIN/NRC Form 3////AB/(I 2)0 5 0 0 0 P 0 0 1 8 0 0 OF.CAUSE (continued)
| | MONTH DAY YEAR YEAR SSOVENTIAL re) REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S) |
| The cause of the second main feedwater pump trip is attributed to low suction pressure due to high feedwater flow while operators were attempting to reduce the turbine load and adjust steam generator levels manually.The heater drain pump trips were likely caused by the transient created by the condensate booster pump trip.The test leads had been connected and disconnected in an informal manner without appropriate documentation.
| | NUMBER S.. I NVMSSR 0 5 0 0 0 04 03 8 7 7 0 1 8 0 0 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT 7 0 THE REOUIREMENTS OF 10 CFR (): ICneck one or more of the follorflnpl l11 OPERATINO MODE (8) 1 20A02(8) 20AOS(cl 50,73(e) (2) llr) 73,71(8) |
| As a result there was no inventory against which to check that all leads had been disconnected prior to starting work on the isolation resistors.
| | POWER 20AOS(e) (1)(O SOM(c) (I) 50.73(e) (2)(r) 73.71(cl LEVEL 20AOS(el(1) (4) 50.38(c) (2) 50.73(el(2) (rill OTHER ISpeclfy In Abnrert l2)(vill)(B) INIow end ln Text, IVIIC Form 20AOS(e)(l)(IB) 50.73( ~ l(2) ll) 50.73(el(2) (rill)(A) 3SSAI 20AOB(e)l1)(lv) 50.73(el(2)(ll) 50.73(e) |
| Other test leads were connected to the PICs for approved and ongoing tests although not actively in use at the time..The failure of the turbine runback feature to reduce load to'50X upon trip of one main feedwater pump was due to an incorrect setpoint for a turbine first stage pressure permissive.
| | Ci~k@&E' 20AOS(e) )1) lrl 50.73(e l(2)(ill) 50.73( ~ ) (2) (x I I.ICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE Andrew Howe Re ulator Cpm 1 919 362 27 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS AEPOAT (13) |
| The pressure setting specified by design was too high to allow the runback to function for this event.CORRECTIVE ACTION Temporary leads which are not documented by an approved procedure were removed from the PICs, and the cabinets were inspected to verify this condition.
| | CAUSE SYSTEM COMPONENT MANUFAC-TURER REPORTABLE TO NPRDS Hp'I CAUSE SYSTEM COMPONENT MANUFAC. |
| Additionally, test leads installed by approved procedures which were not in active use were also removed.Future installation of temporary monitoring equipment will only be in accordance with approved procedures, and such installations will include an independent verification, as appropriate.
| | TURER EPORTABLE TO NPRDS |
| Additionally, test leads will only be connected when required for test and removed after test completion.
