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{{#Wiki_filter:REGULAT INFORMATION DISTRIBUTIO YSTEM<RIDS)ACCESSION NBR FAC IL: 50-389 AUTH.NAME MEN DO Z A I V.N.WOODY'.O.RECIP.NAME 8710220113 DOC.DATE: 87/10/ib NOTARIZED:
{{#Wiki_filter:REGULAT     INFORMATION DISTRIBUTIO         YSTEM <RIDS)
NO St.Lucie Planti Unit 2i Florida Poeer h Light Co.AUTHOR AFF ILI AT ION Florida Power 5 Li ght Co.Florida Poeer 5 Light Co.RECIPIENT'AFFILIATION DOCKET&#xb9;05000389
ACCESSION NBR 8710220113           DOC. DATE: 87/10/ib     NOTARIZED: NO         DOCKET  &#xb9; FAC IL: 50-389    St. Lucie Planti Unit 2i Florida Poeer h Light           Co. 05000389 AUTH. NAME              AUTHOR AFF ILIAT ION MEN DO Z A I V. N.      Florida Power 5 Li ght Co.
WOODY'. O.              Florida Poeer 5 Light Co.
RECIP. NAME            RECIPIENT 'AFFILIATION


==SUBJECT:==
==SUBJECT:==
LER 87-00b-00:
LER 87-00b-00: on 870917'est of 2A 2B emergency'iesel Sc generator automatic load sequence relays incomplete. Caused bg personnel error. Personnel immed.iatelg perf ormed required surveillance test in accordance Uj/procedure. W/8710ib         ltr.
on 870917'est of 2A Sc 2B emergency'iesel generator automatic load sequence relays incomplete.
DISTRIBUTION CODE:         IESRD COPIES RECEIVED: LTR TITLE: 50. 73 Licensee Event Report <LER)i I  ENCL  g Incident Rpti etc.
Caused bg personnel error.Personnel immed.iatelg perf ormed required surveillance test in accordance Uj/procedure.
SIZE:
W/8710ib ltr.DISTRIBUTION CODE: IESRD COPIES RECEIVED: LTR I ENCL g SIZE: TITLE: 50.73 Licensee Event Report<LER)i Incident Rpti etc.NOTES: RECIPIENT ID CODE/NAME PD2-2 LA TOURIGNYi E INTERNAL: ACRS MI CHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS NRR/DEST/ELB NRR/DEST/MEB NRR/DEST/PSB NRR/DEST/SGB NRR/DLPG/GAB NRR/DREP/RAB SIB 02 RES TELFQRDI J RGN2 FILE 01 EXTERNAL: EGLG GRQHi M LPDR NSIC HARRISI J COPIES LTTR ENCL 1 1 1 1 1 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1 1 1*REC IP IENT ID CODE/NAME PD2-2 PD ACRS MOELLER AEQD/DSP/NAS AEOD/DSP/TPAB
NOTES:
.DEDRQ NRR/DEST/CEB NRR/DEBT/I CSB NRR/DEST/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RPB NRR/PMAS/ILRB RES DEPY GI RES/DE/EIB
RECIPIENT         COPIES
'ST LOBBY WARD NRC'PDR NSIC MAYS.G COP IES LTTR ENCL 1 1 2 2 1 1 1'1 1 1: 1 1 1 1 1 1 1 1 1 1 2 2" 1 1.1 1 1'1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 NRC Form 344 (403)LICENSEE EVENT REPORT (LER)V.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150010C EXPIRES,'i 3)i45 FACILITY NAME (I)ST.LUCIE UNIT 2 DOCKE'T NUMBER 12)PAGE I3i 0 389 1OF03''MISSED SURVEILLANCE ON THE 2A AND 2B EMERGENCY DIESEL GENERATOR AUTOMATIC LOAD SE UENCE RELAYS DUE TO A COGNITIVE PERSONNEL ERROR.EVENT DATE (5)LER NUMBER (4)REPORT DATE (7)OTHER FACILITIES INVOLVED (SI MONTH OAY YEAR YEAR ei>.;SEQUENTIAL y'-NUMSER SrT NUMSER MONTH DAY R 4 Vt)KIN YEAR FACILITY NAMES N/A DOCKET NVMBERISI 0 5 0 0 0 0 9 1 7 8 7 8 7 0 6 0010 1 6 8 7 0 5 0 0 0 OPERATINO MOOK (~I~OWER L'EY EL 1 0 20402(4)20A04(e)Ill(0 20 4444)Ii)I 4 I 20A04(~l(1)(SI)2040441(11(lvl 204044)ll I (v)20404(el 50.34 Icl I)I 50.34(cl(1)
* REC IP IENT        COP  IES ID CODE/NAME       LTTR ENCL        ID CODE/NAME      LTTR ENCL PD2-2 LA               1            PD2-2 PD                1      1 TOURIGNYi E           1    1 INTERNAL: ACRS MICHELSON              1    1      ACRS MOELLER            2      2 AEOD/DOA               1    1      AEQD/DSP/NAS            1      1 AEOD/DSP/ROAB          2    2      AEOD/DSP/TPAB    . 1' ARM/DCTS/DAB                       DEDRQ NRR/DEST/ADS NRR/DEST/ELB 1
X 50.73(el(2)(II 50.73(el(2)(4) 50.7 3(e l(2)((BI LICENSEE CONTACT FOR THIS LER (12)50.73(~l(2)(w I 50.73 (~I I 2 I(v)50.73(e)(2)(vnl 50,7 3 Ie)LT)4iil)(Al 50.7 3(~I (2)I v i)i~)I 4 I 50.73I~)(2IIxl THIS REPORT IS SUBMITTED PURSUANT T 0 THK REQUIREMENTS OF 10 CFR (I;fCnece one or more Of tne following/
1 1
