ML17305A568

LER 89-005-01:on 890310,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Electrical Loads in Excess of Circuit Capacity.Design Mod Issued to Supply Dedicated Power to loads.W/900302 Ltr

ML17305A568
Person / Time
Site:	Palo Verde
Issue date:	03/02/1990
From:	Bradish T, James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
192-00636-JML, 192-636-JML, LER-89-005-02, LER-89-5-2, NUDOCS 9003130597
Download: ML17305A568 (16)

Text

ACCELERATED DISIIUBUTION DEMONSHRATION SY%TM I

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9003130597 'DOC.DATE 90/03/02 NOTARIZED: NO DOCKET

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FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi '05000529 AUTH. NAME AUTHOR AFFILIATION BRADISH,T.R. Arizona Public Service Co. (formerly Arizona Nuclear Power LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT'FFILIATION

SUBJECT:

LER 89-005-01:on 890310,loss of power to alternate plant

'ventilation effluent radiation monitor.

W/8 ltr.

DISTRIBUTION CODE: ZE22T COPIES RECEIVED:LTR 1 ENCL ~

.SIZE:

TITLE:. 50.73/50.9'icensee Event Report (LER),, Incident Rpt, etc..

NOTES:Standardized plant. '05000529 RECIPIENT COPIES RECIPIENT COPIES ID

'D CODE/NAME LTTR ENCL CODE/NAME ~

LTTR ENCL P.D5 LA 1 1 PD5 PD 1 1 PETERSON,S. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1' AEOD/DSP/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1. 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 '1 1 NRR/DET/ESGB 8D NRR/DLPQ/LPEB10 1,

1

' 1 NRR/DLPQ/LHFB11 NRR/DOEA/OEAB11 1

1

'1 1

NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 N PLB8D1 1 1 NRR/DST/SRXB 8E 1 1 G F 02 1' RES/DSIR/EZB 1 1 .R FILE 01 1 1 EXTERNAL: EGGG WILLIAMS,S 4 4 L ST LOBBY WARD 1' LPDR 1. 1 NRC PDR 1 1 NSIC 1 1 NSIC'URPHY,G.A 1. 1 FULL TXT, 1 1 MAYS,G'UDOCS NOTES:

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US. TO REDUCE WAS'! CONTACT THE.DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM'.DISTRIBUTION C

FULL TEXT CONVERSION REQUIRED-TOTAL NUMBER'OF COPIES REQUIRED: LTTR 38 ENCL 38 P.

il Ik Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 ~ PHOENIX. ARIZONA 85072-2034 192-00636-JML/TRB/DAJ; JAMES M. LEVINE VICE PRESIDENT Marh 2, 1990 NUCLEAR PRDDVCTIDN U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sirs:

Subj ect: Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 Docket No. STN 50-529 (License No. NPF-51)

Licensee Event Report 89-005-01 File'0-020-404 Attached please find Supplement Number 1 to Licensee Event Report (LER) No.

89-005-00 prepared and submitted pursuant to 10CFR50.73. This report is being submitted to update the scheduled date for implementing a design modification.

The schedule has been revised'ue to the unavailability of parts. In accordance with 10CFR50.73(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, (Acting) Compliance Manager at (602) 393-2521.

Very truly yours, JML/TRB/DAJ/k)

Attachment CC: W. F ~ Conway (all with attachment)

E., E. Van Brunt J. B. Martin D'. H. Coe M. J. Davis A. C. Gehr INPO Records Center EF gg 9003i30597 900302 PDR ADOCK 0 000529 PDC

0 II'(C FORM~ U.S. NUCLEAR REGULATORY COMMISSION (849( APPROVED OMB NO. 3(504)104 EXPIRES: 4(30(92 IMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REGUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT. ILER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS ANO REPORTS MANAGEMENTBRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. OC 20555, AND TO THE PAPERWORK REDUCTION PROIECT (31500104). OFFICE OF MANAGEMENTANO BUDGFT,WASHINGTON, DC 20503.