| | ".' 'C:) |
| NRC FORM 366A (94)3)*U.S.GPO;1988 0.824 538/455 Carolina Power 8 Light Cornpant HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 APR 3 0]gg7 File Number'SHF/10-13510C Letter Number.'HO-870412 (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 87-018-00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
| | 'x SUPPLEMENTAL REPORT EXPECTED (18) MONTH DAY YEAR EXPECTED SU 5 M I SS ION DATE I'IS) |
| 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, RAW:bjb Enclosure R.A.Watson Vice President Harris Nuclear Project cc.'Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRC)Mr.G.Maxwell (NRC-SHNPP)MEM/HO-8704120/Page 1/OS1}}
| | YES Ilfyer, complete EXPECTED SUBSIISSION OATEI NO ABsTAAcT (Limit ro IcoO rpeceL l.e., epproxlmetely fifteen tlnple.tpece typewritten linn/ (15) |
| | At 1126 on April 3, 1987, with the plant operating at 75K thermal power level and 560 MWe, a manual turbine trip and subsequent reactor trip was initiated. The trip was required due to a loss of both main feedwater pumps and the subsequent decrease in steam generator levels. The motor driven auxiliary feedwater pumps started automatically as required upon loss of both main feedwater pumps. |
| | Subsequent to the trip the main steamline isolation valves were manually closed to limit the cooldown transient on the Reactor Coolant System (RCS). |
| | The plant was stabilized in Mode 3 at the'zero-load RCS Tavg of 557 'F. |
| | 87050b027i 870430 PDR (E)DOCK 05000400 5 GRZ S l~ |
| | PDR NRC Form 388 |
| | |
| | NRC Fotm 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3) |
| | LICENSEE EVENT REPORT {LER) TEXT CONTINUATION APPROVED OMB NO. 3150&104 EXPIRES: 8/3)/(8 FACILITY NAME (1) OOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | ? 4 REVISION i%A SEQUENTIAL ':?A YEAR NUMBER NUMBER Shearon Harris Plant 0 5 0 0 0 018 0 0 02 |
| | 'TEXT ///mFm 4/>>ce /4/Eqv/FF/ 1>>4 /I/EEV>>/ HRC F4mI 3884'4/ (17) |
| | DESCRIPTION On April 3, 1987, the plant was operating at approximately 75X thermal power level and 560 MWe. Plant conditions were being maintained in steady state following a reactor startup on April 1 (Reference LER-87-017-0) to allow stabilization of Xenon in the core in preparation for further power ascension testing. |
| | At approximately 1123, a low flow annunciator for condensate booster pump 1B alarmed, and at 1125 condensate booster pump 1B tripped, followed by main feedwater pump 1B. Automatic turbine runback to 50X power did not automatically occur as expected, and the operators manually reduced turbine load. At 1126, both heater drain pumps tripped, and before turbine load could be reduced significantly, the second main feedwater pump tripped. ,Both motor |
| | -driven auxiliary feedwater pumps automatically started due to trip of both main feedwater pumps. Since feedwater could not be immediately restored, a manual trip was initiated. The manual turbine trip was initiated prior to a manual reactor trip, so the reactor trip occurred due to the turbine trip with reactor power above the P-7 interlock setpoint of 10X power. |
| | Subsequent to the trip, the plant was stabilized in Mode 3 at the zero-load RCS Tavg of 557 'F with the main steamline isolation valves manually closed to limit the initial cooldown transient. |
| | The cause of the trip was investigated and resolved, and the plant was returned to service on April 4, 1987. |