(11 73.71(4)73.71(~I OTHER (Specify in apstisct OelOw entr in Tert, iVRC perm 3544I NAME V.N.Mendoza, Shift Technical Advisor TELEPHONE NUssBER AREA CODE 3 054 65-: 3550 COMPLETE ONE LINK FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM'COMPONENT NA NA NA MANUFAC.TVRER NA NA c:)Prrrst 2 wg SYSTKM COMPONENT MANUFAC.TVRER REPORTABLE TO NPRDS w'v SUPPLEMENTAL REPORT EXPECTED lle)YES fff yet, Cemptete tXptCTED SVSetfSSIOef OATtf NO ABSTRACT (Limit to tc00 tpeces.f.e..epprosimeNry Rfteen tingie.specs tvpewrNNn finest (14)EXPECTED SUBMISSION DATE (15I MONTN DAY YEAR N A At 1900 on September 17, 1987, it was determined that the 12 month test of the 2A and 2B Emergency Diesel Generator (EDG)automatic load sequence relays was incomplete.
1 0
A review of the surveillance procedure, performed on May 4, 1987, indicated that only the components on the 4160 volt 2A3 and 2B3 buses were tested and that the test did not include the components on the 4160 volt.2AB bus and the 480 volt load centers (LC).The root cause of the event was a cognitive personnel error by utility personnel implementing the maintenance surveillance procedure and the quality control personnel reviewing the plant work order and the maintenance surveillance procedure for completeness and compliance to the surveillance requirements.
1 NRR/DEST/CEB NRR/DEBT/ I CSB 1:
'For corrective actions, the electrical maintenance personnel immediately-performed the required surveillance test in accordance with the approved procedure.
1      1 1
Plant Management has re-emphasized the importance of adequate review of plant work orders and surveillance procedures.
1 NRR/DEST/MEB          1    1      NRR/DEST/MTB            1      1 NRR/DEST/PSB          1    1      NRR/DEST/RSB            1       1 NRR/DEST/SGB          1     1     NRR/DLPG/HFB            1       1 NRR/DLPG/GAB          1           NRR/DOEA/EAB NRR/DREP/RAB          1 1
In addition, the surveillance procedure was revised for clarity.8710@20113 8710~16389 PDR ADOCK 050$NRC Form 344 iS 43s NRt!Form 3EEA O.831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION U.S.NUCLEAR RECULATORY COMMISSION APPROUEO OMS NO.3(50-0(0<EXPIRES: 8/31/88 FACILITY NAME (I)ST.LUCIE UNIT 2 OOCKET NUMBER (2)YEAR LER NUMSER (8)N).SEQUENTIAL NUMBER REvrsroN NUMBER PACE (3)TEXT///more e/reoo ie required, uee eddr(r'orre/
1     NRR/DREP/RPB 1
HRC Forrrr 3SSA'e/l)2)0 5 0 0 0 3 898 7 006-0'2 OF 0 3 DESCRIPTION OP THE EVENT At approximately
2      2" 1
'1730 on September 17;1987, operations personnel.
SIB        1     1     NRR/PMAS/ ILRB          1       1.
were notified~that an FPL Quality Assurance audit had determined the twelve month test of the 2A and 2B emergency diesel generator (EDG)(EIISSEK)automatic load sequence relays performed on May 4, 1987 was incomplete.
02          1     RES DEPY GI
This procedure required that all components on the the 4160 V buses and the 480 V load centers (LC)be tested for proper load sequence relay timing.During the review, it was discovered that only the components on the 4160 volt 2A3 and 2B3 buses were tested.At 1900 on September 17, 1987, efforts were started" to perform the required surveillance tests to comply with the Technical Specification requirements.
                                                                '
By 0600 on September 18, 1987, all the components on the 2A EDG (Train"A")were satisfactorily tested and by 1453 on September 18, 1987, all of the 2A and, 2B EDG components were satisfactorily tested.All the relays tested were found to be within the tolerance requirements of the Technical Specifications.
1       1 RES TELFQRDI  J      1           RES/DE/EIB              1' RGN2    FILE    01          1 EXTERNAL: EGLG GRQHi      M          5    5        ST LOBBY WARD        1 LPDR                  1     1     NRC'PDR                1       1 NSIC HARRISI J        1     1     NSIC MAYS. G                    1 TOTAL NUMBER OF COPIES REQUIRED:          LTTR    45    ENCL    44
St.Lucie Unit 82 remained at Mode 1, 100%power, throughout this time period.r CAUSE OP THE EVENT The root cause of the event was a cognitive personnel error by utility maintenance and quality control personnel responsible for reviewing the plant work order (PWO)to ensure complete implementation and compliance with the requirements of the surveillance procedures.
 
