ML20044G230

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Insp Rept 50-302/93-11 on 930412-17.Violation Noted.Major Areas Inspected:Cricumstances Surrounding Three Minute Interruption in Operation of DHR Sys Due to Loss of 500KV Offsite Power Source That Occurred on 930408
ML20044G230
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 05/17/1993
From: Fillion P, Freudenberger, Holmesray P, Landis K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20044G221 List:
References
50-302-93-11, NUDOCS 9306020207
Download: ML20044G230 (11)


See also: IR 05000302/1993011

Text

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Report No.: 50-302/93-11

Licensee: Florida Power Corporation

3201 34th Street, South

St. Petersburg, FL 33733

Docket No.:

50-302

License No.: DRP-72

Facility Name: Crystal River 3

Inspection Conducted: April 12 - 17, 1993

Inspect r: I d_

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P. Holmes-R v, Senior Resident Inspector

Datd Signed

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Inspec or:

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pR. Fretidenberger, Resident Inspector

Date Signed

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IMT/93

Inspector

P.~Fillion , actor Inspector, RII

Date Signed

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Approved by: 4

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K. landis, Section Chief

Date Signed

Division of Reactor Projects

SUMMARY

Scope:

This special inspection was conducted by two resident inspectors and a region

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based inspector in the area of followup to operational events. The inspectors

addressed questions to determine the circumstances surrounding a three minute

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interruption in the operation of the decay heat removal system due to a loss

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of the 500kV offsite power source that occurred on April 8, 1993. Offsite

power remained available through the 230kV switchyard during the event.

Results:

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The loss of 500kV offsite power was the result of inadequacies in plant

procedures which constituted a' violation of NRC. requirements. The licensee's-

short term corrective actions were adequate. A root cause analysis was

underway at the time of the inspection. Long term corrective actions were to

be defined after completion of the root cause analysis. One violation was

cited:

VIO 50-302/93-11-01, Failure to establish an adequate procedure for

operation of the 500kV switchyard DC control power system (paragraph

4.6).

9306020207 930517

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REPORT DETAILS

1.

Persons Contacted

Licensee Employees

  • J. Alberdi, Manager, Nuclear Plant Operations
  • G. Boldt, Vice President, Nuclear Production
  • R. Davis, Manager, Nuclear Plant Maintenance
  • M. Fitzgerald, Supervisor, Nuclear Plant Systems Engineering
  • E. Froats, Manager, Nuclear Compliance
  • G. Halnon, Manager, Nuclear Plant Technical Support
  • B. Ilickle, Director, Nuclear Plant Operations

K, Lancaster, Superintendent, Nuclear Maintenance Work Controls

  • W. Marshall, Manager, Nuclear Plant Operations

W. Morgan, Field Supervisor, Substation Maintenance

  • S. Powell, Manager, Electrical Shop

W. 5tevenson, Supervisor, Shift Technical Assistants

  • J. Terry, Manager, Nuclear Plant Systems Engineering

Other licensee employees contacted during this inspection included

engineers, operators and technicians.

NRC Inspectors

  • P. Holmes-Ray, Senior Resident Inspector
  • R. Freudenberger, Resident Inspector
  • P. Fillion, Reactor Inspector, RII
  • Attended exit interview

Acronyms and initialisms used throughout this report are listed in the

last paragraph.

2.

Background and Inspection Plan

Crystal River 3 had four reportable events involving degraded offsite

power between March 13 and April 8,1993 (Reference EN 25241, 25273,

25325, and 25377). The most recent event occurred while performing

maintenance on the 500kV DC control power battery. The resident

inspectors, augmented by one Region II based electrical engineer, .

evaluated the root cause of this event and corrective actions.

In

addition, the most recent loss of power event was evaluated in terms of

similarity to current events at other sites and other non-reportable

switchyard events at Crystal River during the maintenance shutdown. The

evaluations were accomplished by addressing the following inspection

elements which were prepared by NRC management:

a.

Independently assess management oversight and effectiveness in

accurately determining the root cause for the loss of 500kV

offsite power event.

b.