| | CAUSE The initiating event was the trip of condensate booster pump 1B due to a low flow trip caused when test leads connected into the flow instrumentation card in the process instrumentation cabinet (PIC) were inadvertently shorted together. These test leads were being used to provide additional data for evaluating main feedwater and condensate pump trips (Refer'ence LERs 87-008-0, 87-013-0, 87-017-0). A decision had been made by plant management to connect a personal computer to various condensate and feedwater instrumentation points. During installation, it was determined that additional isolation resistors were necessary between the computer and the plant instrumentation loops. The leads were to be removed from the PIC for the installation of these resistors; however, for one lead, this was not done. As a result, when the resistors were being soldered into the circuit where the lead had not been removed, the circuit was grounded or shorted, causing a low flow annunciator and trip of the condensate booster pump. The PIC where the test leads were installed was physically separated from the area where the isolation resistors were being installed. The technician working on the isolation resistors could not view the connected test leads and in fact thought all test leads had been disconnected. |
| | 'NRC FORM 366A + U.S.GPO;1988.0.824 538/455 (943) |
| | |
| | NRC Form 368A U.S. NUCLEAR REOULATORY COMMISSION (983) |
| | LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO, 3150M(OS EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PACE (3) |
| | YEAR gag SEQUENTIAL ~+: REVISION 4%m NUMBER NUMBER OF . |
| | Shearon Harris Plant Unit 1 0 5 0 0 0 P 0 0 1 8 0 0 TEXT /// morB B/roce /B r/U/IBI/ Uw B//dOIN/ NRC Form 3////AB/ (I2) |
| | CAUSE (continued) |
| | The cause of the second main feedwater pump trip is attributed to low suction pressure due to high feedwater flow while operators were attempting to reduce the turbine load and adjust steam generator levels manually. The heater drain pump trips were likely caused by the transient created by the condensate booster pump trip. |
| | The test leads had been connected and disconnected in an informal manner without appropriate documentation. As a result there was no inventory against which to check that all leads had been disconnected prior to starting work on the isolation resistors. Other test leads were connected to the PICs for approved and ongoing tests although not actively in use at the time. |
| | .The failure of the turbine runback feature to reduce load to'50X upon trip of one main feedwater pump was due to an incorrect setpoint for a turbine first stage pressure permissive. The pressure setting specified by design was too high to allow the runback to function for this event. |
| | CORRECTIVE ACTION Temporary leads which are not documented by an approved procedure were removed from the PICs, and the cabinets were inspected to verify this condition. |
| | Additionally, test leads installed by approved procedures which were not in active use were also removed. Future installation of temporary monitoring equipment will only be in accordance with approved procedures, and such installations will include an independent verification, as appropriate. |
| | Additionally, test leads will only be connected when required for test and removed after test completion. |
| | NRC FORM 366A *U.S.GPO;1988 0.824 538/455 (94)3) |
| | |
| | Carolina Power 8 Light Cornpant HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 APR 3 0 ]gg7 File Number'SHF/10-13510C Letter Number.'HO-870412 (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 87-018-00 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:bjb Enclosure cc. 'Dr. J. Nelson Grace (NRC RII) |
| | Mr. B. Buckley (NRC) |
| | Mr. G. Maxwell (NRC SHNPP) |
| | MEM/HO-8704120/Page 1/OS1}} |
|
|---|
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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REQUL Y INFORMATION DIBTRIBUTI SYSTEM <R IDS) i ACCESSION NBR: 87050b0271 DOC. DATE: 87/04/30 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Pover Plant> Unit 1P Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HOWE'. Carolina Power 8c Light Co.
WATSON> R. A. Carol ina Poller 8( Light Co.
RECIP. NAME - RECIPIENT AFFILIATION SUB JECT: LER 87-018-00: on 870403> manual reactor trip initiated due to loss of both main feedeater pumps. Caused bg inadvertent short of test leads in process instrumentation cabi,net 0 incorrect setpoint. Undocumented leads removed. W/870430 ltr.