The copy of the procedure used by the journeyman had handwritten directions on the'teps of, the.procedure.indicating where to start, and where to stop.'hese instructions only covered the 4160 volt 2A3 and 2B3 components.
NRC Form 344                                                                                                                                                  V.S. NUCLEAR REGULATORY COMMISSION (403)
Consequently,'160 volt 2AB bus and the 480 V LC portions of the procedure were never performed.
APPROVED OMB NO. 3150010C EXPIRES,' i 3) i45 LICENSEE EVENT REPORT (LER)
The review of.the PWO did not reveal this omission.ANALYSIS OP THE EVENT Technical Specifications 4.8.1.1.2.d requires that while operating in Modes 1,2,3,and 4 each diesel generator shall be demonstrated operable by verifying that at least once per 12 months the automatic load sequence timers are operable with the interval between each load block within plus/minus one second of its design interval.Since the St.Lucie Unit N2 was operating in Mode'1 when the event was discovered, this report is being submitted under 10 CFR 50.73(a)(2)(i)(B), any operation or condition prohibited by technical specificat'ions as defined in generic letter 87-09.The last'urveillance for the EDG.12-month test'f the automatic load sequence relays was satisfactorily performed in May 1986.This surveillance procedure was completed on September 18, 1987, approximately 18.5 days past the maximum allowable extension of 25%of the testing interval after the surveillance was'due and approximately 22 hours after the discovery of the condition.
FACILITY NAME (I)                                                                                                                                    DOCKE'T NUMBER 12)                            PAGE  I3i 389 1OF03
All components tested satisfactorily, thus the health and safety of the general public were not affected by this event.NRC FORM 3BBA (94)3)
        ''ST.MISSED  LUCIE UNIT 2                                                                                                                                     0 SURVEILLANCE ON                  THE 2A AND 2B EMERGENCY DIESEL GENERATOR AUTOMATIC LOAD SE UENCE RELAYS DUE TO A COGNITIVE PERSONNEL ERROR.
NRC Foehn 3ddA (94)3 I LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.3)9)W)04 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER l3)YEAR LER NUMBER (8)SEOVENTIAL NVMSSA K'I KIO AEV/SION NVMSSA PAGE (3I ST.LUCIE UNIT 2 TEXT III///o/o sPsco is/odw'red,//so sddio'o/MIHRC
EVENT DATE (5)                        LER NUMBER (4)                           REPORT DATE (7)                               OTHER FACILITIES INVOLVED (SI MONTH                              YEAR    ei>.; SEQUENTIAL        R 4 Vt)KIN MONTH        DAY        YEAR              FACILITY NAMES                            DOCKET NVMBERISI OAY      YEAR              y'     -
%%d////3dSA'4/
NUMSER      SrT NUMSER N/A                                    0    5    0      0    0 0      9 1 7            8 7 8          7        0Ill(0      6        0010                  1      6 8 7                                   i)i 0    5    0      0    0 THIS REPORT IS SUBMITTED PURSUANT T 0 THK REQUIREMENTS OF 10 CFR (I; fCnece one or more Of tne following/ (11 OPERATINO MOOK    (~ I 20402(4)                                 20404(el                                50.73( ~ l(2)(wI                                    73.71(4)
(17)o s o o o 38 987 006 0 0 3 OF 03 CORRECTIVE ACTIONS 1.After Operations personnel were notified of the missed surveillance condition, the required surveillance was immediately performed and was deemed satisfactory.
    ~ OWER L'EY EL 20A04(e)                                 50.34 Icl I)I                            50.73 ( ~ II 2 I( v)                                73.71( ~ I 1 0                20 4444) Ii) I 4 I                       50.34(cl(1)                               50.73(e) (2)(vnl                                  OTHER (Specify in apstisct OelOw entr  in Tert, iVRC perm 20A04( ~ l(1)(SI)                  X     50.73(el(2)(II                           50,7 3 Ie) LT)4iil)(Al                            3544I 2040441(11(lvl                            50.73(el(2)(4)                            50.7 3( ~ I (2) Iv    ) I4 I 204044)    llI (v)                       50.7 3(e l(2)((BI                        50.73I ~ )(2IIxl LICENSEE CONTACT FOR THIS LER (12)
2.Plant Management has re-emphasized to plant personnel the importance of completing all technical specification surveillances in a timely manner as required.3.The plant Txaining Department will evaluate this item to determine appropriate training requirements and methods..4.The personnel responsible for preparation and review of the above PWO have*been counselled on the importance of attention to detail in ensuring Technical Specification surveillance requirements are met.5.The surveillance procedure was revised for clarity.ADDITIONAL INFORMATION Failed component information:
NAME                                                                                                                                                                  TELEPHONE NUssBER AREA CODE V. N. Mendoza,                     Shift Technical Advisor                                                                                     3   054 65-: 3550 COMPLETE ONE LINK FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
No component or system failures occured during this event.Previous.similar event: The most recent similar event on Unit II2 was a missed surveillance submi.tted under LER$389-86-014.
MANUFAC.                                                                                                  MANUFAC.        REPORTABLE CAUSE     SYSTEM       'COMPONENT                                                                               SYSTKM    COMPONENT                      TVRER TVRER                                                                                                                   TO NPRDS c:)Prrrst 2 wg w'v NA          NA            NA                  NA                NA SUPPLEMENTAL REPORT EXPECTED             lle)                                                                               MONTN        DAY      YEAR EXPECTED SUBMISSION DATE (15I YES fff yet, Cemptete tXptCTED SVSetfSSIOef OATtf                                     NO                                                                               N A ABSTRACT (Limit to tc00 tpeces. f.e.. epprosimeNry Rfteen tingie.specs tvpewrNNn finest (14)
At 1900 on September 17, 1987,                                                   it       was determined that the 12 month test of the 2A and                       2B     Emergency             Diesel               Generator       (EDG) automatic load sequence relays was incomplete.                                   A     review               of     the   surveillance                         procedure, performed on May 4, 1987,                             indicated           that           only         the   components                     on     the 4160 volt 2A3 and 2B3 buses were                             tested         and       that           the     test   did       not           include           the components on the           4160     volt         . 2AB   bus       and     the       480         volt   load   centers                     (LC).
The         root cause                   of the event was a cognitive personnel error                                                                       by     utility personnel             implementing the maintenance surveillance procedure and                                                                             the quality control personnel reviewing the plant work order and the                                                                                                   maintenance surveillance procedure for completeness and compliance to the                                                                                             surveillance requirements.
              'For corrective actions, the electrical maintenance personnel immediately
              -performed the required surveillance test in accordance with the approved procedure.                   Plant Management has re-emphasized the importance of adequate review of plant work orders and surveillance procedures.                                                                                       In addition, the surveillance procedure was revised for clarity.
8710@20113 8710~16389         050 PDR           ADOCK
          $
NRC Form 344 iS 43s
 
