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{{#Wiki_filter:REQULAT INFORMATION DISTRIBUTION
{{#Wiki_filter:REQULAT       INFORMATION DISTRIBUTION           ~TEM (RIDS)
~TEM (RIDS)ACCESSION NBR: 8705120244 DOC.DATE: 87/05/06 NOTARIZED:
ACCESSION NBR: 8705120244           DOC. DATE: 87/05/06     NOTARIZED: NO             DOCKET ¹ FACIL: STN-50-528 Palo Verde Nuclear Station> Uni t               1> Ari zona Pub li 05000528 AUTH. NAME             AUTHOR AFFILIATION BRADISH> T. R.         Arizona Nuclear'o!.'er Prospect       ( formerlM Ari zona Public Serv HAYNES> J. Q.         AT izona Nuclear Pouer Prospect     (formerly Ari zona Public Serv REC IP. NAME           RECIPIENT AFFILIATION BUB JECT:   LER 87-013-00: on 870408> Limiting Condition for Operation
NO DOCKET¹FACIL: STN-50-528 Palo Verde Nuclear Station>Uni t 1>Ari zona Pub li 05000528 AUTH.NAME AUTHOR AFFILIATION BRADISH>T.R.Arizona Nuclear'o!.'er Prospect (formerlM Ari zona Public Serv HAYNES>J.Q.AT izona Nuclear Pouer Prospect (formerly Ari zona Public Serv REC IP.NAME RECIPIENT AFFILIATION BUB JECT: LER 87-013-00:
            . 3 0 3   entered due to inoperability of ESF pump room air exhaust sos. Caused bM cognitive personnel error Memo sen+ to~
on 870408>Limiting Condition for Operation.3 0 3 entered due to inoperability of ESF pump room air exhaust sos.Caused bM cognitive personnel error~Memo sen+to onsite managers reminding of responsibilities.
onsite managers reminding of responsibilities. W/870506 I+r.
W/870506 I+r.DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR l ENCL l SIZE: TITLE: 50.73 Licensee Event Report (LER)>Incident Rpt>etc.NOTES: Standardi zed plant.M.Davis>NRR: iCg.05000528 RECIPIENT ID CODE/NAME PD5 LA LICITRA E INTERNAL: ACRS MI CHELBON AEOD/DOA AEOD/DSP/TPAB NRR/DEBT/ADE NRR/DEST/CEB NRR/DEST/ICBB NRR/DEBT/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RAB NR A LRB EQ FIL 02 QN FILE 01 EXTERNAL: EQ8cG QROH>M LPDR NBIC HARRIS>J NOTES: COPIES LTTR ENCL 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 5 1 1 1 1 REC IP I ENT ID CODE/NAME PD5 PD DAVIS>M*CRS MOELLER AEOD/DSP/ROAB DEQRO NRR/DEST/ADS NRR/DEST/ELB NRR/DEBT/MEB NRR/DEST/PSB h!RR/DEST/SGB NRR/DLPG/GAB NRR/DREP/EPB NRR/DREP/RPB h!RR/PMAS/PTSB RES SPEIS>T H ST LOBBY WARD NRC PDR NBIC MAYS>G COP IEB LTTR Er,'CL 1 1 1 1 1 1 2 2 1 1 1 0 1 1.1 1 1 1 1 1 1 1 1 2'1 1 1 1 1 1 1 1 TOTAL, NUMBER OF COPIES REQUIRED: LT1R 44 ENCL 42 I
DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR l ENCL l                     SIZE:
NAC Form Sdd (D.BS)LICENSEE EVENT REPORT (LER)VS.NUCLEAR REOULATOAY COMMISSION APPAOVED OMB NO.2)500)04 EXPIAES:~/21/DS FACILITY NAME (I)Palo Verde Unit 1 TITLE lcl DOCKET NUMBER (2)0 5 0 0 052 PA 2 or-0 3 REPORT DATE (7)LER NUMBER (5)EVEN'1 DATE ISI OTHEA FACILITIES INVOLVED (5)DOCKET NUMBER(5)0 5 0 0 0 FAC/LITY NAMES REVS'ONTH NUMBER SEQUENT/AL NUMDDtl oy DAY YEAR YEAR"os(: DAY YEAR MONTH N A Entry Into Technical Specification LCO 3.0.3 Due to Personnel Error 0 4 088 787 013 00 05 06 7 N A 0 5 0 0 0 OPERATINO MODE (DI POWER LEYEL 1 0 0 50.72(cl(2)(lrl 50,72(~)(2)(rl 50,72(~)12)(rS)50 72(402)(rill)(Al 50.72(c)(2l(rill)IS)50.72(cl(2)(cl 20.405(c)20,402(dl 20.405(~)(1)(l)20.405(~)(I)IQ)20.405(~I()l(iill 20,4N(c)(I)I lv I 20.405(~l(1)(v)50.25Ic)(II 50.2dlc)(2) 50.72(cl(2I(l) 50.72(c)(2)
TITLE: 50. 73 Licensee Event Report (LER)> Incident Rpt> etc.
