ML17305B100

LER 90-003-01:on 900331,loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor Occurred.Caused by Personnel Error.Design Mod Issued to Install Dedicated Alternate Sample sys.W/900929 Ltr

ML17305B100
Person / Time
Site:	Palo Verde
Issue date:	09/29/1990
From:	Bradish T, James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
192-00694-JML-T, 192-694-JML-T, LER-90-003, LER-90-3, NUDOCS 9010150066
Download: ML17305B100 (16)

Text

ACCELERATED DIS UTION DEMONS ION SYSTEM REGULATORY LNFORMATION DISTRIBUTION SYSTEM (RIDS)

'ACCESSION NBR:9010150066 DOC.DATE: 90/09/29 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 AUTH. NAME AUTHOR AFFILIATION LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power BRADISH,T.R. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION NRC No Detailed Affiliation Given

SUBJECT:

LER 90-003-01:on 900331,loss of power to alternate plant ventilation effluent radiation monitor.W/900929 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR j ENCL i SIZE:

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

NOTES:Standardized plant. 05000529 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 PETERSON,S. 1 1 TRAMMELL,C. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEBlo 1 1 NRR/DOEA/OEABll 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR DST/SPLBSD1 1 1 NRR/DST/SRXB 8E 1 1 02 1 1 RES/DSIR/EIB 1 1 RGN5 FILE 01 1 1 EXTERNAL: EG&G BRYCE,J.H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MAYSgG 1 1 NSIC MURPHYgG.A 1 1 NUDOCS FULL TXT 1 -

1 NOTES: 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 35 ENCL 35

t Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION

'.O. BOX 52034 PHOENIX, ARIZONA85022-2034

~

192-00694-JML/TRB/RKR JAMES M, LEVINE Vt, E PRESIDENT September 29, 1990 I'iI 'E4+PRODUCTION U. S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station Pl-37 Washington, DC 20555

Dear Sirs:

Sub) ect: Palo Verde Nuclear Generating Station (PVNGS)

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

Licensee Event Report 90-003-01 File 90-020-404 Attached please find Supplement Number 1 to Licensee Event Report (LER) No.90-003 prepared and submitted pursuant to 10CFR50.73. This report is being submitted to update the schedule date for implementing a design modification.

The schedule is being revised due to material delays. In accordance with 10CFR50.73(d), we are 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 Manager at (602) 393-2521.

Very truly yours, A

JML/TRB/RKR/dmn Attachment CC: W. F. Conway (all with attachment)

J. B. Martin D. H. Coe A. C. Gehr A. H. Gutterman INPO Records Center

'7010150066 90092'V PDR ADOCI< 05000529 B PNU i!

)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (689) APPROVED OMB NO. 3(504H04 EXPIAESr 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD

'ICENSEE EVENT REPORT {LER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P630), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) PA E 3 Palo Verde Unit 2 0 5 0 0 05 29 1 OF07 TITLE (4)

Loss of Power to Alternate Plant Ventilation Effluent Radiation Monitor EVENT DATE ISI LFR NUMBER (6) REPORT DATE It) O'THER FACILITIES INVOLVED ( ~ I DAY YEAR SEQUENTIAL REVSrON DAY YEAR FACILITYNAMES DOCKET NUMBER(s)

MONTH YEAR gg NUMBER vvcP NUMBErv MONTH N/A 0 5 0 0 0 0 3 3 1 90 90 0 0 0 9 2 9 9 0 N/A 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR g: (Check one Or more oi the Ioiiowinpi (lll MODE (9) N 20A02(B) 20.405 I c l M.73(sl(2) livl 73.71(B) ill(ill)

POWER 20A05(sHIHI) 5046(cHI) 50.73(s)(2Hv) 73.71)cl LEVEL p p p 20.405 (s H I I (ill M.SB(cH2) 60.73(s) (2)(vBI OTHER ISrwcivy in Aortrect Beiow end In Text, HRC Form 20.405(s) 60.7 3 (v) (2 I (I) 50.73(sH2Hvii(HA) 3664/

20A05 (s) llI (iv) 50.7 3(s) (2)(ill 50,73(sH2)(vill)(B) 20.405(s) IIHv) 50.73 Is H2) (ill( 50,7 3( ~ l(2) I x )

LICENSEE CONTACT FOR THIS LER (12)

NAME TELFPHONE NUMBER AREA CODE Thomas R. Bradish, Com liance Mana er 6 023 3- 252 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13I MANVFAC. REPORTABLE MANVFAC EPOATABLE CAUSE SYSTEM COMPONENT TURER TO NPRDS fur)E(F+jPgr'wir SYSTEM COMPONENT TVRER TO NPADS 5/%I'.IY(gl>jgkgj

')[ANN!