FACILITY NAME (II DOCKET NUMBER lll I'A 5 3)

TITLE (41 Palo Verde Unit 2 o so oo529>OFQ Loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor EVENT DATE (5) LKR NUMBER (6) REPORT OATK (7) OTHER FACILITIES INVOLVED (5)

MONTH OAY YEAR YEAR SEQUENTIAL RavraroN OAY FACILITYNAMES DOCKET NUMBFR(SI NUMBE rl NUMSErr MONTH YEAR N/A 0 5 0 0 0 0 3 1 0 8 9 8 9 ,005 0 1 0 3 0 2 9 0 N/A 0 5, 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (): (Chrch one or morr of thr forlornnfi (1'I OPERATING MODE (9) 1 20.402(b) 20A05(cl 50,73(a) (2)(lrl (air(l 73.71 Br)

POWER 20.405( ~ )Oil() 50DS(a) (I I 50.73(a) (2((el 73.7( (c) .

LEYEL 1 0 0 20A05( ~ ) it)(B) 50.35(cl(2) 60.73(a) (1) (rill OTHER (Sprcily (n Ahrrract hrlow and In Trit, HRC Form 20.405( ~ )l1)(E(l 'X 50.73( ~ ) (2)(I) 50.73(al(2) IA) 35EAI 20AOBla) (1) I(rl 50.73(el(1) (4) 50,73( ~ ) (2)(r(II)(B) 20.405(e) lt l(r) 50.73(a I (110((l 50,73( ~ ) (2((x)

LICENSEE CONTACT FOR THIS LER (12I NAME TELEPHONE NUMBER AREA CODE Thomas R. Bradish, (Actin ) Compliance Manager 6 02 39 3- 25 21 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

XB. o r r, Sc 96xccT CAUSE SYSTEM MANUFAC. EPORTABL'E ic'41 ~ 'OMPONENT MANUFAC. EPORTABLE P

COMPONENT TURER TO NPROS c 4 .v CAUSE SYSTEM TURER TO NPROS +, 6 Mrr .Exk SUPPLEMENTAL REPORT EXPKCTKD l(4) MONTH OAY YEAR EXPECTED SUBMISSION DATE HSI YES (If yrr, comoirtr EXPECTED SVEhrISSION DATEI NO ABSTRACT (Limit to 1400 rprcrr, ir., roproiimrtrly fifteen u'nplr rprcr ryprrrn'ttrn linn( (151 On March 10, 1989, at approximately 2200 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at approximately 100 percent power when a Ghemistry Effluent Technician (contractor, non-licensed) discovered that the Preplanned Alternate Sampling System (IL) for the Plant Ventilation was inoperable. The circuit breaker, which supplies the electrical power (EC), had opened and deenergized the alternate system. With the alternate sampling inoperable, Unit 2 operated in a condition contrary to Technical Specification (TS) 3.3.3.8. At approximately 2210 MST,, the power to the Preplanned Alternate Sampling System power was restored. No safety system responses occurred and none were necessary.

The cause of the event was electrical loads in excess of the circuit capacity resulting in the circuit breaker which supplied electrical power opening. A Design Modification has been issued to supply dedicated power to these loads..

Similar events were reported in LER 529/87-14, 529/88-13, 530/88-07, and 528/89-03.

NRC F orm 355 (559)

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NRC FORM 366A ILS. NUCLEAR REGULATORY COMMISSION

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(SJ(9( APPROVEO OMS NO. 31500104 EXPIAES: 4/30/92 ESTIMATED SUAOEN PER AESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION AEQUESTI 500 HRS. FORWARD COMMENTS REGAROING SUAOEN ESTIMATE TO THE RECOROS TEXT CONTINuATION ANO RFPORTS MANAGEMENT SRANCH (P430I, U.S. NUCLEAR REGULATORY COMMISSION/WASHINGTON. OC 20555, ANO TO THE PAPERWORK REDUCTION PROJECT (3150410iI. OFFICE OP MANAGEMENTANO SUOGET,WASHINGTON, OC 20503.

