ML20127B217

Forwards AEOD Input for Commissioner Curtiss Visit to Plant on 900201,consisting of Summary of Operating Experience from Oct 1988 to Dec 1989

ML20127B217
Person / Time
Site:	Palo Verde
Issue date:	01/18/1990
From:	Novak T NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20127B172	List: ML20127B168 ML20127B217 ML20127B507 ML20127B567
References
FOIA-92-88 NUDOCS 9001240375
Download: ML20127B217 (18)

Text

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MEMORANDUM FOR:

Roy Zinnerman. Director Division of Reactor Safety and Projects l

Region V FROM:

Thomas M. Novak Director Division of Safety Programs Office for Analysis and Evaluation of Operational Date

$UBJECT:

AEOD IMPUT FOR COMMi$$10NER CURTIS$' V:$1T T0 PALO VERDC NUCLEAR PLANT ON FEBRU/.RY 1, 1990 Enclosed is the AE00 input to the briefing package for Comissioner Curtiss' visit to the Palo Verde Nuclear Power Plant on February 1.1990. Our input includes a sumary analysis of operational experience at Palo Verde from October 1.1988 through December 1989.

If you have any questions or need additional inforsation please contact Neill Thomasson of g staff at FTS 492-4431 orJackCrooksat 492-4425.

Thomas M. Novak, Director Division of Safety Programs Office for Analysis and Evaluation-of Operational Data

Enclosure:

As stated cc w/encle W. Ang. Region V R. W. Borchardt. DEDRO t_ ([)

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Review of operational Experience for Commissioner Curtiss's Visit to Palo Verde Nuclear Power Plant Statust January 1, 1990 l

I Division of safety Programs Office for Analysis and Evaluation of Operational Data C O ct GOCCNW-DMNsn m-My s o a O T - 08

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Summary of operational Experience at Palo Verde Nuclear Power Plant October 1, 1988, through December 1989 I.

Overview A diagnostic evaluation of the Palo Verdo plan is in process.

The onsite evaluation occurred November 6-17 and December 4-8, The evaluation is intended to supplement information from 1989.

the Systematic Assessment of Licensee Performance (SALP) program, the Performance Indicator (PI) program, and other assessment j

data.

Based on AEOD screening criteria, AROD has thus far identified i

five events as important during the review period -- one at Unit i and two each at Units 2 and 3.

Through September 1989, the PI program categorized two events at Unit 3 as significant.

Root causes for the LERs were dominated in descending order by maintenance errors (half related to surveillance and testing) and and installation errors.

Inadequate administrative design control and errors by "other personnel" than licensed operators were the other notable event causes.

The bulk of the maintenance and administrative control errors were about equally distributed between Unit 1 and Unit 2.

Each unit experienced multiple events related to potential maintenance problems and design and installation problems; the latter were the dominant causes at Unit 3.

During the period, six unplanned scrans from power occurred --

one at Unit 1, four at Unit 2, and one at Unit 3.

Unit 2, which restarted on June 29, 1989, has experienced two scrams since March 3, 1989, when all three units were shut down following an event that led to an AIT.

The other units have yet to restart.

During the period 15 events with unplanned engineered safety featurs (ESP) actuations occurred. Overall four personnel errors (two licensed operator errors and two technician errors),

one procedure problem, and six equipment problems were associated with these events; four were related to unknown or other factors.

II.

Abnormal occurrencta Between October 1, 1988, and January 1, 1990, no events were classified as Abnormal Occurrences (AO) nor were any candidates for Appendix C (Other Events of Interest) to the Ao reports.

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III. Q_ther Operational Data hiagnostic EvalugL11.QD A diagnostic evaluation of the Palo Verde plant is in process.

Field activities were conducted on November 6-17 and December 4-The evaluation is intended to supplement information 8,

1989.

from the SALP program, the PI prograte, and other assesement data.

The decision to conduct the evaluation resulted from a recent meeting of NRC Senior Managers.