SUPPLEMENTAL REPORT EXPECTED (14I MONTH DAY YEAR EXPECTED SV 6 M I S SION DATE I15)

YES III ym, COmPiete EXPECTED SIIBMISSIDH DATE/ NO ABsTRAGT ILimit to Ie(ID rpecer, I ~ ., epproximetery fiireen rinpie rptce typewritren liner/ (161 Ae approximately 1230 MST on March 31, 1990, Palo Verde Unit 2 was in a refueling outage with the reactor core offloaded to the Spent Fuel Pool when a Chemistry Effluent Technician and the Control Room Shift Supervisor discovered thae the Preplanned Alternate Sampling Program (PASP) portable sample. cart for the Fuel Building Ventilation had been inoperable. At approximately 0620 MST on March 31, 1990, the load center supplying power to the PASP poreable sample cart had been deenergized for a preplanned electrical outage. When ehe load center was deenergized, it was not recognized that it supplied power to the PASP portable sample cart. At approximately 0840 MST on March 31, 1990, the PASP portable sample cart was returned to OPERABLE status'ith the PASP portable sample cart inoperable for approximately ewo hours and twenty minutes, Unit 2 operated in a condition contrary to Technical Specification 3.3.3.8.

The cause of the event was a personnel error due to inadequate ideneification of the loads on the load center prior to deenergization.

As corrective action a Design Modification has been issued to install dedicated alternate sample systems to radiation monitors RU-141, RU-143 and RU-145.

Similar events were reported in LERs 529/87-14, 529/88-13, 530/88-07, 530/89-03, and 529/89-005.

NRC Form 366 (64)9)

NAC FORM 366A U.S, NUCLEAR REGULATOAY COIAMISSION APPROVED 0MB NO.31500)06 (669)

E XP I R E S: 6/30/92 ESTIMATED BUADEN PEA RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION AEOUESTI 60.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWOAK REDUCTION PROJECT (31600106), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITYNAME (ll DOCKET NUMBER (2) LER NUMBER (6) PAGE IS)

YEAR IY<E SEQUENTIAL REVISION CRLA NUMBER NUMBER Palo Verde Unit 2 0 5 0 0 0 0 1 QF 0,7 TEXT ///moro s/rooo /s Tor/or)od. Boo Edd'I/os/VRC Fcnn 356AB/ Ill)

DESCRIPTION OF WHAT OCCURRED:

A. Initial Conditions:

At approximately 0620 MST on March 31, 1990, Palo Verde Unit 2 was in a refueling outage with the reactor core (AC) offloaded to the Spent Fuel Pool (ND).

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

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

At approximately 1230 MST on March 31, 1990, a Chemistry Effluent Technician (utility, non-licensed) and the Control Room Shift Supervisor (utility, licensed) discovered that the Preplanned Alternate Sampling Program (PASP)(IL) portable sample cart for the Fuel Building ventilation (VL) had been inoperable. The power supply for the PASP portable sample cart had been deenergized for a preplanned electrical outage at approximately 0620 MST on March 31, 1990. The power supply was reenergized at approximately 0802 MST. Prior to the event discovery, at approximately 0840 MST on March 31, 1990, the PASP portable sample cart flow had been verified to confirm proper operation. With the PASP portable sample cart inoperable for approximately two hours and twenty minutes, Unit 2 operated in a condition contrary to TS 3.3.3.8.

Prior to the event, at approximately 1700 MST on March 23, 1990, the Fuel Building Ventilation System Low and High Range Radioactive Gaseous Effluent Monitors (RU-145 and RU-146)(MON)(IL) were removed from service when their power supply was deenergized for scheduled maintenance during the refueling outage. This was reported in Special Report 2-SR-90-001 dated April 12, 1990, in accordance with TS 3.3.3.8 ACTION 42b and TS 6.9.2. Approp'riate actions were initiated in accordance with approved procedures.

These actions included the installation of the PASP portable sample cart within one hour in accordance with TS 3.3.3.8 ACTIONS 37 and 40. The portable sample cart taps into the Fuel Building ventilation and uses a particulate and charcoal cartridge for sample collection with an inline flow gauge, and sampling pump.