Determine the technical adequacy of the short and long term

corrective actions.

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c.

Determine the similarity of this event to the recent event

at Vermont Yankee described in NRC Information Notice 91-81,

Switchyard Problems that Contribute to Loss of Offsite Power;

and the event at Oconee described in NRC Inspection Report

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50-269/92-26 (Augmented Inspection Team).

d.

Did the licensee properly assess the risk factors associated with

the work to be accomplished in the 230kV and 500kV switchyards.

e.

Determine if there are any sufficiently common factors in the

three recent degraded offsite power events for which the

licensee's corrective action should have prevented occurrence of

the most recent event.

f.

Determine if the operational controls (including training) on

switchyard activities are adequate.

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3.

Description of Event

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On April 8,1993, the plant was in Mode 5 with a steam bubble in the

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pressurizer. The train

'A' diesel generator was functionally inoperable

due to maintenance activities.

Train 'B' was being powered from the

500kV bus via backfeed through the generator step up transformer. The

230kV bus was energized and available as a power source via the offsite

power transformer. At about 6:00 p.m., plant personnel were in the

process of replacing a cell in the battery which provides control power

for the 500kV switchyard. The work was authorized through work request

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308885. The work request did not include instructions for performing

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the necessary switching operations to disconnect the battery from the

charger.

Nor was an equipment clearance order utilized. With the

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battery charger connected to the system, electrical maintenance

personnel opened a switch to disconnect the battery. Within seconds of

disconnecting the battery, 500kV circuit breakers tripped, deenergizing

the safety-related buses.

Since the battery charger was not designed to

operate independent from a battery, the charger produced voltage outside

the specified operating range when the battery was disconnected.

Apparently, the abnormal voltage on the system damaged a solid state

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auxiliary tripping relay, causing it to go into the tripped condition,

tripping the 500kV breakers. This deenergized the 'B' 4160V Engineered

Safeguards electrical bus in service which resulted in an automatic

start of the

'B' Emergency Diesel Generator and a three minute

interruption in the operation of the decay heat removal system until it

was manually restarted.

Preliminary analysis of the event indicated that safety-related systems

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operated properly in response to the loss of power. The sequence of

events recorder printout showed that power was restored to the

safety-related buses approximately 13 seconds after the 500kV breakers

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tripped and approximately 8 seconds after the Emergency Diesel Generator

received a start signal. Operators transferred to the 230kV power

source about two hours later.

The 500kV bus was restored to service

about two and one half hours after the initial event.

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4.

Inspection

The inspection focused on the following inspection elements which are

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addressed individually below.

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4.1

Inspection Element (a):

Independently assess management oversight

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and effectiveness in accurately determining the root cause for the

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loss of 500kV offsite power event.

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The inspection identified that there were three aspects of the

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event which had some form of cause analysis ongoing. The

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technical analysis of equipment performance, plans for an

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evaluation of the human performance aspects of the event, and

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plans for a Management Review Team of commonality of switchyard

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events at the site during the maintenance outage were reviewed by

the inspectors.

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Following the event, all of the relays potentially affected were

tested and replaced, as necessary.

Since the system had been

returned to service prior to the inspection, the technical

analysis of the hardware involved was virtually complete.

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Nonetheless, the licensee had not determined the magnitude and

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waveshape of the charger output voltage during the period of time

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that the battery was disconnected.

Therefore, it could not be

demonstrated that the relay failure mode was as expected or that

the battery charger had been operating properly. A printout from

the switchyard sequence of events recorder had not been obtained.

Actions such as these appear to have been warranted to demonstrate

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that the equipment involved operated as expected for the

conditions created by the alignment of the system which caused the

event. Management oversight of the technical aspects of the root

cause analysis, although adequate, could have been improved to

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allow a more thorough understanding of the event and to ensure

comprehensive corrective actions.

The Nuclear Maintenance Work Controls Superintendent and the

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Nuclear Safety Supervisor were assigned the task of performing the

root cause analysis. They plan to utilize Compliance Procedure

CP-144, Root Cause Analysis, to perform an evaluation of the human

performance aspects of the event. Some of the subsidiary

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questions that the analysis will attempt to answer are:

What was the sequence of events and personnel actions?

