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| {{#Wiki_filter:REQUL RY INFORNATION DISTR IBUTI'YBTEN (R IDB)I ACCESSION NBR: 8705180101 DOC.DATE: 87/05/12 NOTARIZED: | | {{#Wiki_filter:REQUL RY INFORNATION DISTR IBUTI 'YBTEN (R IDB) |
| NO FACIL: 50-400 Sheav on Harv is Nucleav Pouer Plant>Unit 1>Carolina AUTH.MANE AUTHOR AFFILIATION HUDSON>O.N.Cav olina Power 5 Ligh+Co.WATSON>R.A.Cav olina Power 5 Ligh+Co.RECIP.NANE" RECIPIENT AFFILIATION DOCKET¹05000400 05000400 | | I ACCESSION NBR: 8705180101 DOC. DATE: 87/05/12 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Sheav on Harv is Nucleav Pouer Plant> Unit 1> Carolina 05000400 AUTH. MANE AUTHOR AFFILIATION HUDSON> O. N. Cav olina Power 5 Ligh+ Co. |
| | WATSON> R. A. Cav olina Power 5 Ligh+ Co. |
| | RECIP. NANE " |
| | RECIPIENT AFFILIATION |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER 87-021-00: | | LER 87-021-00: on 870414> circulating water sos flow to main condensev' estv icted v'esul ting in high condensate temps> +v'ip of both feedwatev'v ains 5 manual "tv ip of tuv'bine 5 v'eac+ov'. |
| on 870414>circulating water sos flow to main condensev' estv icted v'esul ting in high condensate temps>+v'ip of both feedwatev'v ains 5 manual"tv ip of tuv'bine 5 v'eac+ov'. | | Caused bg debris on pump sue+ion screens. W/870512 I tv'. |
| Caused bg debris on pump sue+ion screens.W/870512 I tv'.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR g ENCL>SIZE: TITLE: 50.73 Licensee Event Report (LER)>Incident Rpt>etc.NOTES: Application for pev mit v enewal f iled.REC IP I ENT ID CODE/NAI'IE PD2-1 LA BUCKLEY B INTERNAL: ACRS NICHELSON AEOD/DOA AEOD/DBP/TPAB NRR/DEBT/ADE NRR/DEST/CEB NRR/DEBT/ICSB NRR/DEBT/NTB NRR/DEBT/RBB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RAB N/ILRB REG FILE 02 RQN2 FILE 01 EXTERNAL: EQhQ GROH N LPDR NBIC HARRIS>J COP I EB LTTR EI'CL 1 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1 1 RECIPIENT ID CODE/NAI'IE PD2-1 PD*CRB NOELLER AEOD/DSP/ROAB DEDRO NRR/DEST/ADS MRR/DEST/ELB NRR/DEBT/NEB NRR/DEST/PSB MRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/EPB NRR/DREP/RPB NRR/PMAS/PTSB RES SPEIS>T H ST LOBBY WARD NRC PDR NSIC NAYS>G CO~IES LT TR El'C L 1 2 2 2 2 1 1 1 0 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 TOTAL NUNBER OF COPIES REQUIRED: LTl R 43 ENCL 41 NRC Form 355 194)3)LICENSEE EVENT REPORT (LER)UA.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.31504(04 EXPIRES: 5/31/SS FACILITY NAME (I)Shearon Harris, Unit 1 DOCKET NUMBER (2)PAGE 3 0 s 0 o o40 OioF04 TITLE (4)Reactor Trip-Loss of Feedwater; Cooling Tower Fill Material in Condenser EVENT DATE (5)LER NUMBER (6)SEQUENTIAL Rm NVMSER?7:I MONTH DAY YEAR YEAR?@j REPORT DATE (7)YEAR MONTH DAY NUMBER DOCKET NUMBER(S)0 5 0 0 o FACILITY NAMES OTHER FACILITIES INVOLVED (5)04 14 878 7 0 2 1 051 2 8 7 0 5 0 0 0 OPERATING MODE (0)POWER LEVEL uo)8 7 jpj$:<" N"'5" 20.402(b)20AOS(e)(1)(I)20.405 (e)(I)(4)20AOS(s)(I)(ill)20AOS(s)(I)(lr)20.405(~)(I)(v)20.405(c)SOM(c)(1)S0.35(c)(2)50.73(e)(2)(I)50.73(e)(2)(II)50.7 3(s)(2)(III)LICENSEE CONTACT FOR THIS LER (12)50.73(s)(2)llv)50.73(e)(2)(v)50.73(e)(2)(rll)50.73(e)(2)(rill)(A)50.73(e)(2)(vill)(5)50.73(e)(2)(s)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF R (II ICheck one or more of tne fotforffnff (11)73.7101)73.71(c)OTHER ISpeclfy in Abstrsct below end In Text, NIIC Form BBBA I NAME 0.N.Hudson 0 la o AREA CODE TELEPHONE NUMBER COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANVFAC.TVRER 4!%B~WN CAUSE SYSTEM COMPONENT MANU FAG TURER''"@coal v'PORTABLE TO NPRDS".K~!SUPPLEMENTAL REPORT EXPECTED (14)YEs Iff ym, complete ExpfcTED$(IBEtlsslDN DATEI ABsTRAcT ILlmlt to fcoo speces, I e., epproxlmetefy fifteen slnpreepsce typewr/rten ffnNI (15)EXPECTED SUBMISSION DATE US)MONTH DAY YEAR On April 14, 1987, the Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 87X reactor power.Around 1800, during the process of cleaning the circulating water pump suction screens, debris from the cooling tower basin entered the circulating water system and restricted flow to the main condenser. | | DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR g ENCL > SIZE: |
| Condensate temperatures rose rapidly and led to a trip of both condensate pumps due to high condensate temperature.
