ML17304B068

Special Rept 3-SR-89-002:on 890303,electrical Grid Disturbance Occurred,Causing Fault Near Devers,Ca Switchyard & Opening of Main Generator Output Breakers.Low Pressure Reactor Trip & Main Turbine Trip Also Occurred

ML17304B068
Person / Time
Site:	Palo Verde
Issue date:	03/08/1989
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
192-00455-JGH-T, 192-455-JGH-T, 3-SR-89-002, 3-SR-89-2, NUDOCS 8903210135
Download: ML17304B068 (8)

Text

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ACCESSION NBR:8903210135 DOC.DATE: 89/03/08 NOTARIZED: NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530,,

AUTH. NAME AUTHOR AFFILIATION HAYNES,J.G. Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Special Rept 3-SR-89-002:on 890303,complete loss of offsite power to implant non-class lE electrical busses occurred.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES:Standardized plant. 05000530 ~

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME 'TTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 DAVIS,M.J. 1 1, DAVIS,M 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE AEOD/DS P/TPAB ARM/DCTS/DAB 1

1 1

1 1

1 AEOD7 DOA AEOD/ROAB/DSP DEDRO 2,2 1

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4 4 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 I NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NOTES: 1 1 D

NOTE 'IO ALL "RIDS" RECIPZEÃIS:

S PIZASE HELP US TO REDUCE WASTE! CONI'ACI'IHE DOCUMENI'ONI'ROL DESK, ROOM Pl-37 (EXT. 20079) K) ELQ62ihTE YOUR NAME FKR DISTIGBVTION LXSTS FOR DOCUMEÃZS YOU DON'T NEED>

TOTAL NUMBER OF COPIES REQUIRED: LTTR 47 ENCL 46

Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00455-JGH/TDS/DAJ March 8, 1989 U. S. Nu'clear Regulatory Commission NRC Document Control Desk Washington, D.'C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

'Unit 3 Docket No. STN 50-530 (License No. NPF-74)

Special Report 3-SR-89-002 File: 89-020-404 Attached please find Special Report 3-SR-89-002 prepared and submitted pursuant to Emergency Plan Implementing Procedure -03. This report discusses a NOTIFICATION OF UNUSUAL EVENT due to a complete loss of offsite power to'he non-class. in-house electrical busses and a safety injection actuation.

If you have any questions, please contact T. D. Shriver, Compliance Hanager at (602) 393-2521..

Very truly yours, Vice President Nuclear Production JGH/TDS/DAJ/kj

. Attachment CC: D. B. Karner (all w/a)

J. B. Hartin T. J. Polich H. J. Davis A. C. Gehr INPO Records Center R. T. Hilstead C. F. Tedford F. L. Russo R. Godbehere R. Colson ~pNP iI

yl Palo Verde Nuclear Generating Station Unit 3 Notification of Unusual Event Docket No. 50-530 License No. NPF-74 Special Report No. 3-SR-89-002 C

This Special Report is being provided pursuant to Emergency Plan Implementing Procedure (EPIP)-03, "Notification of Unusual Event Implementing Actions" to report the declaration of a Notification of Unusual Event (NUE) for Palo Verde Unit 3. The NUE was declared pursuant to EPIP-02, "Emergency Classification" as a result of a complete loss of offsite power to the in-plant non-class 1E electrical busses 3E-NAN-S01 and 3E-NAN-S02 and a safety injection actuation

resulting from low pressurizer pressure.

On March 3, 1989, Palo Verde Unit 3 was operating in Mode 1 (POWER OPERATION) at approximately 98 percent power and in-plant non-class 1E electrical components (including Reac'tor Coolant Pumps) were being powered by the Main Turbine Generator via the Unit Auxiliary Transformer. At approximately 0102 NS~ t Wg ddt the Devers, California switchyard.

h y t The electrical grid disturbance resulted in the main generator output breakers opening and a reactor power cutback.

During the reactor power cutback, the control system for four (4) of the eight (8) steam bypass control valves appears not to have operated properly which resulted in secondary pressure oscillations and an excessive steam demand.,

The excessive steam demand eventually resulted in a Steam Generator Number two (2) low pressure reactor trip, main turbine trip, and Hain Steam Isolation System (MSIS) Engineered Safety Features (ESF) actuation at approximately 0103 HST. Approximately six seconds after the reactor trip, Safety Injection and Containment Isolation ESF actuations occurred due to low pressurizer pressure., In accordance with approved procedures, two (2) Reactor Coolant Pumps (RCP's) were stopped. Following the Hain Turbine trip, a Fast-Bus Transfer did not occur per design and a loss of power to the in-plant non-class 1E electrical busses occurred. This resulted in the other two (2)

RCP's being deenergized.

As a result of the HSIS actuation, steam flow to the Hain Condenser was terminated. Attempts to remotely operate the Atmospheric Dump Valves (ADV's) were unsuccessful which resulted in the automatic actuation of one (1) Hain Steam Safety Valve (HSSV).

At approximately 0139 MST on March 3, 1989, a Notification of Unusual Event (NUE) was declared pursuant to EPIP-02, "Emergency Classification", due to the loss of power to the in-plant non-class IE electrical busses and the safety injection system actuation. At approximately 0149 MST on March 3, 1989 the appropriate state and local agencies were notified via the Notification and Alert Network (NAN). The Nuclear Regulatory Commission (NRC) Operations Center was notified at approximately 0203 MST on March 3, 1989.

At approximately 0232 MST on March 3, 1989, power was restored to 3E-NAN-SOl.

At approximately 0241 MST on March 3, 1989, the Safety Injection Actuation System was reset. At approximately 0243 HST on March 3, 1989, power was

0 Special Report 3-SR-89-002.

Page 2 restored to 3E-NAN-S02. As a result of restoring power to the in-plant non-class 1E electrical busses, the NUE was terminated at approximately 0252 MST on March 3, 1989.

The event did not result in any challenge to fission product barriers nor did the event .result in significant releases of radioactive materials. A Licensee Event Report will be submitted within 30 days of the event in accordance with 10CFR50.73.