IDI 50.7 2 Ic I (2 I (ill)LICENSEE CONTACT FOA THIS LER 112I THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR ()t IChcch onc or morc of thc folforrind/(Ill 72.71(III 72.71(c)OTHER/Specify/n AO/rrcct hclow cnt/ln ycct, HIIC form d//SAI NAME T.R.Bradish, Compliance Supervisor (Ext.6936)TELEPHONE NUMBER AREA CODE 602 932-5 300 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOR'7 (12)CAUSE SYSTEM COMPONENT MANUFAC.TVRER EPORTABLE TO NPRDS:";rgb'P()rtg,'c VLE sYsTE COMPONENT MANUFAC.TVRER Ay'j,acr Yn 4 y>>y-'O NPRDS'r.A(tj)S 1!kP~'j%i5i SUPPLEMENTAL REPOR'T EXPECTED 114)YES Ilf ycr, comp/crt E/IPECTED St/dc//SSIOH DATE/ABSTRACT ILrmlt to f400 cpcccr.I.c..cpprocimctcry fiftccn rind/c g>>cc rypcrrrlt>>n
NOTES: Standardi   zed   plant. M. Davis> NRR: iCg.                                   05000528 RECIPIENT           COPIES            REC IP I ENT          COP IEB ID CODE/NAME          LTTR ENCL        ID CODE/NAME           LTTR Er,'CL PD5 LA                         1      PD5 PD                      1    1 LICITRA   E                     1      DAVIS> M                    1    1 INTERNAL: ACRS MICHELBON              1    1      *CRS MOELLER                1    1 AEOD/DOA                               AEOD/DSP/ROAB              2    2 AEOD/DSP/TPAB                         DEQRO                      1    1 NRR/DEBT/ADE             1    0      NRR/DEST/ADS                1    0 NRR/DEST/CEB              1    1      NRR/DEST/ELB                1    1.
/mod lid)HO iox IW+k:.>>>CNioo MONTH OAY YEAR EXPECTED SUBMISSION DATE (15)At approximately 1351 MST on April 8, 1987, Palo Verde Unit 1 was in Mode 1 (POt)tER OPERATION) at 100 percent power when Technical Specification (T.S.)Limiting Condition for Operation (LCO)3.0.3 was en'tered due to the inoperability of the Engineered Safety Features (ESF)pump room air exhaust systems.T.S.LCO 3.0.3 was exited at approximately 1541 on April 8, 1987 following the successful completion of Surveillance Test 73ST-9HF01 (Fuel Building AFU Airflow Capacity and Pressurization Test).This event was discovered by a System Engineer (utility non-licensed) during a review of 73ST-9HFOl for future revisions.
NRR/DEST/ICBB            1    1      NRR/DEBT/MEB                1   1 NRR/DEBT/MTB                          NRR/DEST/PSB                1 NRR/DEST/RSB                          h!RR/DEST/SGB               1    1 NRR/DLPG/HFB              1    1      NRR/DLPG/GAB               1    1 NRR/DOEA/EAB              1    1      NRR/DREP/EPB               1
The root cause of this event was a cognitive personnel error by a system engineer (contractor non-licensed) in that he did not properly complete the"Surveillance Test Package Review Sheet".The responsible system engineer is no longer employed by Arizona Nuclear Power Project.As corrective action, a memo has been sent to onsite Managers to remind them it is the responsibility of each performance group to track their own Conditional ST's and any portion of a scheduled ST that could'ot be performed in its entirety to ensure their status is maintained current.No similar events have been reported where improper documentation of*a partial surveillance test has resulted in exceeding a surveillance requirement.
                                                                                  '
8705120244 87050b PDR ADOCK 05000528 8 PDR HRC corm Sdd
1 NRR/DREP/RAB              1    1      NRR/DREP/RPB               2 NR    A    LRB          1    1      h!RR/PMAS/PTSB                   1 EQ  FIL          02            1      RES SPEIS> T               1    1 QN    FILE      01      1    1 EXTERNAL: EQ8cG QROH> M                5    5      H ST LOBBY WARD             1   1 LPDR                      1     1     NRC PDR                    1 NBIC HARRIS>    J        1     1     NBIC MAYS> G                1   1 NOTES:
TOTAL, NUMBER OF COPIES REQUIRED:         LT1R   44   ENCL       42