U.S. NUCLEAR RECULATORY COMMISSION NRt! Form 3EEA O.831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION                                                                   APPROUEO OMS NO. 3(50-0(0<
EXPIRES: 8/31/88 FACILITY NAME     (I)                                                               OOCKET NUMBER (2)                       LER NUMSER (8)                                   PACE (3)
YEAR  N). SEQUENTIAL                   REvrsroN NUMBER                       NUMBER ST. LUCIE UNIT 2 0  5    0  0  0  3    898      7        006 0'                                    2 OF      0 3 TEXT /// more e/reoo ie required, uee eddr(r'orre/ HRC Forrrr 3SSA'e/ l)2)
DESCRIPTION OP THE EVENT At approximately '1730                                   on   September         17; 1987, operations personnel. were notified that an FPL Quality
                                      ~                                          Assurance         audit had determined the twelve month test of the 2A and 2B emergency                                       diesel       generator (EDG) (EIISSEK) automatic load sequence relays performed on May 4,                                           1987     was incomplete.         This procedure required that all components on                                       the     the   4160   V   buses     and   the                   480 V load centers (LC) be tested for proper                                           load     sequence       relay     timing.                       During the review,             it       was discovered that only                         the   components       on     the   4160 efforts volt 2A3 were and 2B3 buses were tested.                                       At   1900       on   September     17,     1987, started to perform the required
                                    "
surveillance          tests     to     comply                     with         the Technical Specification                                   requirements.           By   0600   on   September       18,                   1987,         all the components on the 2A EDG (Train "A") were satisfactorily tested and by 1453 on September 18, 1987, all of the 2A and, 2B EDG components were satisfactorily tested. All the relays tested were found to be within the tolerance                 requirements                   of the     Technical Specifications.                     St.                   Lucie Unit 82 remained                   at   Mode 1,             100% power,   throughout         this   time   period.
r CAUSE OP THE EVENT The root cause of the event was a cognitive personnel error by utility maintenance and quality control personnel responsible                                                           for reviewing the plant work order (PWO) to ensure complete implementation and compliance with the requirements of the surveillance procedures.                                                             The copy of the procedure used by the journeyman had handwritten directions on the'teps of, the .procedure .indicating where to start, and where to stop.'hese instructions only covered the 4160 volt 2A3 and 2B3 components.                                                         Consequently,'160 volt 2AB bus and the 480 V LC portions of the procedure were never performed. The review of. the PWO did not reveal this omission.
ANALYSIS OP THE EVENT Technical Specifications 4.8.1.1.2.d requires that while operating in Modes 1,2,3,and 4 each diesel generator shall be demonstrated operable by verifying that at least once per 12 months the automatic load sequence timers are operable with the interval between each load block within plus/minus one second of its design interval. Since the St. Lucie Unit N2 was operating in Mode'1 when the event was discovered, this report is being submitted under 10 CFR 50.73(a)
(2)(i)(B), any operation or condition prohibited by technical specificat'ions as defined in generic letter 87-09. The last'urveillance for the EDG .12-month test'f the automatic load sequence relays was satisfactorily performed in May 1986.                 This surveillance procedure was completed on September 18, 1987, approximately 18.5 days past the maximum allowable extension of 25% of the testing interval after the surveillance was'due and approximately 22 hours after the discovery of the condition. All components tested satisfactorily, thus the health and safety of the general public were not affected by this event.
NRC FORM 3BBA (94)3)
 
