ML17303A394

LER 85-035-01:on 850525 & 0604,pump Performance Tests Not Reviewed within 96 H,Per IWP-3220 of ASME Code.Caused by Procedural Error.Procedures for Surveillance Program Changed to Direct All Procedures to engineers.W/870330 Ltr

ML17303A394
Person / Time
Site:	Palo Verde
Issue date:	03/30/1987
From:	Bradish T, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
192-00171-JGH-T, LER-85-035, NUDOCS 8704130629
Download: ML17303A394 (14)

Text

REGULAT INFORNATION DISTRIBUTION TEN (RIDS)

J ACCESSION NBR: 8704130629 DOC. DATE: 87/03/30 NOTARIZED: NO DOCKET q ~ FAC IL: STN-50-528 Pal o Verde Nuclear Station. Uni t 1> Ari zona Pub 1 i 05000528 AUTH. NANE, AUTHOR AFFILIATION BRADISH, T. R. Arizona Nuclear Pouer Prospect (formerly Ari zona Public Serv HAYNEBi J. G. Ar i zona Nuclear Pcwer Pr o Ject ( formerly Ari zona Public Serv RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 85-035-01: on 850525 5 060%I pump peT formance tests not reviewed within 96 hI per IWP-3220 of ASME Code. Caused bg procedural error. Procedures for surveillance program changed to direct all procedures to engineers. 4l/870330 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR I ENCL TITLE: 50. 73 Licensee Event Report (LER) Incident Rpti etc.

~ SIZE:

NOTES: Standardized plant. N. Davis'RR: aCg. 05000528 REC1P I ENT COPIES RECIPIENT COP IES ID CODE/NAl'lE LTTR EtiCL ID CODE/NAME LTTR ENCL PD5 L* 1 PD5 PD 1 1 LICITRA E 1 DAVIS> M 1 INTERNAL: ACRB NICHELSON 1 1 ACRS MOELLER 1 ACRB WYL.IE 1 1 AEOD/DOA 1

• EOD/DSP/ROAB 2 2 AEOD/DSP/TAPB 1

.NRR/ADT 1 NRR/DEST/ADE 0 NRR/DEST/*DB 0 ERR/DEBT/CEB 1 NRR/DEBT/EL.B 1 1 NRR/DEBT/ ICSB 1 NRR/DEBT/NEB a t .'R R /DEBT/ NT8 1 NRR/DEBT/PSB NRR/DEBT/RSB a NRR/DEBT/SGB ERR/DLPG/HFB 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB 1 NRR/DREP/EPB 1 1 NRR/DREP/R*B 1 IAS/ILRB 1 1 NRR/PNAB/PTSB 1 02 1 1 RES SPEIS> T 1 RGN5 F ILE Oi 1 EXTERNAL: EG8cG GR OHI M 5 5 H ST LOB B Y WARD LPDR 1 NRC PDR NBIC H*RR IS J 1 1 twiBI C MAYSI G NO1 ES:

TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 41

1 NRC Form 355 VA. NVCLEAR REGULATORY COMMISSION (933)

APPAOV ED 0MB NO. 3160410C LICENSEE EVENT REPORT (LER) EXPIRES: 5/31/SS FACILITY NAME (II DOCKEt NUMBER 11) PA E Palo Verde Unit 1 0 5 0 0 0 5 2 1OF03

'TITLE Iei Failure to Perform ASME Section XI Re uired Test Review EVENT DATE I5) LER NUMBER (5) REPORt DATE (7) OTHER FACILI'TIES INVOLVED ISI MONTH OAY YEAR YEAR SEOVCNTI*L Rl VISION DAY FACILITYNAMES DOCKET NUMBER(3)

NUMBER NUMBER MONTH YEAR N A 0 5 0 0 0 52 585 85 035

)Ill(i) 0 1 0 3 3 0 8 7 N A 0 5 0 0 0 OPERATING THIS REPORT IS SVSM)tTED PURSUANT 7 0 THE REOUIREMENTS OF 10 CFR II: IChrce onr or morr of the followr'npf (ll MODE (5) 20A02(O) ,20AO5(cl 50.73(el(2) (tv l 73.71(5)

~ OWER 20AOB( ~ 50.35(cl(ll 50.73(c)(1)(vl 73.71(cl LEVEL p p 20 ASS(c) (I ) (5) 50.35(c)(2) 50.73(el)2) lvS) OTHER ISprcify in AOItrrtt Oelow rmtin Trit, HAC Form 20AOB(II(1 l(riil X 50.73(el(2)lil 50.73(el(2) (viii)IAI JSSAI

gg:,";,:j c-.