NRC Fosw 355A 1903 I e LICENSEE EVENT REPORT ILERI TEXT CONTINUATION U 3 NUCLEAR REOULATORY COMMISSION APPROVED OMS NO 3150 0104 EXPIRES: S/31/SS FACILITY NAME ITI DOCKET NUMSER l21 LER NUMSER I~I YEAR'~i.5EOUENTSAL PRI iEYOIOSS MUM TA i<i NQMQTA~AOE (3I Palo Verde Unit 1 TEXT Ill ssssss ssssss is FSss'st.ws oddeewl HJIC Fspnn~'sl IIT)0 5 0 0 0 5 2 8 8 7 013-00 0 2 OF 0 3 At approximately 1351 MST on April 8, 1987, Palo Verde Unit 1 was in Mode 1 (POWER OPERATION) at 100 percent power when Technical Specification (T.S.)Limiting Condition for Operation (LCO)3.0.3 was entered due to the inoperability of the Engineered Safety Features (ESF)(JE)pump room air exhaust systems (AHU).In accordance with T.S.LCO 3.0.3, actions were initiated to place the unit in a Mode in which the ESF pump room air exhaust cleanup systems are not required to be operable.T.S.LCO 3.0.3 was exited, at approximately 1541 on April 8, 1987 following the successful completion of surveillance test 73ST-9HF01 (Fuel Building AFU Airflow Capacity and Pressurization Test).The duration of this event was 1 hour and 50 minutes.On April 8, 1987, a system engineer (utility non-licensed) was reviewing the January 31, 1986 performance of surveillance test (ST)73ST-9HF01 for future revisions when he discovered that the ESF pump room air exhaust cleanup systems had not been surveillance tested as was indicated on the"Surveillance Test Package Review Sheet"..The system engineer discovered an entry in the surveillance test log that stated that the ESF pump room air exhaust cleanup systems were due to be surveillance tested in October 1986.In accordance with T.S.4.7.8.b.l, b.3, d.l and d.2, the ESF pump room air exhaust cleanup systems must be demonstrated operable once every 18 months.The previous test had been completed satisfactorily in April, 1985.The surveillance test interval, including the maximum allowable extension of 25 percent, was exceeded in March 1987.Upon notification of the finding, the Unit 1 Shift Supervisor (utility licensed)declared the ESF pump room air exhaust cleanup systems inoperable and entered the unit into T.S.LCO 3.0.3.The ESF pump room air exhaust cleanup system was declared operable and T.S.LCO 3.0.3 exited at approximately 1541 following successful completion of the surveillance testing.The root cause of this event was a cognitive personnel error by the system engineer (contractor non-licensed) in that he did not properly complete the"Surveillance Test Package Review Sheet".The responsible system engineer is no longer employed by Arizona Nuclear Power Project.The improper completion of the Surveillance Test Package Review Sheet" resulted in the Surveillance Program Control Group scheduling the next performance of 73ST-9HF01 for June 10, 1987.As a result, the surveillance interval for the ESF pump room air exhaust cleanup system was exceeded.Improper completion of the"Surveillance Test Package Review Sheet" is contrary to approved procedural controls.As corrective action, a memo has been sent to all onsite Managers to remind them it is the responsibility of each performance group to track their own Conditional ST's and any portion of a scheduled ST that could not be performed in its entirety to ensure their status is maintained current.'sRC s ORM 355A I953s
I NAC Form Sdd                                                                                                                                        VS. NUCLEAR REOULATOAY COMMISSION (D.BS)
APPAOVED OMB NO. 2)500)04 LICENSEE EVENT REPORT (LER)                                                          EXPIAES: ~ /21/DS FACILITY NAME (I)                                                                                                                      DOCKET NUMBER (2)                                  PA    2 TITLE lcl Palo Verde Unit                     1                                                                                           0    5    0    0    052                        or-  0 3 Entry Into Technical Specification                                              LCO      3.0.3    Due  to Personnel Error EVEN'1 DATE ISI                      LER NUMBER (5)                          REPORT DATE (7)                            OTHEA FACILITIES INVOLVED (5)
MONTH      DAY      YEAR      YEAR    "os(:
SEQUENT/AL oy REVS'ONTH                        DAY    YEAR            FAC/LITY NAMES                        DOCKET NUMBER(5)
NUMDDtl        NUMBER N A                                      0   5   0     0           0 0 4        088 787                              013               00 05 06                            7          N A                                      0   5    0    0            0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR ()t IChcch onc or morc                  of thc folforrind/ (Ill MODE (DI                    20,402(dl                                  20.405(c)                            50.72(cl(2)(lrl                              72.71(III POWER                            20.405( ~ ) (1)(l)                        50.25Ic)(II (ill)                    50,72( ~ )(2)(rl                              72.71(c)
LEYEL 1      0 0           20.405( ~ )(I)IQ)                          50.2dlc)(2)                          50,72( ~ )12)(rS)                            OTHER /Specify /n AO/rrcct hclow cnt/ ln ycct, HIIC form 20.405( ~ I() l(iill                      50.72(cl(2I(l)                        50 72(402)(rill) (Al                        d//SAI 20,4N(c) (I ) I lv I                      50.72(c)(2) IDI                        50.72(c) (2l(rill)IS) 20.405( ~ l(1)(v)                        50.7 2 Ic I (2 I                      50.72(cl(2)(cl LICENSEE CONTACT FOA THIS LER 112I NAME                                                                                                                                                        TELEPHONE NUMBER AREA CODE T. R. Bradish, Compliance Supervisor (Ext. 6936)                                                                                    602 932                        5            300 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOR'7 (12)
:";rgb'P()rtg,'c MANUFAC.          EPORTABLE Ay'j,acr Yn 4    y>>
CAUSE    SYSTEM      COMPONENT                                                                        VLE sYsTE    COMPONENT              MANUFAC.                                                  y-'O TVRER          TO NPRDS                                                                        TVRER              NPRDS          'r.A(tj)S 1!kP~'j%i5i iox IW+k:. >>>CNioo SUPPLEMENTAL REPOR'T EXPECTED 114)                                                                                  MONTH              OAY    YEAR EXPECTED SUBMISSION DATE (15)
YES Ilfycr, comp/crt E/IPECTED St/dc//SSIOH DATE/                                        HO ABSTRACT ILrmlt to f400 cpcccr. I.c.. cpprocimctcry fiftccn rind/c g>>cc rypcrrrlt>>n /mod      lid)
At approximately 1351 MST on April 8, 1987, Palo Verde Unit 1 was in Mode 1 (POt)tER OPERATION) at 100 percent power when Technical Specification (T.S.) Limiting Condition for Operation (LCO) 3.0.3 was en'tered due to the inoperability of the Engineered Safety Features (ESF) pump room air exhaust systems.                                                                               T.S. LCO 3.0.3 was exited at approximately 1541 on April 8, 1987 following the successful completion of Surveillance Test 73ST-9HF01 (Fuel Building AFU Airflow Capacity and Pressurization Test).                                   This event was discovered by a System Engineer (utility non-licensed) during a review of 73ST-9HFOl for future revisions.
The     root cause of this event was a cognitive personnel error by a system engineer (contractor non-licensed) in that he did not properly complete the "Surveillance Test Package Review Sheet". The responsible system engineer is no longer employed by Arizona Nuclear Power Project.                                               As corrective action, a memo has been sent to onsite Managers to remind them                                     it       is the responsibility of each performance group to track their own Conditional ST's and any portion of a scheduled ST that be performed in its entirety to ensure their status is maintained current.
could'ot No    similar events                      have been reported where improper documentation of *a                                                            partial surveillance test                        has resulted in exceeding a surveillance requirement.
8705120244 87050b PDR            ADOCK 05000528 8                                          PDR HRC corm Sdd