DISTRIBUTION CODE: IE22D COPIEB RECEIVED: LTR g TITLE: 50. 73 Licensee Event Report (LER) i Incident Rpti etc.
ENCL Q SIZE:
NOTES: Application for permit reneual filed. 05000400 RECIPIENT COPIES REC IP I ENT COP IEB ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 BUCKLEY B 1 1 INTERNAL: ACRS MICHELBON 1 1 ACRS MOELLER 1 AEOD/DOA 1 1 AFOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 NRR/DEST/*DE 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB NRR/DEST/ I CSB 1 1 NRR/DEST/MEB 1 NRR/DEST/MTB 1 1 NRR/DEBT/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SQB 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB 1 1 NRR/DREP/EPB ~
1 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 RB 1 NRR/PMAS/PTSB 1 1 REQ FILE 02 RES SPEIS T 1 1 FILE 01 1 EXTERNAL: EQhQ QROH, M 5 5 H BT LOBBY WARD 1 LPDR 1 1 NRC PDR 1 NSI C HARR IS> J 1 NSIC MAYSi Q 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTlR 41 ENCL 39
NRC Form 388 U.S, NUCLEAA REOULATORY COMMISSION (943) APPAOVED OMB NO. 3150010k EXPIAESI 8/31/88 LICENSEE EVENT REPORT (LER)
FACILITY NAME (I) DOCKET NUMBER (2) PACE 3 Shearon Harris Plant Unit 1 0 5 0 0 0 1 OF TITLE (8)
Reactor Trip Loss of Feedwater EVENT DATE (5) LFR NUMBER (5) REPORT DATE IT) OTHER FACILITIES INVOLVED (8)
MONTH DAY YEAR YEAR SSOVENTIAL re) REVISION MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(S)
NUMBER S.. I NVMSSR 0 5 0 0 0 04 03 8 7 7 0 1 8 0 0 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT 7 0 THE REOUIREMENTS OF 10 CFR (): ICneck one or more of the follorflnpl l11 OPERATINO MODE (8) 1 20A02(8) 20AOS(cl 50,73(e) (2) llr) 73,71(8)
POWER 20AOS(e) (1)(O SOM(c) (I) 50.73(e) (2)(r) 73.71(cl LEVEL 20AOS(el(1) (4) 50.38(c) (2) 50.73(el(2) (rill OTHER ISpeclfy In Abnrert l2)(vill)(B) INIow end ln Text, IVIIC Form 20AOS(e)(l)(IB) 50.73( ~ l(2) ll) 50.73(el(2) (rill)(A) 3SSAI 20AOB(e)l1)(lv) 50.73(el(2)(ll) 50.73(e)
Ci~k@&E' 20AOS(e) )1) lrl 50.73(e l(2)(ill) 50.73( ~ ) (2) (x I I.ICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE Andrew Howe Re ulator Cpm 1 919 362 27 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS AEPOAT (13)
CAUSE SYSTEM COMPONENT MANUFAC-TURER REPORTABLE TO NPRDS Hp'I CAUSE SYSTEM COMPONENT MANUFAC.
TURER EPORTABLE TO NPRDS
".' 'C:)
'x SUPPLEMENTAL REPORT EXPECTED (18) MONTH DAY YEAR EXPECTED SU 5 M I SS ION DATE I'IS)
YES Ilfyer, complete EXPECTED SUBSIISSION OATEI NO ABsTAAcT (Limit ro IcoO rpeceL l.e., epproxlmetely fifteen tlnple.tpece typewritten linn/ (15)
At 1126 on April 3, 1987, with the plant operating at 75K thermal power level and 560 MWe, a manual turbine trip and subsequent reactor trip was initiated. The trip was required due to a loss of both main feedwater pumps and the subsequent decrease in steam generator levels. The motor driven auxiliary feedwater pumps started automatically as required upon loss of both main feedwater pumps.
Subsequent to the trip the main steamline isolation valves were manually closed to limit the cooldown transient on the Reactor Coolant System (RCS).
The plant was stabilized in Mode 3 at the'zero-load RCS Tavg of 557 'F.
87050b027i 870430 PDR (E)DOCK 05000400 5 GRZ S l~
PDR NRC Form 388
NRC Fotm 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3)
LICENSEE EVENT REPORT {LER) TEXT CONTINUATION APPROVED OMB NO. 3150&104 EXPIRES: 8/3)/(8 FACILITY NAME (1) OOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
? 4 REVISION i%A SEQUENTIAL ':?A YEAR NUMBER NUMBER Shearon Harris Plant 0 5 0 0 0 018 0 0 02
'TEXT ///mFm 4/>>ce /4/Eqv/FF/ 1>>4 /I/EEV>>/ HRC F4mI 3884'4/ (17)
DESCRIPTION On April 3, 1987, the plant was operating at approximately 75X thermal power level and 560 MWe. Plant conditions were being maintained in steady state following a reactor startup on April 1 (Reference LER-87-017-0) to allow stabilization of Xenon in the core in preparation for further power ascension testing.