NRC Foehn 3ddA                                                                                                             U.S. NUCLEAR REGULATORY COMMISSION (94)3 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                                     APPROVEO OMB NO. 3)9)W)04 EXPIRES: 8/31/88 FACILITY NAME (I)                                                                 DOCKET NUMBER l3)             LER NUMBER (8)                   PAGE (3I SEOVENTIAL   K
                                                                                                                                    'I AEV/SION YEAR      NVMSSA    KIO    NVMSSA ST. LUCIE UNIT 2 o  s  o  o    o 38 987            006              0        0 3 OF      03 TEXT III///o/o sPsco is /odw'red, //so sddio'o/MIHRC %%d////3dSA'4/ (17)
CORRECTIVE ACTIONS
: 1.       After Operations personnel                         were   notified of the missed surveillance condition, the required surveillance                         was immediately performed and was deemed satisfactory.
: 2.       Plant Management has re-emphasized to plant personnel the importance of completing all technical specification surveillances in a timely manner as required.
: 3.       The       plant Txaining Department                     will evaluate this     item to determine appropriate training requirements                         and methods..
                                                                                                                                                      *
: 4.       The       personnel responsible for preparation and review of the above PWO have been         counselled on the importance of attention to detail in ensuring Technical Specification surveillance requirements are met.
: 5.      The      surveillance procedure                    was  revised for    clarity.
ADDITIONAL INFORMATION Failed component information:
No component                  or system failures occured during this event.
Previous .similar event:
The most recent similar event on Unit                                 II2 was a missed   surveillance submi.tted under LER $ 389-86-014.
N/IC FORM SddA (94)3)
N/IC FORM SddA (94)3)
P.OX 14000, JUNO BEAC<., k.C;.gQ<0~pe.iOBcR i (, 1~8(L<7 OI7-IO CFR 50.73 U.S.Nuclear Regulatory Commission A t tn: Doc umen t Contr o I Desk Washington, D.C.20555 Gen t I emen: Re: St.Lucie Unit 2 Docket No.50-389 Reportable Event: 87-06 Date of Event: September l7, l 987 Missed Surveillance on Emergency Diesel Generator Auto Load Se uence Rela s The attached Licensee Event Report is being submitted pursuant to the requirments of IO CFR 50.73.a.to provide notification on the subject event.Very truly yours, iI'p,i;o,E~
 