NRC'FoIm 344A 18 83I LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REOUI.ATONY COMMISSION APPROVED OM8 NO 3150 OIOS EXPIRES: 8/31/88 FACILITY NAME 111 Palo Verde Unit 1 TEXT////INvo s/Mco/I/POw'NL vso PROOo'one/P/RC FomI 38//AS/IITI DOCKET NUMEER 111 YEAR o s o o o 528 87 LER NUMEER IEI yes SSOUSNTIAL NUM SR 013 II 4 V IS IO 4 NUM 4 II-0 0~AOE 13)03oF 0 3 The successful completion of 73ST-9HF01 demonstrated the operability of the ESF pump room air exhaust cleanup system.Since the ESF pump room air exhaust cleanup system operated as designed, this event did not affect the safe operation of the plant or the health and safety of the public.There were no structures, components, or systems that were inoperable at the start of the event, other than those described above, that contributed to the event.There were no unusual characteristics of the work location which contributed to the event.There were no automatic or manually initiated safety system responses.
NRC Fosw 355A 1903 I e                                                    U 3 NUCLEAR REOULATORY COMMISSION LICENSEE EVENT REPORT ILERI TEXT CONTINUATION                                APPROVED OMS NO 3150 0104 EXPIRES: S/31/SS FACILITY NAME ITI                                                    DOCKET NUMSER l21 LER NUMSER I ~ I                      ~ AOE (3I YEAR '~i. 5EOUENTSAL    PRI iEYOIOSS i<i MUM TA          NQMQTA Palo Verde Unit TEXT Illssssss ssssss is FSss'st.
There were no operator actions which contributed to this event.No similar events have been reported where improper documentation of a partial surveillance test has resulted in exceeding a surveillance requirement.
1 ws oddeewl HJIC Fspnn ~'sl IIT) 0  5  0  0    0  5 2 8 8 7        013 00                      0 2  OF    0 3 At approximately 1351 MST on April 8, 1987, Palo Verde Unit 1 was in Mode 1 (POWER OPERATION) at 100 percent power when Technical Specification (T.S.) Limiting Condition for Operation (LCO) 3.0.3 was entered due to the inoperability of the Engineered Safety Features (ESF)(JE) pump room air exhaust systems (AHU). In accordance with T.S. LCO 3.0.3, actions were initiated to place the unit in a Mode in which the ESF pump room air exhaust cleanup systems are not required to be operable. T.S. LCO 3.0.3 was exited, at approximately 1541 on April 8, 1987 following the successful completion of surveillance test 73ST-9HF01 (Fuel Building AFU Airflow Capacity and Pressurization Test).                                  The duration of this event was 1 hour and 50 minutes.
4/IC I OIIM 344A 188)I I jl l l Arizona Nuclear Power Project P.o, BOX 52034~PHOENIX, ARIZONA 85072-2034 192-00203-JGH/TRB/MJC May 6, 1987 U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555  
On April 8, 1987, a system engineer (utility non-licensed) was reviewing the January 31, 1986 performance of surveillance test (ST) 73ST-9HF01 for future revisions when he discovered that the ESF pump room air exhaust cleanup systems had not been surveillance tested as was indicated on the "Surveillance Test Package Review Sheet".. The system engineer discovered an entry in the surveillance test log that stated that the ESF pump room air exhaust cleanup systems were due to be surveillance tested in October 1986.
In accordance with T.S. 4.7.8.b.l, b.3, d.l                              and d.2, the ESF pump room air exhaust cleanup systems must be demonstrated operable once every 18 months. The previous test had been completed satisfactorily in April, 1985. The surveillance test interval, including the maximum allowable extension of 25 percent, was exceeded in    March 1987.
Upon        notification of the finding, the Unit 1 Shift Supervisor (utility licensed) declared the ESF pump room air exhaust cleanup systems inoperable and entered the unit into T.S. LCO 3.0.3. The ESF pump room air exhaust cleanup system was declared operable and T.S. LCO 3.0.3 exited at approximately 1541 following successful completion of the surveillance testing.
The      root cause of this event was a cognitive personnel error by the system engineer (contractor non-licensed) in that he did not properly complete the "Surveillance Test Package Review Sheet". The responsible system engineer is no longer employed by Arizona Nuclear Power Project.                            The improper completion of the Surveillance Test Package Review Sheet" resulted in the Surveillance Program Control Group scheduling the next performance of 73ST-9HF01 for June 10, 1987. As a result, the surveillance interval for the ESF pump room air exhaust cleanup system was exceeded.                  Improper completion of the "Surveillance Test Package Review Sheet" is contrary to approved procedural controls.
As    corrective action, a memo has been sent to all onsite Managers to remind them it is ST's the responsibility of each performance group to track their own Conditional and any portion of a scheduled ST that could not be performed in its entirety to ensure their status is maintained current.
'sRC  s  ORM 355A I953s
 