At approximately 1123, a low flow annunciator for condensate booster pump 1B alarmed, and at 1125 condensate booster pump 1B tripped, followed by main feedwater pump 1B. Automatic turbine runback to 50X power did not automatically occur as expected, and the operators manually reduced turbine load. At 1126, both heater drain pumps tripped, and before turbine load could be reduced significantly, the second main feedwater pump tripped. ,Both motor
-driven auxiliary feedwater pumps automatically started due to trip of both main feedwater pumps. Since feedwater could not be immediately restored, a manual trip was initiated. The manual turbine trip was initiated prior to a manual reactor trip, so the reactor trip occurred due to the turbine trip with reactor power above the P-7 interlock setpoint of 10X power.
Subsequent to the trip, the plant was stabilized in Mode 3 at the zero-load RCS Tavg of 557 'F with the main steamline isolation valves manually closed to limit the initial cooldown transient.
The cause of the trip was investigated and resolved, and the plant was returned to service on April 4, 1987.
CAUSE The initiating event was the trip of condensate booster pump 1B due to a low flow trip caused when test leads connected into the flow instrumentation card in the process instrumentation cabinet (PIC) were inadvertently shorted together. These test leads were being used to provide additional data for evaluating main feedwater and condensate pump trips (Refer'ence LERs 87-008-0, 87-013-0, 87-017-0). A decision had been made by plant management to connect a personal computer to various condensate and feedwater instrumentation points. During installation, it was determined that additional isolation resistors were necessary between the computer and the plant instrumentation loops. The leads were to be removed from the PIC for the installation of these resistors; however, for one lead, this was not done. As a result, when the resistors were being soldered into the circuit where the lead had not been removed, the circuit was grounded or shorted, causing a low flow annunciator and trip of the condensate booster pump. The PIC where the test leads were installed was physically separated from the area where the isolation resistors were being installed. The technician working on the isolation resistors could not view the connected test leads and in fact thought all test leads had been disconnected.
'NRC FORM 366A + U.S.GPO;1988.0.824 538/455 (943)
NRC Form 368A U.S. NUCLEAR REOULATORY COMMISSION (983)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO, 3150M(OS EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PACE (3)
YEAR gag SEQUENTIAL ~+: REVISION 4%m NUMBER NUMBER OF .
Shearon Harris Plant Unit 1 0 5 0 0 0 P 0 0 1 8 0 0 TEXT /// morB B/roce /B r/U/IBI/ Uw B//dOIN/ NRC Form 3////AB/ (I2)
CAUSE (continued)
The cause of the second main feedwater pump trip is attributed to low suction pressure due to high feedwater flow while operators were attempting to reduce the turbine load and adjust steam generator levels manually. The heater drain pump trips were likely caused by the transient created by the condensate booster pump trip.
The test leads had been connected and disconnected in an informal manner without appropriate documentation. As a result there was no inventory against which to check that all leads had been disconnected prior to starting work on the isolation resistors. Other test leads were connected to the PICs for approved and ongoing tests although not actively in use at the time.
.The failure of the turbine runback feature to reduce load to'50X upon trip of one main feedwater pump was due to an incorrect setpoint for a turbine first stage pressure permissive. The pressure setting specified by design was too high to allow the runback to function for this event.
CORRECTIVE ACTION Temporary leads which are not documented by an approved procedure were removed from the PICs, and the cabinets were inspected to verify this condition.
Additionally, test leads installed by approved procedures which were not in active use were also removed. Future installation of temporary monitoring equipment will only be in accordance with approved procedures, and such installations will include an independent verification, as appropriate.
Additionally, test leads will only be connected when required for test and removed after test completion.
NRC FORM 366A *U.S.GPO;1988 0.824 538/455 (94)3)
Carolina Power 8 Light Cornpant HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 APR 3 0 ]gg7 File Number'SHF/10-13510C Letter Number.'HO-870412 (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 87-018-00 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:bjb Enclosure cc. 'Dr. J. Nelson Grace (NRC RII)
Mr. B. Buckley (NRC)
Mr. G. Maxwell (NRC SHNPP)
MEM/HO-8704120/Page 1/OS1