| | TITLE: 50. 73 Licensee Event Report (LER) Incident Rpt> etc. |
| This resulted in the loss of both feedwater trains and, consequently, a manual trip of the turbine and reactor at 1830 on April 14.Following plant shutdown, all visible debris was removed from accessible areas.The plant was returned to service at approximately 1500 on April 15, 1987.8705180101 870512 PDR ADOCK 05000000 8 PDR NRC Form 355 194)3)
| | > |
| NRC Form 366A (983)LICENSE EVENT REPORT (LER)TEXT CONTIN ATION UrL NUCLEAR REGULATOAY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)@%i SEOUENTIAI.
| | NOTES: Application for pev mit v enewal f iled. 05000400 REC IP I ENT COP I EB RECIPIENT CO~IES ID CODE/NAI'IE LTTR EI'CL ID CODE/NAI'IE LT TR El'C L PD2-1 LA 1 PD2-1 PD 1 BUCKLEY B 1 1 INTERNAL: ACRS NICHELSON 1 1 *CRB NOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/ROAB 2 2 AEOD/DBP/TPAB 1 1 DEDRO 1 1 NRR/DEBT/ADE 1 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 MRR/DEST/ELB 1 NRR/DEBT/ICSB 1 NRR/DEBT/NEB 1 1 NRR/DEBT/NTB 1 NRR/DEST/PSB 1 NRR/DEBT/RBB 1 MRR/DEST/SGB NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/EPB 1 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 N /ILRB 1 NRR/PMAS/PTSB 1 1 REG FILE 02 1 1 RES SPEIS> T 1 1 RQN2 FILE 01 1 EXTERNAL: EQhQ GROH N 5 5 H ST LOBBY WARD 1 LPDR 1 1 NRC PDR 1 1 NBIC HARRIS> J 1 NSIC NAYS> G 1 1 TOTAL NUNBER OF COPIES REQUIRED: LTl R 43 ENCL 41 |
| re: NUMSER i~oN REV/S/ON T~>rd NUMSER PAGE (3)TEXT/cameo<<>>co/4/r//roo/t, rrro//I/or>>/HRC Arm 35549/(IT)0 5 0 0 0 OF DESCRIPTION OF EVENT On April 14, 1987, the Shearon Harris Nuclear Mode 1 at approximately 87X power.All three operation.
| | |
| Circulating water pump'A'ad an differential pressure, and a Work Request was clean the pump screens.Power Plant was operating in circulating water pumps were in elevated suction screen issued at 1520 on April 14 to The circulating water pumps have stationary vertical screens to keep debris from the cooling tower basin out of the pump intakes.Two suction screen positions (inner and outer)are available at each pump bay.The inservice screen is typically installed in the outer location (farthest from the pump).However, in this case, the screens were installed in the inner location.At approximately 1800 on April 14, work was in progress to clean the suction screens.The screens must be removed for cleaning.The affected pump was not shut down when the screen was removed because full circulating water flow was required.A spare screen had been installed in the outer position serving the southern bay of pump'A'o start the cleaning process.As the debris-laden inner screen was removed for cleaning, most of the trapped debris fell into the bay.The small trough attached to the bottom of the screen did not accommodate the large amount of material present.The fallen debris was immediately drawn into circulating water pump'A'nd was pumped to the condenser.
| | NRC Form 355 UA. NUCLEAR REGULATORY COMMISSION 194)3) |
| At approximately 1825, condensate pump high temperature alarms were received in the Main Control Room.The operators then observed a condensate temperature rise from about 127 to 130'F within one minute.Condensate pump'B'ubsequently tripped due to high condensate temperature at approximately 1829.This caused a loss of the'B'eedwater train and initiated an automatic turbine runback and control rod insertion.