C.0.Wo'ody Group Vice President Nuclear Energy COW/GRM/gp Attachment cc: J.Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St.Lucie Plant GRM I/030/I an FPL Group company}}
P. OX 14000, JUNO BEAC<., k .
C;
                  .gQ
                              <0
                      .
            ~pe                                                           iOBcR   i (, 1~8(
L<7 OI7-IO CFR 50.73 U.S. Nuclear Regulatory Commission A t tn: Doc umen t Contr o I Desk Washington, D. C. 20555 Gen t I emen:
Re:     St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 87-06 Date of Event: September l7, l 987 Missed Surveillance on Emergency Diesel Generator Auto Load Se uence Rela s The   attached Licensee Event Report is being submitted pursuant to the requirments of IO CFR 50.73.a. to provide notification on the subject event.
Very truly yours, iI'p,i;o,E~
C. 0. Wo'ody Group Vice President Nuclear Energy COW/GRM/gp Attachment cc:   J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRM I /030/I                                                                   an FPL Group company}}

Revision as of 23:17, 29 October 2019

LER 87-006-00:on 870917,discovered That Test of Emergency Diesel Generator Automatic Load Sequence Relays Incomplete. Caused by Personnel Error.Personnel Immediately Performed Required Surveillance Test Per procedure.W/871016 Ltr
ML17221A444
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 10/16/1987
From: Mendoza V, Woody C
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-87-417, LER-87-006-03, LER-87-6-3, NUDOCS 8710220113
Download: ML17221A444 (5)
v • d • e


Text

REGULAT INFORMATION DISTRIBUTIO YSTEM <RIDS)

ACCESSION NBR 8710220113 DOC. DATE: 87/10/ib NOTARIZED: NO DOCKET ¹ FAC IL: 50-389 St. Lucie Planti Unit 2i Florida Poeer h Light Co. 05000389 AUTH. NAME AUTHOR AFF ILIAT ION MEN DO Z A I V. N. Florida Power 5 Li ght Co.

WOODY'. O. Florida Poeer 5 Light Co.

RECIP. NAME RECIPIENT 'AFFILIATION

SUBJECT:

LER 87-00b-00: on 870917'est of 2A 2B emergency'iesel Sc generator automatic load sequence relays incomplete. Caused bg personnel error. Personnel immed.iatelg perf ormed required surveillance test in accordance Uj/procedure. W/8710ib ltr.

DISTRIBUTION CODE: IESRD COPIES RECEIVED: LTR TITLE: 50. 73 Licensee Event Report <LER)i I ENCL g Incident Rpti etc.

SIZE:

NOTES:

RECIPIENT COPIES

  • REC IP IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 PD2-2 PD 1 1 TOURIGNYi E 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEQD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB . 1' ARM/DCTS/DAB DEDRQ NRR/DEST/ADS NRR/DEST/ELB 1

1 1

1 0

1 NRR/DEST/CEB NRR/DEBT/ I CSB 1:

1 1 1

1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/RAB 1 1

1 NRR/DREP/RPB 1

2 2" 1

SIB 1 1 NRR/PMAS/ ILRB 1 1.