NRC'FoIm 344A                                                                                                U.S. NUCLEAR REOUI.ATONY COMMISSION 18 83I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                            APPROVED OM8 NO 3150 OIOS EXPIRES: 8/31/88 FACILITY NAME       111                                              DOCKET NUMEER 111           LER NUMEER IEI                      ~ AOE 13)
YEAR yes SSOUSNTIAL        II4 V IS IO 4 NUM SR        NUM 4 II Palo Verde Unit                     1                         o  s  o  o    o 528 87        013 0                  0    03oF        0 3 TEXT   ////INvo s/Mco /I /POw'NL vso PROOo'one/P/RC FomI 38//AS/ IITI The       successful completion of 73ST-9HF01 demonstrated the operability of the ESF pump room             air exhaust cleanup system. Since the ESF pump room air exhaust cleanup system operated as designed, this event did not affect the safe operation of the plant or the health and safety of the public.
There were no structures, components, or systems that were inoperable at the start of the event, other than those described above, that contributed to the event.
There were no unusual characteristics of the work location which contributed to the event. There were no automatic or manually initiated safety system responses.
There were no operator actions which contributed to this event.
No     similar events                     have been reported where improper documentation of a                   partial surveillance test                       has resulted in exceeding a surveillance requirement.
4/IC I OIIM 344A 188)I
 