| | APPROVED OMB NO. 31504(04 EXPIRES: 5/31/SS LICENSEE EVENT REPORT (LER) |
| Condensate pump'A'ripped due to high condensate temperature approximately 10 to 15 seconds later.This caused a loss of the'A'eedwater train and a loss of main feedwater flow.The reactor and turbine were manually tripped at 1830 due to the loss of both feedwater trains.A normal recovery from the trip ensued.Auxiliary feedwater automatically started and was used to maintain steam generator levels until a feed system could be restored.Following the plant shutdown, a debris removal effort was initiated.
| | FACILITY NAME (I) DOCKET NUMBER (2) PAGE 3 Shearon Harris, Unit 1 0 s 0 o o40 OioF04 TITLE (4) |
| The condenser waterbox was entered for inspection and cleaning.The amount of debris removed was sufficient to cause significant flow reduction.
| | Reactor Trip Loss of Feedwater; Cooling Tower Fill Material in Condenser EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (5) |
| Concurrently, the circulating water pump suction screens were removed, cleaned, and reinstalled in the outer screen locations.
| | MONTH SEQUENTIAL Rm DAY YEAR FACILITYNAMES DOCKET NUMBER(S) |
| Approximately 100 cu.ft.of debris was removed from the condenser.
| | DAY YEAR YEAR ?@j NVMSER ?7:I NUMBER MONTH 0 5 0 0 o 04 14 878 7 0 2 1 051 2 8 7 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF R (II ICheck one or more of tne fotforffnff (11) |
| The circulating water system was then restarted to flush material to the waterbox.The waterbox was then recleaned to remove as much residual debris as possible.Visible debris was removed from accessible areas of the cooling tower basin.NRC FORM 366A$4)3)*U,S.GPO:1988%
| | MODE (0) 20.402(b) 20.405(c) 50.73(s) (2) llv) 73.7101) |
| 824 538/455 NRC Form 366A (94LT)LICENS EVENT REPORT (LER)TEXT CONTIN ATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3(50&104 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (21 YEAR LER NUMBER (6)j"=8<SEQUENTIAL N NUMBER/&i'EVISION
| | SOM(c) (1) 73.71(c) |
| '.4C NUMBER PAGE (3)Shearon Harris Unit 1 TEXT/SmrFF EPoco lr t)rl/rkFIL IIFF/I/o/oo/NRC Fonrr 38543/117) o s o o o 40 87-0 2 1-0 0 03 OFO 4 DESCRIPTION OF EVENT (continued)
| | '5 POWER 20AOS(e)(1) (I) 50.73(e) (2) (v) |
| In addition, selected heat exchangers in the normal service water system were inspected for debris.No debris was found in the air compressor
| | LEVEL uo) 20.405 (e) (I ) (4) S0.35(c) (2) 50.73(e) (2) (rll) OTHER ISpeclfy in Abstrsct 8 "7 below end In Text, NIIC Form |
| 'B'ntercooler, and about two handfuls of debris was removed from the Waste Processing Building nonessential services chilled water system chiller (WC-3)heat exchanger.
| | :<" N" 20AOS(s) (I ) (ill) 50.73(e) (2) (rill)(A) BBBAI jpj$ 50.73(e ) (2) (I) 20AOS(s ) (I ) (lr) 50.73(e) (2) (II) 50.73(e) (2) (vill)(5) 20.405( ~ ) (I ) (v) 50.7 3(s) (2) (III) 50.73(e) (2) (s) |
| The plant was returned to service at approximately 1500 on April 15, 1987.CAUSE An inspection of the cooling tower indicated that the debris was primarily plastic fill material used in the tower to facilitate cooling water distribution. | | LICENSEE CONTACT FOR THIS LER (12) |
| The fill material is a corrugated plastic sheet.(See attached sketch.)The returning circulating water is distributed to the spray nozzles and spray headers by means of concrete flumes.Seals connecting various parts of the flumes had failed and the leaking water was impinging directly on the plastic fill material.This caused the fill material to break up and fall into the cooling tower basin.This debris had collected on the circulating water pump suction screens.In addition, the inservice screens were in the wrong location (inner position), the Work Request for cleaning the screens did not specify sequential instructions for cleaning the screens, and screen cleaning procedures were not available. | | NAME TELEPHONE NUMBER AREA CODE |
| The large amount of material on the screens was below the water line and could not be seen until the screens were lifted.When the screens were lifted for cleaning, the debris fell into the bay and since there was no backup screen, the material was sucked into the running pump.An engineering evaluation of the cooling tower fill material damage was conducted.