The portable sample cart is electrically powered from a local outlet. The Portable Area Monitor (PAM) was also installed. The PAM is located on the Fuel Building roof to monitor the Fuel Building Ventilation discharge pipe. The output from the PAM is connected to the Radiation Monitoring System (RMS) minicomputer NAC Form 366A (549)

J' NRC FORM356A U.S. NUCLEAR REGULATORY COIAMISSION APPROVED OMB NO. 31500104 (64)9)

EXPIRES: 4/30N2 ESTIMATED BURDEN PER RESPONSE TO COMI'LY WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REOUESTI 500 HRS. FORWARD COMMFNTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON. DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON. DC 20503.

FACILITY NAME <I) DOCKET NUMBER (2) LER NUMBER LB) PAGE (3)

YEAR +mg+ SEOVENTIAL NOMSER

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'E REVISION NVMSER Palo Verde Unit 2 o s o o o 529 90 003 01 03>>0 TEXT lllmoro Jaooo B ror)rrr)od, o Jo rddrTI rmol ill)C Farm 36643) (17)

(CPU)(IL) in the Chemistry Lab. The PAM is also powered from a local outlet.

Following the installation of the portable sample cart, the process and sample flow rates were verified a minimum of every four hours pursuant to TS 3.3.3.8 ACTION 36. At approximately 0615 MST on March 31, 1990, a portable sample cart flow check was performed. At that time, the portable sample cart was energized and operable. At approximately 0620 MST on March 31, 1990, a non-class IE 480 Volt load center (NGN-L17)(XFMR)(EC), which normally supplies nonessential lighting and outlets, was deenergized to permit connection of a temporary power supply to allow its normal power supply to be deenergized for a preplanned electrical outage.

The load center was providing power to the local outlets for the portable sample cart and PAM. During the next scheduled tour, at approximately 0711 MST, a Chemistry Effluent Technician discovered that the PAM was not operating and notified the Control Room Shift Supervisor (utility, licensed).

At approximately 0750 MST while investigating the PAM inoperability, the Chemistry Effluent Technician discovered that the PAM was deenergized and notified the Control Room Shift Supervisor. The Control Room Shift Supervisor determined that the PAM was inoperable due to its load center being deenergized. At approximately 0802 MST, the PAM was returned to service when the load center was reenergized. The PAM had been inoperable from approximately 0620 MST to approximately 0802 MST on March 31, 1990, a period of approximately 1 hour and 42 minutes. The PAM was not required to be OPERABLE during this time period to meet TS requirements.

At approximately 1230 MST on March 31, 1990, while reviewing the loads supplied by the load center, the Chemistry Effluent Technician and the Control Room Shift Supervisor discovered that the portable sample cart was powered by the same load center as the PAM. Prior to this discovery, at approximately 0840 MST on .

March 31, 1990 (after the load center had been reenergized),

proper operation of the portable sample cart flow had been verified during the regularly scheduled surveillance. The portable sample cart was inoperable from approximately 0620 MST to 0840 MST on March 31, 1990, for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes. This is contrary to TS 3.3.3.8 ACTION 40 which requires that "effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment".

NRC Form 366A (669)

<Be9)

'S.

NRC FORM 36LA FACILITYNAME (I)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION NUCLEAR AEGULATORY COMMISSION DOCKET NUMBER (2I APPROVEO OMS NO. 31504))04 E XP I R E 6: 4/30R)2 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 600 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPOATS MANAGEMENT BRANCH IP430), U.S. NUCLEAA REGULATORY COMMISSION, WASHINGTON, OC 20555, ANO TO THE PAPERWORK REDUCTION PROJECT (31604)104). OFFICE OF MANAGEMENTAND BUDGET. WASHINGTON,DC 20503.

YE*A LER NUMBER (6) xe sEOUENTIAL @s AEvrsION NUMSSII ~ .: NUM Srl PAGE (3)

BF mars spscs Js Palo Verde Unit rsr)rrr'rsd, Irss 4ddr'drNrss JS 2'EXT RC Farm 3554'sl (IT) 0 5 0 0 0 003 oF 0 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 Fuel Building Ventilation System Radioactive Gaseous Effluent Monitors, RU-145 and RU-146, were inoperable due to deenergization of their power supply for scheduled maintenance during the refueling outage. The PASP portable sample cart and PAM became inoperable as described in Section I.B. No other structures, systems, 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.

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

Not applicable - no failures were noted.

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

Not applicable - no component failures were involved.

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

Not applicable - no failures were involved.

H. Method of discovery of each component or system failure or procedural error:

Not applicable - no component or system failures or procedural errors were involved.

Cause of Event:

The cause of the event was a personnel error (SALP Cause Code A) by chemistry personnel (utility, non-licensed). Interim corrective action from a previous similar event (LER 529/89-005) required that PASP equipment be electrically powered such that a loss of power would provide an alarm in the control room.