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Arizona Nuclear Power Project P.o, BOX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00203-JGH/TRB/MJC May 6, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555


==Subject:==
==Subject:==
Palo Verde Nuclear Generating Station (PVNGS)Unit 1 Docket No.STN 50-528 Licensee Event Report 87-013-00 File: 87-020-404
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 Licensee Event Report       87-013-00 File: 87-020-404
 
==Dear  Sirs:==
 
Attached please find Licensee Event Report (LER) No. 87-013-00 prepared and submitted pursuant to 10 CFR 50.73. In accordance with 10 CFR 50,.73(d), we are herewith forwarding a copy of the LER to the Regional Administrator of the Region V Office.
If you have any questions, please contact T.          R. Bradish, Compliance Supervisor at (602) 932-5300 Ext. 6936.
Very  tru    y  yours, l/6 J.
yr~
G. Haynes Vice President Nuclear Production JGH/MJC/cld Attachment CCI      0. M. DeMichele            (all    w/a)
E. E. Van Brunt,  Jr.
J. B. Martin R. P. Zimmerman R. C. Sorensen E. A. Licitra A. C. Gehr INPO Records  Center


==Dear Sirs:==
Attached please find Licensee Event Report (LER)No.87-013-00 prepared and submitted pursuant to 10 CFR 50.73.In accordance with 10 CFR 50,.73(d), we are herewith forwarding a copy of the LER to the Regional Administrator of the Region V Office.If you have any questions, please contact T.R.Bradish, Compliance Supervisor at (602)932-5300 Ext.6936.Very tru y yours, l/6 yr~J.G.Haynes Vice President Nuclear Production JGH/MJC/cld Attachment CCI 0.M.E.E.J.B.R.P.R.C.E.A.A.C.INPO DeMichele Van Brunt, Jr.Martin Zimmerman Sorensen Licitra Gehr Records Center (all w/a)
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Revision as of 10:29, 29 October 2019

LER 87-013-00:on 870408,Tech Spec 3.0.3 Entered Due to Inoperability of ESF Pump Room Air Exhaust Sys.Caused by Cognitive Personnel Error.Memo Sent to Onsite Managers Reminding Personnel of responsibilities.W/870506 Ltr
ML17300A824
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 05/06/1987
From: Bradish T, Haynes J
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00203-JGH-T, LER-87-013, NUDOCS 8705120244
Download: ML17300A824 (10)
v • d • e


Text

REQULAT INFORMATION DISTRIBUTION ~TEM (RIDS)

ACCESSION NBR: 8705120244 DOC. DATE: 87/05/06 NOTARIZED: NO DOCKET ¹ FACIL: STN-50-528 Palo Verde Nuclear Station> Uni t 1> Ari zona Pub li 05000528 AUTH. NAME AUTHOR AFFILIATION BRADISH> T. R. Arizona Nuclear'o!.'er Prospect ( formerlM Ari zona Public Serv HAYNES> J. Q. AT izona Nuclear Pouer Prospect (formerly Ari zona Public Serv REC IP. NAME RECIPIENT AFFILIATION BUB JECT: LER 87-013-00: on 870408> Limiting Condition for Operation

. 3 0 3 entered due to inoperability of ESF pump room air exhaust sos. Caused bM cognitive personnel error Memo sen+ to~

onsite managers reminding of responsibilities. W/870506 I+r.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR l ENCL l SIZE:

TITLE: 50. 73 Licensee Event Report (LER)> Incident Rpt> etc.

NOTES: Standardi zed plant. M. Davis> NRR: iCg. 05000528 RECIPIENT COPIES REC IP I ENT COP IEB ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR Er,'CL PD5 LA 1 PD5 PD 1 1 LICITRA E 1 DAVIS> M 1 1 INTERNAL: ACRS MICHELBON 1 1 *CRS MOELLER 1 1 AEOD/DOA AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB DEQRO 1 1 NRR/DEBT/ADE 1 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1.

NRR/DEST/ICBB 1 1 NRR/DEBT/MEB 1 1 NRR/DEBT/MTB NRR/DEST/PSB 1 NRR/DEST/RSB h!RR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/EPB 1

'

1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 NR A LRB 1 1 h!RR/PMAS/PTSB 1 EQ FIL 02 1 RES SPEIS> T 1 1 QN FILE 01 1 1 EXTERNAL: EQ8cG QROH> M 5 5 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 NBIC HARRIS> J 1 1 NBIC MAYS> G 1 1 NOTES:

TOTAL, NUMBER OF COPIES REQUIRED: LT1R 44 ENCL 42

I NAC Form Sdd VS. NUCLEAR REOULATOAY COMMISSION (D.BS)