| | : 0. N. Hudson 0 la o COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| The evaluation indicated that the damage to the cooling tower is approaching its limit, and significant additional fill damage is not expected.Tower performance is expected to be degraded;and a performance monitoring program for the cooling tower will quantify the available capacity of the tower.The normal service water (NSW)system also takes suction from the cooling tower.However, the pumps use a separate intake from the cooling tower basin.The NSW pumps'ischarge is also equipped with a self-cleaning strainer.The NSW supplies water to the Turbine Building, Waste Processing Building, and is the normal supply to the emergency service water system.As stated above, small amounts of debris were found in components serviced by NSW.As a result, a program will be developed to monitor heat exchangers serviced by NSW and ESW.NRC FORM SESA (94)3)4 U.B.GPO.1986 D624 538/455 NRC Form 366A (94)3)LICENS EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/68 FACILITY NAME I'l DOCKET NUMBER (2)LER NUMBER (6)yEAR gg SEQUENT/AL g@REVISION i@NUMBER':: NUMSErr PAGE 13)Shearon Harris Unit 1 TEXT/Hmao 4Poco JI/99rr)a/, INo/I/orro/HRC Form 3/F/AS)(17)o s o o o 4 8 7 2 1 0 OF 0 4 ANALYSIS This event is being reported in accordance with lOCFR50.73(a)(2)(iv) due to manual actuation of the Reactor Protection System.There were no safety consequences as a result of this event.All systems functioned as required, and the plant was shut down safely.CORRECTIVE ACTIONS In summary, the following corrective actions were taken or are planned.1.Visible debris was removed from accessible areas.2.The circulating water pump suction screens were placed in the outer screen locations.
| | ''" @coal v COMPONENT MANVFAC. SYSTEM COMPONENT MANUFAG 'PORTABLE CAUSE SYSTEM TVRER CAUSE TURER TO NPRDS 4!% ".K~! |
| 3.Circulating water pump suction screen cleaning procedures have been developed and implemented.
| | B~WN SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE US) |
| 4.The cooling tower was subsequently repaired in a May outage.5.A program has been developed and implemented to monitor the performance of critical plant heat exchangers that are serviced by normal service water either via NSW or ESW.O/RC FORM 366A (94)3)*U.S.GPO:1986.0 624 538/455 WARt1 AIR OUTLET WARi1 AIR ttt t DRIFT ELININATOR SPRAY N022LE.D HOT WATER PVC FILL o o a oo o oo o o o'o'o COOL AIR INLET 365 F T.DIAMETER~COOLED WATER FALLS TO BASIN BELOW COOL AIR NATURAL DRAFT COOL I NG TOWER 0 C~I Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O.Box 165 New Hill, NC 27562 NAY 32 1987 File Number.SHF/10-13510C Letter Number'HO-870425 (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 87-021"00 Gentlemen.'n accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted.
| | YEs Iffym, complete ExpfcTED $ (IBEtlsslDN DATEI ABsTRAcT ILlmlt to fcoo speces, I e., epproxlmetefy fifteen slnpreepsce typewr/rten ffnNI (15) |
| 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.'Dr.J.Nelson Grace (NRC-RII)Mr.B.Buckley (NRR)Mr.G.Maxwell (NRC-SHNPP)MEM/HO-8704250/PAGE 1/OS1}}
| | On April 14, 1987, the Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 87X reactor power. Around 1800, during the process of cleaning the circulating water pump suction screens, debris from the cooling tower basin entered the circulating water system and restricted flow to the main condenser. Condensate temperatures rose rapidly and led to a trip of both condensate pumps due to high condensate temperature. This resulted in the loss of both feedwater trains and, consequently, a manual trip of the turbine and reactor at 1830 on April 14. Following plant shutdown, all visible debris was removed from accessible areas. The plant was returned to service at approximately 1500 on April 15, 1987. |
| | 8705180101 870512 PDR ADOCK 05000000 8 PDR NRC Form 355 194)3) |
| | |
| | UrL NUCLEAR REGULATOAY COMMISSION NRC Form 366A (983) |
| | LICENSE EVENT REPORT (LER) TEXT CONTIN ATION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | YEAR @%i SEOUENTIAI. i~oN REV/S/ON re: NUMSER T~>rd NUMSER |
| | /cameo 0 5 0 0 0 OF TEXT <<>>co /4 /r//roo/t, rrro //I/or>>/HRC Arm 35549/ (IT) |
| | DESCRIPTION OF EVENT On April 14, 1987, the Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 87X power. All three circulating water pumps were in operation. Circulating water pump 'A'ad an elevated suction screen differential pressure, and a Work Request was issued at 1520 on April 14 to clean the pump screens. |
| | The circulating water pumps have stationary vertical screens to keep debris from the cooling tower basin out of the pump intakes. Two suction screen positions (inner and outer) are available at each pump bay. The inservice screen is typically installed in the outer location (farthest from the pump). However, in this case, the screens were installed in the inner location. At approximately 1800 on April 14, work was in progress to clean the suction screens. The screens must be removed for cleaning. The affected pump was not shut down when the screen was removed because full circulating water flow was required. A spare screen had been installed in the outer position serving the southern bay of pump 'A'o start the cleaning process. |