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Is the division of responsibility between the plant and

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switchyard maintenance groups adequately defined?

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Is there a general problem with maintenance crew shift

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turnovers?

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Is communications among operations, the Outage Shift Manager

and substation maintenance effective?

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Is training related to the switchyard equipment for

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maintenance and operations personnel adequate?

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What is the detailed description of the event in terms of

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hardware performance?

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In addition to the evaluation of the human performance aspects of

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this event, the licensee had established a Management Review Team

to review the switchyard events associated with the maintenance

outage. The Management Review Team has responsibility to evaluate

the adequacy of root cause evaluations, short and long term

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corrective actions; and to identify generic problems, and cost

effective enhancements which would serve to prevent similar events

in the future.

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Management decisions to perform the evaluation of the human

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performance aspects and to establish the Management Review Team

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were sufficient to establish the basis for the identification of

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the significant contributing causes of the April 8 interruption of

shutdown cooling and commonality to other switchyard problems

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during the maintenance outage.

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4.2

Inspection Element (b):

Determine the technical adequacy of the

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short and long term corrective actions.

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The primary short term corrective action to prevent recurrence was

an operations Standing Order issued .on April 9, which prohibited

maintenance activities in the switchyard (230kV or 500kV) that was

supplying power to the safety-related buses, and therefore

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shutdown cooling, while in Modes 5 and 6.

The licensee plans to

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incorporate this prohibition into applicable shutdown operations

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procedures. This action alone is sufficient to prevent work in

the switchyard from affecting decay heat removal.

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The licensee plans to define long term corrective actions when the

root cause analysis and Management Review Team activities

described above are complete, therefore, long term corrective

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actions were not evaluated as part of this inspection. However,

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the inspectors noted that the plans for evaluation of the event

did not include a review of the adequacy of existing procedures

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associated with operation of systems in the switchyards.

4.3

Inspection Element (c): Determine the similarity of this event to

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the recent event at Vermont Yankee described in NRC Information

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Notice 91-81, Switchyard Problems that Contribute to Loss of

Offsite Power; and the event at Oconee described in NRC Inspection

Report 50-269/92-26 (Augmented Inspection Team).

On October 19, 1992, the Oconee plant experienced a loss of. power

which was initiated when a DC System bus tie breaker was opened,

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1 aving a portion of the system powered only by a battery charger

without a battery. Since the charger could not maintain a proper

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voltage in this configuration, the resultant voltage excursion

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caused zener diodes in the breaker failure relays to conduct which

caused breaker failure relay operations. This in turn set in

motion circuitry which caused loss of power to plant auxiliaries.

Post-event testing on the charger identified that the charger was

not functioning properly. This was not discernable by observation

of the voltmeters.

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NRC Information Notice 91-81, Switchyard Problems that Contribute

to Loss of Offsite Power, describes an event that took place on

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April 23, 1991, at the Vermont Yankee Plant very similar to the

Oconee event. The Vermont Yankee event began when the battery was

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disconnected from the DC System. The charger output became

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unstable which caused breaker failure relay operations which

caused the loss of power event.

Common elements in these two events are the fact that battery

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chargers may not be able to maintain voltage within acceptable

limits when the battery is not connected to the system, and a

certain style of breaker failure relay is particularly vulnerable

to overvoltages.

Also in both these events the battery chargers

were not functioning properly.

The Crystal River event began when the battery was disconnected

from the bus leaving only a charger to supply the loads. The

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charger was not designed for this mode of operation. This aspect

of the event was exactly like the Oconee and Vermont Yankee

events.

Relays were damaged during the Crystal River event, but

breaker failure relays were not involved.

In this respect the

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events were similar but not exactly alike. The licensee had

previously addressed the breaker failure relay issue and

determined that their breaker failure relays did not have the

vulnerability described in the notice and report.