APPAOVED OMB NO. 2)500)04 LICENSEE EVENT REPORT (LER) EXPIAES: ~ /21/DS FACILITY NAME (I) DOCKET NUMBER (2) PA 2 TITLE lcl Palo Verde Unit 1 0 5 0 0 052 or- 0 3 Entry Into Technical Specification LCO 3.0.3 Due to Personnel Error EVEN'1 DATE ISI LER NUMBER (5) REPORT DATE (7) OTHEA FACILITIES INVOLVED (5)

MONTH DAY YEAR YEAR "os(:

SEQUENT/AL oy REVS'ONTH DAY YEAR FAC/LITY NAMES DOCKET NUMBER(5)

NUMDDtl NUMBER N A 0 5 0 0 0 0 4 088 787 013 00 05 06 7 N A 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR ()t IChcch onc or morc of thc folforrind/ (Ill MODE (DI 20,402(dl 20.405(c) 50.72(cl(2)(lrl 72.71(III POWER 20.405( ~ ) (1)(l) 50.25Ic)(II (ill) 50,72( ~ )(2)(rl 72.71(c)

LEYEL 1 0 0 20.405( ~ )(I)IQ) 50.2dlc)(2) 50,72( ~ )12)(rS) OTHER /Specify /n AO/rrcct hclow cnt/ ln ycct, HIIC form 20.405( ~ I() l(iill 50.72(cl(2I(l) 50 72(402)(rill) (Al d//SAI 20,4N(c) (I ) I lv I 50.72(c)(2) IDI 50.72(c) (2l(rill)IS) 20.405( ~ l(1)(v) 50.7 2 Ic I (2 I 50.72(cl(2)(cl LICENSEE CONTACT FOA THIS LER 112I NAME TELEPHONE NUMBER AREA CODE T. R. Bradish, Compliance Supervisor (Ext. 6936) 602 932 5 300 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOR'7 (12)

";rgb'P()rtg,'c MANUFAC. EPORTABLE Ay'j,acr Yn 4 y>>

CAUSE SYSTEM COMPONENT VLE sYsTE COMPONENT MANUFAC. y-'O TVRER TO NPRDS TVRER NPRDS 'r.A(tj)S 1!kP~'j%i5i iox IW+k:. >>>CNioo SUPPLEMENTAL REPOR'T EXPECTED 114) MONTH OAY YEAR EXPECTED SUBMISSION DATE (15)

YES Ilfycr, comp/crt E/IPECTED St/dc//SSIOH DATE/ HO ABSTRACT ILrmlt to f400 cpcccr. I.c.. cpprocimctcry fiftccn rind/c g>>cc rypcrrrlt>>n /mod lid)

At approximately 1351 MST on April 8, 1987, Palo Verde Unit 1 was in Mode 1 (POt)tER OPERATION) at 100 percent power when Technical Specification (T.S.) Limiting Condition for Operation (LCO) 3.0.3 was en'tered due to the inoperability of the Engineered Safety Features (ESF) pump room air exhaust systems. T.S. LCO 3.0.3 was exited at approximately 1541 on April 8, 1987 following the successful completion of Surveillance Test 73ST-9HF01 (Fuel Building AFU Airflow Capacity and Pressurization Test). This event was discovered by a System Engineer (utility non-licensed) during a review of 73ST-9HFOl for future revisions.

The root cause of this event was a cognitive personnel error by a system engineer (contractor non-licensed) in that he did not properly complete the "Surveillance Test Package Review Sheet". The responsible system engineer is no longer employed by Arizona Nuclear Power Project. As corrective action, a memo has been sent to onsite Managers to remind them it is the responsibility of each performance group to track their own Conditional ST's and any portion of a scheduled ST that be performed in its entirety to ensure their status is maintained current.

could'ot No similar events have been reported where improper documentation of *a partial surveillance test has resulted in exceeding a surveillance requirement.

8705120244 87050b PDR ADOCK 05000528 8 PDR HRC corm Sdd

NRC Fosw 355A 1903 I e U 3 NUCLEAR REOULATORY COMMISSION LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVED OMS NO 3150 0104 EXPIRES: S/31/SS FACILITY NAME ITI DOCKET NUMSER l21 LER NUMSER I ~ I ~ AOE (3I YEAR '~i. 5EOUENTSAL PRI iEYOIOSS i<i MUM TA NQMQTA Palo Verde Unit TEXT Illssssss ssssss is FSss'st.