F+igvj 10AOS(c )(1K(vi 50.7 3 (e) I2) I 5 I 50.73(el(2)(vBII(SI 10AOS( ~ l(1)(v) 50.73(e l(2) (iiil 50 73( ~ )(2)lcl LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE Thomas R. Bradish, Com liance Su ervisor (Ext. 6936) 602 932 -530 0 COMPLETE. ONE LINE FOR EACH COMPONENT FAILURE DESCSIISED IN THIS REPOAT l13)

MANUFAC EPORTASLE MANUFAC CAUSE SYSTEM COMPONENT TURER TO NPRDS RETRIIIP/EI c crr SYSTEM COMPONENT TURER EPORTABI.E TO NPRDS SUPPLEMENTAL REPORT EXPECTED (Iel MONTH DAY YEAR EXPECTED SUBMISSION DATE (151 YES IlfyN, ComPlrtr EXPECTED S(IPMISSIOIY DATEI X

ABETRAcT I(imit to tr00 Iprcri, ir., rpproiimetrly frftrrn tinplr corer typrwnnrn linrD (15l At the time of these events, Palo Verde Unit 1 was in Mode 2 at normal operating temperature and pressure.

Palo Verde Unit 1 Technical Specification (Tech Spec) 4.0.5 specifies the Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components. This inspection and testing shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.

Twice on lhy 25 and once on June, 4, 1985, pump performance test results were not reviewed within the 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> required by IMP-3220 of the ASME Code.

The cause of these events has been determined to be procedural errors in the routing of test data that caused review delay. Steps will be taken to eliminate these procedural errors in routing.

8704130629 870330 PDR ADOCK 05000528 S

PDR NRC Serm 3SS

P f

t

NRC FoII>>I 344A U.S. NUCLEAR REGULATORY COMMISSION 1943)

LICENSEE EVENT REPORT {LER) TEXT CONTINUATION APPROYEO OMS NO 31SG-GIGA EXPIRES: EI31(88 FACILITY NAME 111 OOCKET NUMEER 11l LER NUMSER ISI PAGE 131 YEAR 5'EQUENTIAL @i>> AKVISIGII NVMIIA MVMFFA Palo Verde Unit 1 0 s 0 0 0 528 8 5 0 3 5 1 0 2 OF 0 3 TEXT O'II<<4 Soscs iI IPFIsl<<E v>> RSI4'<<ISSHRC f<<IIIALA'si IITl Palo Verde Unit 1 Tech Spec 4;0.5 specifies the Surveillance Requirements for inservice inspection and testing of ASHE Code Class 1, 2, and 3 components.

The results of the pump performance tests that took place on May 18, 1985, Hay 21, 1985, and May 30, 1985 were not reviewed by the reviewing engineers within the 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> required by IMP-3220 of the ASHE Boiler and Pressure Vessel Code,Section XI.

These events occurred while the unit was in Mode 2 at normal operating temperature and pressure.

The following three events occurred that exceeded the required 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> review requirement:

1. The Train "B" Containment Spray Pump (BE) was tested on Hay 18, 1985, at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. The test results were not reviewed until 0928 on May 25, 1985.

2. The Train "B" Essential Spray Pond Pump (BS) was tested at 0640 hours0.00741 days <br />0.178 hours <br />0.00106 weeks <br />2.4352e-4 months <br /> on Hay 21, 1985, but the ASHE review did not occur until 0934 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.55387e-4 months <br /> on May 25, 1985.

3. The Train "A" Charging Pump (CB) was tested on May 30, 1985, at 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br />. The ASHE review was not completed until June 4, 1985, at 1407 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.353635e-4 months <br />.

In all three cases, the pump test results met acceptance criteria at the test time and all were declared operable by the Shift Supervisor.

The routing procedure, then in effect for completed tests was: 1) From Control Room to Drawing and Document Control (DDC), 2) DDC to the Surveillance Program Control Group (SPCG) and, 3) SPCG to the reviewing engineer.