FACILITYNAME I'l COCKET NUMSEA (21 LER NUMSEA (Sl PAGE LS)

YEAR SEaUENTIAL e IICV IS IO N NUMBER NUMQ ~ Il TKXT Palo Verde Unit 2 illma>> rl>>er *mewed. UJP PI/I/o'or>>l//RC %%dmI 35SAS/ (IT(

0 S,O 0 0" 5 298 '9 0 0 5 01 02 OF 0 6 I.. DESCRIPTION OF WHAT OCCURRED:

A. Initial Conditions:

On March,10, 1989 at approximately 2200 MST, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at approximately 100 percent power.

B. Reportable Event Description (Including Dates and Approximate Times of Major Occurrences):

Event Classification: Condition Prohibited by the Plant's Technical Specification (TS)

On March 10, 1989, at approximately 2200 MST, a Chemistry Effluent Technician (contractor, non-licensed) discovered that the Preplanned Alternate Sampling Program (PASP)(IL) for the Plant Ventilation (VL) was inoperable. The circuit breaker, which supplies the electrical power (EC), had opened and'eenergized the alternate system. With the alternate sampling system inoperable, Unit 2 operated in a condition contrary to TS 3.3.3.8.

Prior to. the event, on December 6, 1989 at approximately 0700 MST, the normal Plant Ventilation low and high range effluent monitors (RU-143 and RU-144)(IL) were decl'ared inoperable due to intermittent spiking of the low range detector (RU-143).

Appropriate actions were initiated in accordance with approved procedures'he'se actions included the installation of the Preplanned Alternate Sampling System on a portable cart within one hour in accordance with TS 3.3.3.8 ACTION 37 and.40. The alternate sampling system. taps into the Plant vent and utilizes a particulate and charcoal cartri'dge for sample collection with an in-line flow gauge and sampling pump. The alternate sampling system is electrically powered from a local outlet. ~

Following the installation of the alternate sampling system, the process and sample flow rates were verified a minimum of every four hours pursuant to TS 3.3.3.'8 ACTION 36. On March 10, 1989, at approximately 2005 MST, a process and alternate sampling system flow check was performed. At this time, the alternate sampling system was energized and operable.

During, conduct of a PASP cart flowrate check at approximately 2200 MST, a Chemistry Technician (contractor, non-licensed) discovered that the PASP sample cart had lost power. The Chemistry Technician started a portable electric generator and restored NRC Form 366A 1669(

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L, NRC FOAM SSSA ILS. NUCLEAR REGULATORY COMMISSION (889) APPROVED OMS NO. 3)500104 EXPIRES: 8/30/92 LICENSEE. EVENT REPORT (LER) ESTIMATED 8URDEN PEA RESPONSE TO COMPLY WTH THIS INFOAMATION COLLECTION REQUEST: SOB) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT8RANCH IP430), U.S. NUCLEAR REGULA'TORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERwoRK AEDUGTIDN PADJEGT 13)504104). DFF)cE.

OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20M3.

FACILITYNAME Ill DOCKET NUMSEA 12)

LER NUMSER (51 PAGE ISI YEAR err SEQUENTIAL :oYg RtVdlON NUMttR NUMetR Palo Verde Unit 2 ,o s o o o 52 989 0 0 5 0 1 03 ot'06 TEXT ///more epooe ie nqcwerL rue //too'o/ JVRC Form 35849/ I)7) power to the sample cart at approximately 2210 MST; At approximately 2220 MST, the Chemistry Technician notified the ~

Shift Supervisor (utility, licensed) of the loss of power to the sample cart. The Shift Supervisor dispatched an Auxilia+

Operator (utility, non-licensed) to reset the electrical breaker that supplied the affected outlets; and this was accomplished at approximately 2230 MST. The Chemistry Technician then transferred the power supply back to the normal outlet.