02 1 RES DEPY GI

'

1 1 RES TELFQRDI J 1 RES/DE/EIB 1' RGN2 FILE 01 1 EXTERNAL: EGLG GRQHi M 5 5 ST LOBBY WARD 1 LPDR 1 1 NRC'PDR 1 1 NSIC HARRISI J 1 1 NSIC MAYS. G 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

NRC Form 344 V.S. NUCLEAR REGULATORY COMMISSION (403)

APPROVED OMB NO. 3150010C EXPIRES,' i 3) i45 LICENSEE EVENT REPORT (LER)

FACILITY NAME (I) DOCKE'T NUMBER 12) PAGE I3i 389 1OF03

ST.MISSED LUCIE UNIT 2 0 SURVEILLANCE ON THE 2A AND 2B EMERGENCY DIESEL GENERATOR AUTOMATIC LOAD SE UENCE RELAYS DUE TO A COGNITIVE PERSONNEL ERROR.

EVENT DATE (5) LER NUMBER (4) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH YEAR ei>.; SEQUENTIAL R 4 Vt)KIN MONTH DAY YEAR FACILITY NAMES DOCKET NVMBERISI OAY YEAR y' -

NUMSER SrT NUMSER N/A 0 5 0 0 0 0 9 1 7 8 7 8 7 0Ill(0 6 0010 1 6 8 7 i)i 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THK REQUIREMENTS OF 10 CFR (I; fCnece one or more Of tne following/ (11 OPERATINO MOOK (~ I 20402(4) 20404(el 50.73( ~ l(2)(wI 73.71(4)

~ OWER L'EY EL 20A04(e) 50.34 Icl I)I 50.73 ( ~ II 2 I( v) 73.71( ~ I 1 0 20 4444) Ii) I 4 I 50.34(cl(1) 50.73(e) (2)(vnl OTHER (Specify in apstisct OelOw entr in Tert, iVRC perm 20A04( ~ l(1)(SI) X 50.73(el(2)(II 50,7 3 Ie) LT)4iil)(Al 3544I 2040441(11(lvl 50.73(el(2)(4) 50.7 3( ~ I (2) Iv ) I4 I 204044) llI (v) 50.7 3(e l(2)((BI 50.73I ~ )(2IIxl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUssBER AREA CODE V. N. Mendoza, Shift Technical Advisor 3 054 65-: 3550 COMPLETE ONE LINK FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC. MANUFAC. REPORTABLE CAUSE SYSTEM 'COMPONENT SYSTKM COMPONENT TVRER TVRER TO NPRDS c:)Prrrst 2 wg w'v NA NA NA NA NA SUPPLEMENTAL REPORT EXPECTED lle) MONTN DAY YEAR EXPECTED SUBMISSION DATE (15I YES fff yet, Cemptete tXptCTED SVSetfSSIOef OATtf NO N A ABSTRACT (Limit to tc00 tpeces. f.e.. epprosimeNry Rfteen tingie.specs tvpewrNNn finest (14)

At 1900 on September 17, 1987, it was determined that the 12 month test of the 2A and 2B Emergency Diesel Generator (EDG) automatic load sequence relays was incomplete. A review of the surveillance procedure, performed on May 4, 1987, indicated that only the components on the 4160 volt 2A3 and 2B3 buses were tested and that the test did not include the components on the 4160 volt . 2AB bus and the 480 volt load centers (LC).

The root cause of the event was a cognitive personnel error by utility personnel implementing the maintenance surveillance procedure and the quality control personnel reviewing the plant work order and the maintenance surveillance procedure for completeness and compliance to the surveillance requirements.

'For corrective actions, the electrical maintenance personnel immediately

-performed the required surveillance test in accordance with the approved procedure. Plant Management has re-emphasized the importance of adequate review of plant work orders and surveillance procedures. In addition, the surveillance procedure was revised for clarity.

8710@20113 8710~16389 050 PDR ADOCK

$

NRC Form 344 iS 43s

U.S. NUCLEAR RECULATORY COMMISSION NRt! Form 3EEA O.831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROUEO OMS NO. 3(50-0(0<

EXPIRES: 8/31/88 FACILITY NAME (I) OOCKET NUMBER (2) LER NUMSER (8) PACE (3)

YEAR N). SEQUENTIAL REvrsroN NUMBER NUMBER ST. LUCIE UNIT 2 0 5 0 0 0 3 898 7 006 0' 2 OF 0 3 TEXT /// more e/reoo ie required, uee eddr(r'orre/ HRC Forrrr 3SSA'e/ l)2)

DESCRIPTION OP THE EVENT At approximately '1730 on September 17; 1987, operations personnel. were notified that an FPL Quality