The following corrective actions are being implemented to prevent a recurrence of these events.

1. The controlling procedure for the Surveillance Program (73AC-9ZZ04) has been changed to direct DDC to forward all completed pump surveillance procedures directly to the reviewing engineers and then to SPCG.

2. The reviewing engineers will be placed on the distribution list for all surveillance test schedules to keep them apprised of pump testing in advance of procedure performance.

3. Additionally, the Shift Technical Advisors (STAs) (Utility licensed and non-licensed) perform a review of the completed tests in the control room to fulfill the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> review requirement. The STAs are onshift

'>>IIC I ORM 5444 I9 83I

I NRC Form 344A U,S, NUCLEAR REGULATORY COMM/SS/ON

/9.83)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMS NO 3/50 0/04 EXP/RES 8/31/88 FACILITY NAME II I OOCKET NUMSER ISI LER NUMSER'IS) PAGE ISI YEAR SE GVSNTIAL Pjcy, REVISION NVMIITR NVMPfR TEXT /// moro cpoco 8 ror/Ir/lor/ I/oo aaWirw'///C form 3//8A'c/ I IT/

0 5 0 0 0 5 2 8 5 035 01 03 OF 0

3. Continued 24 hours a day, 7 days a week, so the tests can be reviewed shortly after completion, The original corrective action taken for this event involved the use of a label to identify ASHE Section XI tests.

However, the STAs now perform the test review in order to minimize the time between completion of testing and the review of the test data and to reduce the possibility. of misplaced test packages.

No previous similar events have been reported.

VRC IORM 344k 19 83l

t 1

NRC Form 345 U.Sr NUCLEAR SIEGULATORY COMMISSION (9.53)

APPROVED OMB NO. 31504104 LICENSEE EVENT REPORT {LER) EXPIRES: SI31ISS FACILITY N AME ( I ) DOCKET NUMBER (2) PA 3I TITLE (4I Palo V r 0 5 0 0 0 5 2 8 1 oF0 Failure to Perform ASME Section XI Re uired Test Review EVENT DATE(5) LER NUMBE'R (5) REPORT DATE l7) OTHER FACILITIES INVOLVED (SI MONTH OAY YEAR YEAR SSOVSNTI*L AX IISVrcrOrs MONTH OAY YEAR FACILITYNAMES DOCKET NUMBERIS) ssvMBEA f53 trvMBEII N/A 0 5 0 0 0 0 7 0 3 8 585 045 01 0 3 3 0 8 7 THIS REPORT IS SUBMITTED PURSUANT 1 0 THE REQUIREMENTS OF 10 CFR (I: (Chose one or more N/A 0 5 0 0 0 OPERATINO ol the forlowingl (11 MODE (9) 20.402(S) 20.405(c) 50.13(e)LTI(lvl 73.71(SI POWE R 20.405( ~ ) II I II) 50.35 (c) (11 50.73(e) (2(HI 73.7 1(c)

LEVEL I10) 20.405(sI I I I(S) 50.35(cH2) 50.73(el(2) IvS I OTHER (Specify in renttrett Oelow enrf ln Test, HIIC Form 20,405( ~ HI I(rill X 50.73(e)(2HB 50.13(eH2) lvlllHAI 3ESAI 20.405(e Hl l(Iv) 50 73(eH2) (ill 50.73(e H2 Hv(SHB) 20.405(el(IHvl 50.73(402HI(l) 50.73 I ~ ) (2)(el LICENSEE CONTACT FOR THIS I.ER 112I NAME TELEPHONE NUMBER AREA CODE Thomas R. Bradish, Com liance Su ervisor Ext. 6936)

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 602 932 53 00 MANUFAC.

CAUSE SYSTEM COMPONENT TVRER CAUSE SYSTEM COMPONENT MANVFAC TUREA EPORTABLE <<'g+v@P~

TO NPRDS Qi~<k~x~<<:.A+p,st

..';.gg

@4~4$%j>'."II .Iv~,

I"gAC+~~j.-.:

SUPPLEMENTAL REPORT EXPECTED I)4) MONTH DAY YEAR EXPECTED SUBMISSION YES llf yes, complsre EXPECTED SVSMISSIOrY DATE) DATE 05)

NO ASSTAACT (Limit to te00 speceL I ~ ., epprosimetely Irfteen singre specs typewritten hnesl (15)

On July 3, 1985, Palo Verde Unit 1 was in Mode 1 and at 38 percent reactor power.