| | As the debris-laden inner screen was removed for cleaning, most of the trapped debris fell into the bay. The small trough attached to the bottom of the screen did not accommodate the large amount of material present. The fallen debris was immediately drawn into circulating water pump 'A'nd was pumped to the condenser. |
| | At approximately 1825, condensate pump high temperature alarms were received in the Main Control Room. The operators then observed a condensate temperature rise from about 127 to 130'F within one minute. Condensate pump |
| | 'B'ubsequently tripped due to high condensate temperature at approximately 1829. This caused a loss of the 'B'eedwater train and initiated an automatic turbine runback and control rod insertion. Condensate pump due to high condensate temperature approximately 10 to 15 seconds |
| | 'A'ripped later. This caused a loss of the 'A'eedwater train and a loss of main feedwater flow. The reactor and turbine were manually tripped at 1830 due to the loss of both feedwater trains. A normal recovery from the trip ensued. |
| | Auxiliary feedwater automatically started and was used to maintain steam generator levels until a feed system could be restored. |
| | Following the plant shutdown, a debris removal effort was initiated. The condenser waterbox was entered for inspection and cleaning. The amount of debris removed was sufficient to cause significant flow reduction. |
| | Concurrently, the circulating water pump suction screens were removed, cleaned, and reinstalled in the outer screen locations. Approximately 100 cu. |
| | ft. of debris was removed from the condenser. The circulating water system waterbox was then was then restarted to flush material to the waterbox. The recleaned to remove as much residual debris as possible. Visible debris was removed from accessible areas of the cooling tower basin. |
| | NRC FORM 366A |
| | *U,S.GPO:1988% 824 538/455 |
| | $ 4)3) |
| | |
| | NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (94LT) |
| | LICENS EVENT REPORT (LER) TEXT CONTIN ATION APPROVED OMB NO. 3(50&104 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (21 LER NUMBER (6) PAGE (3) |
| | YEAR N j"=8< SEQUENTIAL /&i'EVISION NUMBER '.4C NUMBER Shearon Harris Unit 1 o s o o o 40 87 0 2 1 0 0 03 OFO 4 TEXT /SmrFF EPoco lr t)rl/rkFIL IIFF /I/o/oo/NRC Fonrr 38543/117) |
| | DESCRIPTION OF EVENT (continued) |
| | In addition, selected heat exchangers in the normal service water system were inspected for debris. No debris was found in the air compressor and about two handfuls of debris was removed from the Waste 'B'ntercooler, Processing Building nonessential services chilled water system chiller (WC-3) heat exchanger. |
| | The plant was returned to service at approximately 1500 on April 15, 1987. |
| | CAUSE An inspection of the cooling tower indicated that the debris was primarily plastic fill material used in the tower to facilitate cooling water distribution. The fill material is a corrugated plastic sheet. (See attached sketch.) The returning circulating water is distributed to the spray nozzles and spray headers by means of concrete flumes. Seals connecting various parts of the flumes had failed and the leaking water was impinging directly on the plastic fill material. This caused the fill into the cooling tower basin. This debris had collected on the circulating material to break up and fall water pump suction screens. |
| | In addition, the inservice screens were in the wrong location (inner position), the Work Request for cleaning the screens did not specify sequential instructions for cleaning the screens, and screen cleaning procedures were not available. The large amount of material on the screens was below the water line and could not be seen until the screens were lifted. When the screens were lifted for cleaning, the debris fell into the bay and since there was no backup screen, the material was sucked into the running pump. |
| | An engineering evaluation of the cooling tower conducted. The evaluation indicated that the damage to the cooling tower is fill material damage was approaching its limit, and significant additional expected. Tower performance is expected to be degraded; and a performance fill damage is not monitoring program for the cooling tower will quantify the available capacity of the tower. |
| | The normal service water (NSW) system also takes suction from the cooling tower. However, the pumps use a separate intake from the cooling tower basin. The NSW pumps'ischarge is also equipped with a self-cleaning strainer. The NSW supplies water to the Turbine Building, Waste Processing Building, and is the normal supply to the emergency service water system. As stated above, small amounts of debris were found in components serviced by NSW. As a result, a program will be developed to monitor heat exchangers serviced by NSW and ESW. |
| | NRC FORM SESA 4 U.B.GPO.1986 D624 538/455 (94)3) |