C'. Status of structures, systems, or components that were inoperable at the start of the event that contributed to the event:

As stated in,Section I.B, the. Plant Ventilation Radiation Monitors, RU-143 and RU-144 were inoperable for corrective maintenance. No other structures, system, or components were inoperable at the start of the event that contributed to the event.

D. Cause of each component or system failure,, if known:

Not applicable - no component or system failures were involved.

However, as stated in Section I.B, electrical power to the alternate sampling system was interrupted when the circuit breaker opened.

E. Failure mode, mechanism, and effect of each failed component, if known:

Not applicable - no failures were noted.

F. For failures of components with multiple functions, list of systems or secondary functions that were also affected:

Not applicable - no component failures were involved.

G. For failures that rendered a train of a safety system inoperable, estimated time elapsed from the discovery of the failure until the trains were returned to, service:

Not applicable - no failures were involved. However, the alternate sampling system was discovered inoperable on March 10, 1989 at approximately 2220 MST. The alternate sampling system was made operable at approximately 2210 MST. The total elapsed time was approximately 10 minutes.

N AC Forro 35SA )589)

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(549)

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NRC FORM 366A LICENSEE EVENT REPORT, CONTINUATION NUCLEAR REGULATORY COMMISSION IL'ER)'EXT INFORMATION APPROVEO OMS NO. 3(504104 EXPIRES: 4/30/92 ESTIMATED'SURDEN PER RESPONSE TO'COMPLY'WTH THIS COLLKCTION REQUEST: 500 HRS. FORWARD COMMENTS REGARDING SURDEN ESTIMATE TO THE REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK .REDUCTION PROJECT (31504104). OFFICE OF MANAGEMENTAND 6 UDG ET, WASHINGTON, DC 20503; RECORDS'ND FACILITYNAME (I) DOCKET NUMBER (2) LER NUMSER (6) PAGE (3) 66004NWAI. r)6YISrorr YEAR ~WC rrUM66R i+g. NUM664 Palo Verde Unit 2 o's o o,o:52 9 89 ,0 05' 01 0 4. QF

'06'EXT lllmore spece /4 reFr/'rer/ use er/r/iriorre/HRC Forrrr 3654'sl (17).

H. Method'f discovery of each c'omponent or system failure or procedu'ral'rror:

r Not applicable - no -component or system -failures or, procedural errors w'ere involved.

Cause of Event:

r The root cause of the event was. temporary and permanent el'ectrical loads in excess of the .circuit capac'ity. In response. the circuit.

breaker opened and caused a loss of electrical power to: the alternate sampling system. Without electri.'cal power, the sampling pump can not draw a, sample from the Plant Ventilation.

Safety System Response:,

Not applicable - no safety'syste'm responses occurred'nd none were.'ecessary.

7 K. Failed Component Informati:on:

Not applicable - no component failures were involved.

ASSESSMENT OF THE SAFETY CONSEQUENCES AND IMPLICATIONS. OF THIS EVENT:

No adverse safety consequences or implications, resulted from this, event.

The alternate system was determined to be inoperable for up to one hour and 55 minutes. Upon discovery of'he loss. of power, the"alternate sampling system power was restored within, approximately ten minutes.-

The TS 3.3.3.8 ACTION 40 permits 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to install the alternate sampling system. No significant radiation levels were measured before or after'the event.

III. CORRECTIVE ACTIONS A. ,Immediate Power was restored to the alternate sampling, system.

B. A'ction to Prevent Recurrence:

A Design Modification has been issued to supply dedicated power to the sample cart in all three units. Implementation of the design modification in Units 1,, 2, and 3 is expected by September 1990.