Palo Verde Unit 1 Technical Specification (Tech Spec) 4.0.5 specifies the Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components. This inspection and testing shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.

Procedure 41ST-1SI10 was performed on the train "B" High Pressure Safety Injection Pump (HPSI)(BQ) on June 22, 1985. The pump test results were not reviewed within the required time limit of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

The cause of this is the same as in LER 85-035-00. Procedural errors in the routing of test data caused the review delay. Steps had been taken to eliminate these procedural errors but were not fully implemented at the time of this event. These steps 'are now complete.

NRC form 354

f f

NRC Form 3EEA U.E. NUCLEAR REGULATORY COMMSEESON I8 83I LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVEO OM8 NO 3lm~lOS EXPIRES: EI3l/88 FACILITY NAME ill OOCKET SSUMEER l2l LER SSUMEER IEI PACE I3s SEQVENTSAL rsLYresoN YEAR <<g NVM EN NVMPEN Palo Verde Unit 1 o s o o o 5 2 8 8 5 045 0 1 02oF 02 TEXT IIImore soece II eoerwed, srse ddreoonNI IIIIC Form OPIA'sI lit)

Palo Verde Unit 1 Technical Specification (Tech Spec) .4.0.5 specifies the Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components. The results of the pump performance test that took place'n July 3, 1985 vere not revieved by the reviewing engineers (non-licensed utility and contract) within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> required by IVP-3220 of the ASME Boiler and Pressure Vessel Code,Section XI. This was discovered by the engineers doing the review.

This event occurred while the unit was in Mode 1 and at 38 percent reactor power with normal operating temperature and pressure.

HPSI "B" pump had been tested on June 22, 1985 at 1107. The required ASME review of the test results vere not completed until July 3, 1985 at 1212. This event is identical vith those incidents identified in LER 85-035-00. At that time the following corrective actions were specified to correct the problem.

1. The controlling procedure for the Surveillance Program (73AC-9ZZ04) has been changed to direct Drawing and Document Control (DDC) to forward all completed pump surveillance procedures directly to the reviewing engineers and then to the Surveillance Program Control Group (SPCG).

2. The revieving engineers have been placed on the distribution list for all su'rveillance test schedules to keep them apprised of pump testing in advance of procedure performance.

3, Additionally, the Shift Technical Advisors (STAs) (Utility licensed and non-licensed) perform a review of the completed tests in the control room to fulfill the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> review, requirement. The STAs are onshift 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day 7 days a week, so the tests can be reviewed shortly after completion.

The original corrective action taken for this event involved the use of a label to identify ASME Section XI tests. However, the STAs now perform the test review in order to minimize the time between completion of testing and the review of the test data and to reduce the possibility of misplaced test packages, At the time of this most recent event, the corrective action had not been fully implemented. This was determined to be the root cause of the event.

In addition to the corrective action stated, the reviewing engineers will monitor the required surveillance test schedules and will alert DDC on the timeliness of review/requirements.

The ASME review was completed on July 3, 1985. The results of the review revealed that the HPSI "B" pump passed satisfactorily. Therefore this event had no impact on the health and safety of the public.

A similar event was reported in LKR 528-85-035.

NsrC s SSNM 2SO+

IO 83 I

I l

Arizona Nuclear Power Project P.o. BOX 52034 ~ PHOENIX. ARIZONA 85072-2034 192-00171-JGH/TRB/JHT March 30, 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 Reports 85-035-01 and 85-045-01 File: 87-020-404

Dear Sirs:

Attached please find Supplement Nos. Ol to Licensee Event Report (LER) Nos.

85-035-00 and 85-045-00 prepared and submitted pursuant to the requirements of 10 CFR 50.73(d). We are herewith forwarding a copy of this report 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 truly yours, J. G. Haynes Vice President Nuclear Production JGH/TRB/cld Attachment cc: 0. M. DeMichele (all w/a)

E. E. Van Brunt, Jr.

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

)I. f

-r I I

ff If II I

I I

(

I