| | |
| | NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3) |
| | LICENS EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/68 FACILITYNAME I'l DOCKET NUMBER (2) LER NUMBER (6) PAGE 13) yEAR gg i@ SEQUENT/AL NUMBER ':: |
| | g@ REVISION NUMSErr Shearon Harris Unit 1 o s o o o 4 8 7 2 1 0 OF 0 4 TEXT /Hmao 4Poco JI /99rr)a/, INo /I/orro/HRC Form 3/F/AS) (17) |
| | ANALYSIS This event is being reported in accordance with lOCFR50.73(a)(2)(iv) due to manual actuation of the Reactor Protection System. |
| | There were no safety consequences as a result of this event. All systems functioned as required, and the plant was shut down safely. |
| | CORRECTIVE ACTIONS In summary, the following corrective actions were taken or are planned. |
| | : 1. Visible debris was removed from accessible areas. |
| | : 2. The circulating water pump suction screens were placed in the outer screen locations. |
| | : 3. Circulating water pump suction screen cleaning procedures have been developed and implemented. |
| | : 4. The cooling tower was subsequently repaired in a May outage. |
| | : 5. A program has been developed and implemented to monitor the performance of critical plant heat exchangers that are serviced by normal service water either via NSW or ESW. |
| | O/RC FORM 366A *U.S.GPO:1986.0 624 538/455 (94)3) |
| | |
| | WARt1 AIR WARi1 AIR OUTLET ttt t DRIFT ELININATOR SPRAY N022LE |
| | .D HOT WATER PVC FILL o o a oo oo o o o |
| | o ' o'o |
| | ~ COOLED WATER COOL AIR COOL AIR FALLS TO BASIN BELOW INLET 365 F T. DIAMETER NATURAL DRAFT COOL I NG TOWER |
| | |
| | 0 C~I Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 NAY 32 1987 File Number. SHF/10-13510C Letter Number'HO-870425 (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 87-021"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. 'Dr. J. Nelson Grace (NRC RII) |
| | Mr. B. Buckley (NRR) |
| | Mr. G. Maxwell (NRC SHNPP) |
| | MEM/HO-8704250/PAGE 1/OS1}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
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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
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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
[Table view] |
Text
REQUL RY INFORNATION DISTR IBUTI 'YBTEN (R IDB)
I ACCESSION NBR: 8705180101 DOC. DATE: 87/05/12 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Sheav on Harv is Nucleav Pouer Plant> Unit 1> Carolina 05000400 AUTH. MANE AUTHOR AFFILIATION HUDSON> O. N. Cav olina Power 5 Ligh+ Co.
WATSON> R. A. Cav olina Power 5 Ligh+ Co.
RECIP. NANE "
RECIPIENT AFFILIATION
SUBJECT:
LER 87-021-00: on 870414> circulating water sos flow to main condensev' estv icted v'esul ting in high condensate temps> +v'ip of both feedwatev'v ains 5 manual "tv ip of tuv'bine 5 v'eac+ov'.
Caused bg debris on pump sue+ion screens. W/870512 I tv'.
DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR g ENCL > SIZE:
TITLE: 50. 73 Licensee Event Report (LER) Incident Rpt> etc.
>
NOTES: Application for pev mit v enewal f iled. 05000400 REC IP I ENT COP I EB RECIPIENT CO~IES ID CODE/NAI'IE LTTR EI'CL ID CODE/NAI'IE LT TR El'C L PD2-1 LA 1 PD2-1 PD 1 BUCKLEY B 1 1 INTERNAL: ACRS NICHELSON 1 1 *CRB NOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/ROAB 2 2 AEOD/DBP/TPAB 1 1 DEDRO 1 1 NRR/DEBT/ADE 1 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 MRR/DEST/ELB 1 NRR/DEBT/ICSB 1 NRR/DEBT/NEB 1 1 NRR/DEBT/NTB 1 NRR/DEST/PSB 1 NRR/DEBT/RBB 1 MRR/DEST/SGB NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/EPB 1 1 NRR/DREP/RAB 1 NRR/DREP/RPB 2 2 N /ILRB 1 NRR/PMAS/PTSB 1 1 REG FILE 02 1 1 RES SPEIS> T 1 1 RQN2 FILE 01 1 EXTERNAL: EQhQ GROH N 5 5 H ST LOBBY WARD 1 LPDR 1 1 NRC PDR 1 1 NBIC HARRIS> J 1 NSIC NAYS> G 1 1 TOTAL NUNBER OF COPIES REQUIRED: LTl R 43 ENCL 41
NRC Form 355 UA. NUCLEAR REGULATORY COMMISSION 194)3)
APPROVED OMB NO. 31504(04 EXPIRES: 5/31/SS LICENSEE EVENT REPORT (LER)
FACILITY NAME (I) DOCKET NUMBER (2) PAGE 3 Shearon Harris, Unit 1 0 s 0 o o40 OioF04 TITLE (4)
Reactor Trip Loss of Feedwater; Cooling Tower Fill Material in Condenser EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (5)
MONTH SEQUENTIAL Rm DAY YEAR FACILITYNAMES DOCKET NUMBER(S)
DAY YEAR YEAR ?@j NVMSER ?7:I NUMBER MONTH 0 5 0 0 o 04 14 878 7 0 2 1 051 2 8 7 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF R (II ICheck one or more of tne fotforffnff (11)
MODE (0) 20.402(b) 20.405(c) 50.73(s) (2) llv) 73.7101)
SOM(c) (1) 73.71(c)
'5 POWER 20AOS(e)(1) (I) 50.73(e) (2) (v)
LEVEL uo) 20.405 (e) (I ) (4) S0.35(c) (2) 50.73(e) (2) (rll) OTHER ISpeclfy in Abstrsct 8 "7 below end In Text, NIIC Form
- <" N" 20AOS(s) (I ) (ill) 50.73(e) (2) (rill)(A) BBBAI jpj$ 50.73(e ) (2) (I) 20AOS(s ) (I ) (lr) 50.73(e) (2) (II) 50.73(e) (2) (vill)(5) 20.405( ~ ) (I ) (v) 50.7 3(s) (2) (III) 50.73(e) (2) (s)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER AREA CODE
- 0. N. Hudson 0 la o COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
" @coal v COMPONENT MANVFAC. SYSTEM COMPONENT MANUFAG 'PORTABLE CAUSE SYSTEM TVRER CAUSE TURER TO NPRDS 4!% ".K~!