1 ws oddeewl HJIC Fspnn ~'sl IIT) 0 5 0 0 0 5 2 8 8 7 013 00 0 2 OF 0 3 At approximately 1351 MST on April 8, 1987, Palo Verde Unit 1 was in Mode 1 (POWER OPERATION) at 100 percent power when Technical Specification (T.S.) Limiting Condition for Operation (LCO) 3.0.3 was entered due to the inoperability of the Engineered Safety Features (ESF)(JE) pump room air exhaust systems (AHU). In accordance with T.S. LCO 3.0.3, actions were initiated to place the unit in a Mode in which the ESF pump room air exhaust cleanup systems are not required to be operable. T.S. LCO 3.0.3 was exited, at approximately 1541 on April 8, 1987 following the successful completion of surveillance test 73ST-9HF01 (Fuel Building AFU Airflow Capacity and Pressurization Test). The duration of this event was 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 50 minutes.

On April 8, 1987, a system engineer (utility non-licensed) was reviewing the January 31, 1986 performance of surveillance test (ST) 73ST-9HF01 for future revisions when he discovered that the ESF pump room air exhaust cleanup systems had not been surveillance tested as was indicated on the "Surveillance Test Package Review Sheet".. The system engineer discovered an entry in the surveillance test log that stated that the ESF pump room air exhaust cleanup systems were due to be surveillance tested in October 1986.

In accordance with T.S. 4.7.8.b.l, b.3, d.l and d.2, the ESF pump room air exhaust cleanup systems must be demonstrated operable once every 18 months. The previous test had been completed satisfactorily in April, 1985. The surveillance test interval, including the maximum allowable extension of 25 percent, was exceeded in March 1987.

Upon notification of the finding, the Unit 1 Shift Supervisor (utility licensed) declared the ESF pump room air exhaust cleanup systems inoperable and entered the unit into T.S. LCO 3.0.3. The ESF pump room air exhaust cleanup system was declared operable and T.S. LCO 3.0.3 exited at approximately 1541 following successful completion of the surveillance testing.

The root cause of this event was a cognitive personnel error by the system engineer (contractor non-licensed) in that he did not properly complete the "Surveillance Test Package Review Sheet". The responsible system engineer is no longer employed by Arizona Nuclear Power Project. The improper completion of the Surveillance Test Package Review Sheet" resulted in the Surveillance Program Control Group scheduling the next performance of 73ST-9HF01 for June 10, 1987. As a result, the surveillance interval for the ESF pump room air exhaust cleanup system was exceeded. Improper completion of the "Surveillance Test Package Review Sheet" is contrary to approved procedural controls.

As corrective action, a memo has been sent to all onsite Managers to remind them it is ST's the responsibility of each performance group to track their own Conditional and any portion of a scheduled ST that could not be performed in its entirety to ensure their status is maintained current.

'sRC s ORM 355A I953s

NRC'FoIm 344A U.S. NUCLEAR REOUI.ATONY COMMISSION 18 83I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OM8 NO 3150 OIOS EXPIRES: 8/31/88 FACILITY NAME 111 DOCKET NUMEER 111 LER NUMEER IEI ~ AOE 13)

YEAR yes SSOUSNTIAL II4 V IS IO 4 NUM SR NUM 4 II Palo Verde Unit 1 o s o o o 528 87 013 0 0 03oF 0 3 TEXT ////INvo s/Mco /I /POw'NL vso PROOo'one/P/RC FomI 38//AS/ IITI The successful completion of 73ST-9HF01 demonstrated the operability of the ESF pump room air exhaust cleanup system. Since the ESF pump room air exhaust cleanup system operated as designed, this event did not affect the safe operation of the plant or the health and safety of the public.

There were no structures, components, or systems that were inoperable at the start of the event, other than those described above, that contributed to the event.

There were no unusual characteristics of the work location which contributed to the event. There were no automatic or manually initiated safety system responses.

There were no operator actions which contributed to this event.

No similar events have been reported where improper documentation of a partial surveillance test has resulted in exceeding a surveillance requirement.

4/IC I OIIM 344A 188)I

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Arizona Nuclear Power Project P.o, BOX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00203-JGH/TRB/MJC May 6, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528 Licensee Event Report 87-013-00 File: 87-020-404

Dear Sirs:

Attached please find Licensee Event Report (LER) No. 87-013-00 prepared and submitted pursuant to 10 CFR 50.73. In accordance with 10 CFR 50,.73(d), we are herewith forwarding a copy of the LER to the Regional Administrator of the Region V Office.

If you have any questions, please contact T. R. Bradish, Compliance Supervisor at (602) 932-5300 Ext. 6936.

Very tru y yours, l/6 J.

yr~

G. Haynes Vice President Nuclear Production JGH/MJC/cld Attachment CCI 0. M. DeMichele (all w/a)

E. E. Van Brunt, Jr.

J. B. Martin R. P. Zimmerman R. C. Sorensen E. A. Licitra A. C. Gehr INPO Records Center

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