Preplanned bus outages during the refueling resulted in loss of power to several radiation monitors. In accordance with TS ACTION NRC Form 366A <64)9)

NRC FORM 366A U.S. NUcLEAR REGULATDRY colrIMIssloN (SBB)" APPROVED OMB NO. 31604)04 EXPIRES: O/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPI.Y WTH THIS LICENSEE EVENT REPORT ILER) INFORMATION COLLECTION REOUESTI 600 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH (F430), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 30666, AND TO THE PAPERWORK REDUCTION PROJECT (31600104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 30603.

FACILITYNAME (I) DOCKET NUMBER (3) LER NUMBER (8) PAGE 13)

SEQUENTIAL Nx: REVI5ION YEAR 'NUMBER 'I'II NUMBER Palo Verde Unit 2 TEXT ///moro J/rooo/1 roOIrwod. Pro oddrO'Pool//RC Form 31)SrEB/(IT) 05000529 9 0 003 01 05 QF 0 7 requirements, PASP equipment was placed in service to provide alternate sampling for the monitors out of service. Since the alarm computer in the control room could not accept all of the alarms, the alternate sample cart for Radiation Monitor RU-145 was not connected to the alarm computer in the control room. Other higher priority PASP equipment was connected instead.

Since the PASP equipment could not be connected to the alarm computer, chemistry personnel should have taken additional action and notified the control room that the PASP equipment was being supplied from a specific outlet and that additional measures were required to prevent a loss of power to the PASP equipment (e.g.,

caution tag power supplies for the PASP equipment). Chemistry personnel did not inform the control room which electrical outlets were supplying power to the PASP equipment resulting in operations personnel (utility, licensed) not performing an adequate review of the loads on the non class 1E load center prior to deenergizing the load center. There were no administrative controls which recommended that chemistry personnel inform the control room which outlets were supplying power to the PASP equipment. There were no unusual characteristics of the work location that directly contributed to this event.

Safety System Response:

Not applicable - no safety system responses occurred and none were necessary.

Failed Component Information:

Not applicable - no component failures were involved.

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

The portable sample cart was determined to be inoperable for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes. There was no fuel movement or crane movement over the spent fuel pool during this event. The Fuel Building Area Radiation Monitors (RU-19 and RU-31) did not indicate any change in radiation levels during this event. The PASP sample from the portable sample cart and the PAM did not indicate any significant radiation levels prior to and after this event. Therefore, there were no safety consequences or implications as a result of this event. This event did not adversely effect the health and safety of the public.

NRC Form 366A (SBB)

II NRC FORM 36SA US, NUCLEAR REGULATORY COIAMISSION I669) APPAOV EO OMB NO. 31500104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT {LER) INFORMATION COLLECTION REQUEST: 600 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION ANO REPORTS MANAGEMENT BRANCH (P4)30). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPFRWORK REDUCTION PAO/ECT (31504)104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (I) DOCKET NUMBER (2) LER NUMBER LE) PAGE (3)

YEAR Rdo) 564UENTIAL g<< REvlsloN NUMBER or:.i'VMOOR Palo Verde Unit 2 0 5 0 0 0 5 2 9 90 00 3 01 06 oFo TEXT //I moro 4Oooo /4 ioOII/rod, ooo oddrr/ono////IC Fono 36543/ ()Tl III. CORRECTIVE ACTIONS:

A. Immediate:

Power was returned to the alternate sampling system and PAM.

B. Action to Prevent Recurrence:

1. A Design Modification has been issued to install dedicated alternate sample systems to radiation monitors RU-141, RU-143 and RU-145. The alternate sample systems will be supplied by dedicate'd power. Implementation of the design modification in Units 1, 2, and 3 was originally expected to be completed by September 30, 1990, however due to material delays the modification is expected to be completed by December 1990.

2. The RMS Sample Collection Procedure for all three units has been changed to require that when PASP equipment cannot be connected to the alarm computer in the control room, chemistry personnel inform the control room which electrical outlets PASP equipment is powered from and request that the power supplies for the PASP equipment (when it is in use) be caution tagged to alert personnel that Technical Specification required equipment is connected to these power supplies.

IV. PREVIOUS SIMILAR EVENTS:

Five previous events have occurred which are similar to this 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 Technical Specification required equipment. Since the event described in this LER involves deenergizing the power supply for the PASP equipment, the corrective action described in LER 87-014 would not have been expected to prevent the event described in this LER.

2. LER 529/88-013 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 Engineering Evaluation Request was issued to evaluate the feasibility of supplying alternate power to the loads. Based on this evaluation, a design modification was issued to supply dedicated power to the alternate t NRC Form 366A (669)