NRC Form 366A (549)

t NRC FORM 3SSA US. NUCLEAR REGULATORY COMMISSION (B49) OMB NO. 31504104 ESI A/30192 CONTINUATION'PPROVED

'XPIR ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EYENT REPORT ILER) INFORMATION COLLECTION"REOVESTI 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT ANO,REPORTS MANAGEMENT BRANCH IP430), V.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 13)504105). OFFICE OF MANAGEMENTAND BUDGET,WASHINGTON. DC 20503:

FACILITY NAME (11 DOCKET NUMBER (2l LER NUMBER (Sl PAGE (3)

OUf NTIAL YEAII ~<> 55 NUMSf  ? SE REVISION R lliUMOfR Palo Verde- Unit 2-'- o 6 o.o o 5 29 89 .00 5 0 1 05 OF 0 TEXT (JF mere TP¹eo lf reeM'rfd, IrJO eddreenar WRC Femr 3SSAYJ ()7)

As interim, corrective action while awaiting the plant. change, power has been supplied to the PASP sample carts from a welding outlet to minimize the possibility of an overload condition when RU-141 (condenser Air Removal Exhaust Radiation Monitor) or RU-143 (Plant Ventilation Exhaust Radiation Monitor) are inoperable.

Additionally, when RU'-141 or RU-143 are inoperable, the PASP sample. cart is electrically powered such that a loss of this power will provide an alarm in the- Control Room; IV. PREVIOUS -SIMILAR EVENTS':

Four previous events have occurred which are similar to the event:

LER 529/87-014 described an event where the alternate sampling system for the Fuel Building Ventilation Radiation Monitor (RU'-145) had been turned off and rendered inoperable. As corrective action to prevent recurrence, a placard was installed on the cart which identifies the cart as a Technical. Specification piece of equipment. Since the event described in this LER involves the, overloading and subsequent tripping of the power supply breaker, the corrective action described in LER 87-014 would not. have prevented the event described in this LER.

2) LER'29/88-013 described an event where the .alternate sampling system for Normal Plant Ventilation Radiation Monitor (RU-143) had

.been rendered inoperable. when the circuit breaker opened. As corrective action to prevent recurrence, an Engi'neering Evaluation Request was issued to evaluate the feasibility of supplying alternate .power to the loads. This evaluation had progressed to the point of a conceptual study when this event occurred and thus, did. not pr'event the event.

3) LER 530/88-007 described an event where the alternate sampling system for the Condenser Vacuum Pump/Gland Seal Exhaust'Radiation.

Monitor (RU-141) became electrically disconnected from a nearby electrical outlet and thus, rendered inoperable. As action to the involved individual was counseled, 'reventrecurrence,

'additional training was performed, and enhanced labeling for the sample cart was developed. Additionally, an evaluation was initiated to upgrade the installation of the sample cart. The evaluation discussed is part'of the conceptual'tudy discussed as corrective action in Section III.B of this LER.. Installation of these upgrades would not have prevented the event described in this LER. Also, counseling, training, and'abeling would not have prevented the event discussed in this LER.

N RC Fono 35SA (ILS9)

il 0 NRC50RM355A (LS. NUCLEAR REGULATORY. COMMISSION (5491 APPROVED OMB NO.

3150d104'XP(RES:

e/30192-

.ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH'THIS LICENSEE EVENT REPORT INFORMATION COLLECTION REQUEST: 50AI HRS. FORWARD COMMENTS REGAROINQ BURDEN ESTIMATE TO THE RECORDS (LER)'EXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH (P-5301, U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3(5001041, OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, OC 20503.

FACILITYNAMC (11 DOCKET NUMBER (2) (.ER NUMBER (51 PAGE YEAR rg@ CCQVCNTIAI, NVMSCR jj% RCVNKIN 5 NVMCCR (31'alo Verde Unit 2 o-s o o o 52 9 89 00 5 01 0 6 o" 0 -6 TEXT (ifmove epeoe ie eovvv'ved, we edve'v(ovve(NRC Fomv 36SASU (IT(

4) LER 528/89-003 described'n event where the alternate sampling system for the Fuel Building Exhaust Radiation Monitor (RU-145) became. inoperable when the circuit breaker opened. As corrective action to prevent recurrence, a Design Modification had been issued to supply dedicated power so the sample care.

Implementation of'his- change is expected by September 1990.

Since this change has not been installed in the unit, it. did not prevent this event.

NRC Fovm 355A (5091

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