~ Assurance audit had determined the twelve month test of the 2A and 2B emergency diesel generator (EDG) (EIISSEK) automatic load sequence relays performed on May 4, 1987 was incomplete. This procedure required that all components on the the 4160 V buses and the 480 V load centers (LC) be tested for proper load sequence relay timing. During the review, it was discovered that only the components on the 4160 efforts volt 2A3 were and 2B3 buses were tested. At 1900 on September 17, 1987, started to perform the required

"

surveillance tests to comply with the Technical Specification requirements. By 0600 on September 18, 1987, all the components on the 2A EDG (Train "A") were satisfactorily tested and by 1453 on September 18, 1987, all of the 2A and, 2B EDG components were satisfactorily tested. All the relays tested were found to be within the tolerance requirements of the Technical Specifications. St. Lucie Unit 82 remained at Mode 1, 100% power, throughout this time period.

r CAUSE OP THE EVENT The root cause of the event was a cognitive personnel error by utility maintenance and quality control personnel responsible for reviewing the plant work order (PWO) to ensure complete implementation and compliance with the requirements of the surveillance procedures. The copy of the procedure used by the journeyman had handwritten directions on the'teps of, the .procedure .indicating where to start, and where to stop.'hese instructions only covered the 4160 volt 2A3 and 2B3 components. Consequently,'160 volt 2AB bus and the 480 V LC portions of the procedure were never performed. The review of. the PWO did not reveal this omission.

ANALYSIS OP THE EVENT Technical Specifications 4.8.1.1.2.d requires that while operating in Modes 1,2,3,and 4 each diesel generator shall be demonstrated operable by verifying that at least once per 12 months the automatic load sequence timers are operable with the interval between each load block within plus/minus one second of its design interval. Since the St. Lucie Unit N2 was operating in Mode'1 when the event was discovered, this report is being submitted under 10 CFR 50.73(a)

(2)(i)(B), any operation or condition prohibited by technical specificat'ions as defined in generic letter 87-09. The last'urveillance for the EDG .12-month test'f the automatic load sequence relays was satisfactorily performed in May 1986. This surveillance procedure was completed on September 18, 1987, approximately 18.5 days past the maximum allowable extension of 25% of the testing interval after the surveillance was'due and approximately 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> after the discovery of the condition. All components tested satisfactorily, thus the health and safety of the general public were not affected by this event.

NRC FORM 3BBA (94)3)

NRC Foehn 3ddA U.S. NUCLEAR REGULATORY COMMISSION (94)3 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3)9)W)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER l3) LER NUMBER (8) PAGE (3I SEOVENTIAL K

'I AEV/SION YEAR NVMSSA KIO NVMSSA ST. LUCIE UNIT 2 o s o o o 38 987 006 0 0 3 OF 03 TEXT III///o/o sPsco is /odw'red, //so sddio'o/MIHRC %%d////3dSA'4/ (17)

CORRECTIVE ACTIONS

1. After Operations personnel were notified of the missed surveillance condition, the required surveillance was immediately performed and was deemed satisfactory.
2. Plant Management has re-emphasized to plant personnel the importance of completing all technical specification surveillances in a timely manner as required.
3. The plant Txaining Department will evaluate this item to determine appropriate training requirements and methods..
4. The personnel responsible for preparation and review of the above PWO have been counselled on the importance of attention to detail in ensuring Technical Specification surveillance requirements are met.
5. The surveillance procedure was revised for clarity.

ADDITIONAL INFORMATION Failed component information:

No component or system failures occured during this event.

Previous .similar event:

The most recent similar event on Unit II2 was a missed surveillance submi.tted under LER $ 389-86-014.

N/IC FORM SddA (94)3)

P. OX 14000, JUNO BEAC<., k .

C;

.gQ

<0

.

~pe iOBcR i (, 1~8(

L<7 OI7-IO CFR 50.73 U.S. Nuclear Regulatory Commission A t tn: Doc umen t Contr o I Desk Washington, D. C. 20555 Gen t I emen:

Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 87-06 Date of Event: September l7, l 987 Missed Surveillance on Emergency Diesel Generator Auto Load Se uence Rela s The attached Licensee Event Report is being submitted pursuant to the requirments of IO CFR 50.73.a. to provide notification on the subject event.

Very truly yours, iI'p,i;o,E~

C. 0. Wo'ody Group Vice President Nuclear Energy COW/GRM/gp Attachment cc: J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRM I /030/I an FPL Group company

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