The decision was based on concerns regarding plant performance problems at Palo Verde and their management and organizational changes.

A final report is scheduled to be issued in February 1990.

LER Revigya Based on the AEOD LER screening criteria, five events were classified as important events and are summarized as follows:

LER 528/89-005 (4/12/89)t Atmospheric Dump Valve deficiencies.

(This involved a safety system failure).

LER 529/89-001 (1/3/89):

Loss of power to the Class 1E 4.16 XV busses caused an ESP actuation.

LER 529/89-009 (7/12/89):

Partial loss of forced flow to the reactor caused a reactor trip.

LER 530/89-001 (3/3/89):

Inability to remotely or manually operate the atmospheric dump valves caused a reactor trip due to low steam generator level.

(This event resulted in an AIT, and was also a PI significant event.)

LER 530/89-007 (5/3/89):

Potter and Bromfield relay malfunctions.

(This involved a safety system failure.)

glanificant Eventa The two events identified as significant events in the PI program Unit 3 had the March 3,1989, event (LER 530/89-are as follows:

001) involving f ailure of the atmospheric dump valves and other equipmant thtt resulted in an AIT report (EA-89-88, April 19, 1989).

The causes f or the event were maintenance, operator and equipnent failure.

The AIT found the event

errors, symptomatic of "...managemont's failure to set a standard which Unit 3 demands that plant problems be recognized and fixed."

a significant event on September 6,

1989, When the also had licensee discovered improperly set ring settings on the steam safety valves during the Unit 3 refueling outage (see EN 16513).

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3 Uncianned Reactor ScrAmA Unit i had an unplanned scram from power on March 5, 1989, in the event described in LER 528/89-004; following this scram, the plant has remained shutdown as a consequence of the AIT event at Unit 3 and for refueling.

One scram Unit 2 experienced four unplanned scrams from power.

occurred on November 16, 1988 (LER 529/88-014) ) when the feed speed control was set too lov for plant conditions, pump resulting in a low steam generator level, and a second scram occurred February 16, 1989 (LER 529/89-003) when the feedwater regulating valve controller stuck, causing a low steam generator On July 12, 1989 (LER 529/89-009) a scram resulted from level.

a deenergized 13.8 KV bus, while the most recent scram on October 31, 1989 (LER 529/89-010) was a result of an erroneous input to the coro protection calculator from an excore detector.

had one unplanned scram from power during the March 3, Unit 3 1989 AIT event (see LER 89-001).

Five of the scrams from power were caused by e.quipment and one by a procedural error.

Enaineored Safety Featura Actuations Fifteen events involving unplanned actuations of engineered safety features (EsFs) (other than scrams) occurred -- four at Unit 1,

four at Unit 2, and seven at Unit 3.

Four events involved the initiation of the emergency power system (EDG), but Five none of these resulted in actually loading the diesels.

actuations of the safety injection syntens occurred -- 3 HPSI and The March 2 LPSI, with coolant injected in three of the events.

3, 1989, event at Unit 3 resulted in the actuation of the containment spray system. Overall, the predominant ESF actuation involved the control room atmospheric control system, which occurred in 11 of the events. The auxiliary feedwater system was actuated four times, while the essential water system and the component cooling water systems were actuated in one event each at Unit 1.

(Note that an ESF event can result in multiple actuations of EsF systems; thus, the number of systems actuated exceed the number of events.)

the 15 events involved four personnel errors, five

Overall, equipment problems, one procedural problem, and five other causes including unknown and natural phenomena.

Maintenance or troubleshooting activities vero associated with four of the ESF actuation events and testing was being done during two events.

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Egrformance Indienter Data Performance Indicator (PI) data extending through october 1989 are attached.

The PI safety system actuations are a specific HOTE:

subset of all ESF actuations -- energency core cooling systen actuations and emergency power (diesel generator) actuations in response to a dead bus.

O The PI data are through Septenbar 1989, whereas the scram and ESF actuation discussions in Section III include events through December 1989 as the data are available.

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