B~WN SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE US)
YEs Iffym, complete ExpfcTED $ (IBEtlsslDN DATEI ABsTRAcT ILlmlt to fcoo speces, I e., epproxlmetefy fifteen slnpreepsce typewr/rten ffnNI (15)
On April 14, 1987, the Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 87X reactor power. Around 1800, during the process of cleaning the circulating water pump suction screens, debris from the cooling tower basin entered the circulating water system and restricted flow to the main condenser. Condensate temperatures rose rapidly and led to a trip of both condensate pumps due to high condensate temperature. This resulted in the loss of both feedwater trains and, consequently, a manual trip of the turbine and reactor at 1830 on April 14. Following plant shutdown, all visible debris was removed from accessible areas. The plant was returned to service at approximately 1500 on April 15, 1987.
8705180101 870512 PDR ADOCK 05000000 8 PDR NRC Form 355 194)3)
UrL NUCLEAR REGULATOAY COMMISSION NRC Form 366A (983)
LICENSE EVENT REPORT (LER) TEXT CONTIN ATION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR @%i SEOUENTIAI. i~oN REV/S/ON re: NUMSER T~>rd NUMSER
/cameo 0 5 0 0 0 OF TEXT <<>>co /4 /r//roo/t, rrro //I/or>>/HRC Arm 35549/ (IT)
DESCRIPTION OF EVENT On April 14, 1987, the Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 87X power. All three circulating water pumps were in operation. Circulating water pump 'A'ad an elevated suction screen differential pressure, and a Work Request was issued at 1520 on April 14 to clean the pump screens.
The circulating water pumps have stationary vertical screens to keep debris from the cooling tower basin out of the pump intakes. Two suction screen positions (inner and outer) are available at each pump bay. The inservice screen is typically installed in the outer location (farthest from the pump). However, in this case, the screens were installed in the inner location. At approximately 1800 on April 14, work was in progress to clean the suction screens. The screens must be removed for cleaning. The affected pump was not shut down when the screen was removed because full circulating water flow was required. A spare screen had been installed in the outer position serving the southern bay of pump 'A'o start the cleaning process.
As the debris-laden inner screen was removed for cleaning, most of the trapped debris fell into the bay. The small trough attached to the bottom of the screen did not accommodate the large amount of material present. The fallen debris was immediately drawn into circulating water pump 'A'nd was pumped to the condenser.
At approximately 1825, condensate pump high temperature alarms were received in the Main Control Room. The operators then observed a condensate temperature rise from about 127 to 130'F within one minute. Condensate pump
'B'ubsequently tripped due to high condensate temperature at approximately 1829. This caused a loss of the 'B'eedwater train and initiated an automatic turbine runback and control rod insertion. Condensate pump due to high condensate temperature approximately 10 to 15 seconds
'A'ripped later. This caused a loss of the 'A'eedwater train and a loss of main feedwater flow. The reactor and turbine were manually tripped at 1830 due to the loss of both feedwater trains. A normal recovery from the trip ensued.
Auxiliary feedwater automatically started and was used to maintain steam generator levels until a feed system could be restored.
Following the plant shutdown, a debris removal effort was initiated. The condenser waterbox was entered for inspection and cleaning. The amount of debris removed was sufficient to cause significant flow reduction.
Concurrently, the circulating water pump suction screens were removed, cleaned, and reinstalled in the outer screen locations. Approximately 100 cu.
ft. of debris was removed from the condenser. The circulating water system waterbox was then was then restarted to flush material to the waterbox. The recleaned to remove as much residual debris as possible. Visible debris was removed from accessible areas of the cooling tower basin.
NRC FORM 366A
- U,S.GPO:1988% 824 538/455
$ 4)3)
NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (94LT)
LICENS EVENT REPORT (LER) TEXT CONTIN ATION APPROVED OMB NO. 3(50&104 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (21 LER NUMBER (6) PAGE (3)
YEAR N j"=8< SEQUENTIAL /&i'EVISION NUMBER '.4C NUMBER Shearon Harris Unit 1 o s o o o 40 87 0 2 1 0 0 03 OFO 4 TEXT /SmrFF EPoco lr t)rl/rkFIL IIFF /I/o/oo/NRC Fonrr 38543/117)
DESCRIPTION OF EVENT (continued)
In addition, selected heat exchangers in the normal service water system were inspected for debris. No debris was found in the air compressor and about two handfuls of debris was removed from the Waste 'B'ntercooler, Processing Building nonessential services chilled water system chiller (WC-3) heat exchanger.
The plant was returned to service at approximately 1500 on April 15, 1987.
CAUSE An inspection of the cooling tower indicated that the debris was primarily plastic fill material used in the tower to facilitate cooling water distribution. The fill material is a corrugated plastic sheet. (See attached sketch.) The returning circulating water is distributed to the spray nozzles and spray headers by means of concrete flumes. Seals connecting various parts of the flumes had failed and the leaking water was impinging directly on the plastic fill material. This caused the fill into the cooling tower basin. This debris had collected on the circulating material to break up and fall water pump suction screens.
In addition, the inservice screens were in the wrong location (inner position), the Work Request for cleaning the screens did not specify sequential instructions for cleaning the screens, and screen cleaning procedures were not available. The large amount of material on the screens was below the water line and could not be seen until the screens were lifted. When the screens were lifted for cleaning, the debris fell into the bay and since there was no backup screen, the material was sucked into the running pump.
An engineering evaluation of the cooling tower conducted. The evaluation indicated that the damage to the cooling tower is fill material damage was approaching its limit, and significant additional expected. Tower performance is expected to be degraded; and a performance fill damage is not monitoring program for the cooling tower will quantify the available capacity of the tower.
The normal service water (NSW) system also takes suction from the cooling tower. However, the pumps use a separate intake from the cooling tower basin. The NSW pumps'ischarge is also equipped with a self-cleaning strainer. The NSW supplies water to the Turbine Building, Waste Processing Building, and is the normal supply to the emergency service water system. As stated above, small amounts of debris were found in components serviced by NSW. As a result, a program will be developed to monitor heat exchangers serviced by NSW and ESW.
NRC FORM SESA 4 U.B.GPO.1986 D624 538/455 (94)3)
NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3)
LICENS EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/68 FACILITYNAME I'l DOCKET NUMBER (2) LER NUMBER (6) PAGE 13) yEAR gg i@ SEQUENT/AL NUMBER '::
g@ REVISION NUMSErr Shearon Harris Unit 1 o s o o o 4 8 7 2 1 0 OF 0 4 TEXT /Hmao 4Poco JI /99rr)a/, INo /I/orro/HRC Form 3/F/AS) (17)
ANALYSIS This event is being reported in accordance with lOCFR50.73(a)(2)(iv) due to manual actuation of the Reactor Protection System.
There were no safety consequences as a result of this event. All systems functioned as required, and the plant was shut down safely.
CORRECTIVE ACTIONS In summary, the following corrective actions were taken or are planned.
- 1. Visible debris was removed from accessible areas.
- 2. The circulating water pump suction screens were placed in the outer screen locations.
- 3. Circulating water pump suction screen cleaning procedures have been developed and implemented.
- 4. The cooling tower was subsequently repaired in a May outage.
- 5. A program has been developed and implemented to monitor the performance of critical plant heat exchangers that are serviced by normal service water either via NSW or ESW.
O/RC FORM 366A *U.S.GPO:1986.0 624 538/455 (94)3)
WARt1 AIR WARi1 AIR OUTLET ttt t DRIFT ELININATOR SPRAY N022LE
.D HOT WATER PVC FILL o o a oo oo o o o
o ' o'o
~ COOLED WATER COOL AIR COOL AIR FALLS TO BASIN BELOW INLET 365 F T. DIAMETER NATURAL DRAFT COOL I NG TOWER
0 C~I Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 NAY 32 1987 File Number. SHF/10-13510C Letter Number'HO-870425 (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 87-021"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. 'Dr. J. Nelson Grace (NRC RII)
Mr. B. Buckley (NRR)
Mr. G. Maxwell (NRC SHNPP)
MEM/HO-8704250/PAGE 1/OS1