With respect

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to the possibility that the battery charger was not functioning

properly thus aggravating the voltage transient, the licensee has

not tested the charger as part of the event analysis and therefore

the answer is indeterminate at the time of this inspection. The

licensee stated that there was no periodic preventive maintenance

program for the chargers in question.

Consequently, the analysis

of the available information was limited in scope.

The licensee was aware of the Oconee and Vermont Yankee problems

associated with isolated charger mode of operation. However,

since the analysis of the information available was narrowly

focused, it precluded the identification of the similar

vulnerability at Crystal River.

4.4

Inspection Element (d): Did the licensee properly assess the risk

factors associated with the work to be accomplished in the 230kV

and 500kV switchyards?

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At the time this inspection element was developed, it was believed

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that work had been ongoing in both the 230kV and 500kV switchyards

at the time of the event. The inspection revealed that this was

not true. Work was authorized on equipment in the 230kV

switchyard associated with the functional testing of the newly

installed Backup Engineered Safeguards Transformer. This work was

on hold while the cause was being determined for an inadvertent

deenergization of the 'B' 230kV bus during day shift on April 8.

Although work was not being performed in both the 230kV and the

500kV switchyards simultaneously, the inspectors determined that

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the risk of interrupting power to the shutdown cooling systems

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while performing the 500kV switchyard battery cell replacement was

not adequately evaluated by the licensee. This observation was

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supported by the fact that the Offsite Power Transformer was

operable and available to supply the shutdown cooling loads during

the replacement of the 500kV switchyard battery cell; however, the

control room operators did not recognize a need nor were they

advised to transfer to the alternate power supply. As noted in

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paragraph 4.2, above, a Standing Order was issued on April 9,

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which prohibited maintenance activities in the switchyard (230kV

or 500kV) that was supplying power to shutdown cooling systems.

4.5

Inspection Element (e): Determine if there are any sufficiently

common factors in the recent three degraded offsite power events

for which the licensee's corrective action should have prevented

occurrence of the most recent event.

The three events referred to by this inspection element were the

three previous reportable events which occurred on March 13,

March 17, and March 29. Additionally, three non-reportable events

which occurred on March II, March 25, and April 8, were also

evaluated. They are briefly described below.

On March 11, during maintenance activities on 230kV breaker

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No. 1157 (Unit 1 tie breaker - fossil unit) by the

substation construction crew, 230kV breaker No. 1692 was

inadvertently tripped.

Breakers 1691 and 1692 are the tie

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breakers for the 230kV Unit 3 startup transformer. Breaker

No. 1691 remained closed so the offsite power transformer

remained energized.

Safety-related buses were energized

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from the 500kV scurce at the time. Miscommunication and

failure to follow procedure by the substation crew played a

role in the event. There was no power loss to the unit.

(reference Problem Report 93-59)

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On March 13, severe weather caused a degradation of the

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offsite power supplies. The Startup transformer tripped and

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one of two 500kV backfeed breakers opened. There was no

power loss to the unit.

(reference Problem Report 93-69 and

EN 25241)

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On March 17, light rain combined with salt, that had

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deposited in the switchyard due to the March 13 severe

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weather, to form electrolyte. This resulted in electrical

degradation and loss of 230kV switchyard.

500kV backfeed

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remained available.

(reference Problem Report 93-95 and EN 25273)

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On March 25, a substation relay technician placed his test

instrument leads on the wrong terminals which caused a bus

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differential relay operation which caused deenergizing the

'B' 230kV bus.

(reference Problem Report 93-87)

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On March 29, a control power cable in the 500kV switchyard

failed causing a loss of the 500kV backfeed and interruption

of shutdown cooling.

(reference Problem Report 93-95 and EN

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25325)

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On April 8, while performing functional testing on the new

backup emergency safeguards transformer, a plant technician

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placed a jumper wire on the wrong terminals which caused

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operation of a lockout relay which deenergized the 'B'

230kV

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bus. The technician was performing trouble shooting at the

time. A typographical error in the procedure and a drawing

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error played a role in this event.

The safety-related buses

were being powered from the 500kV bus at the time of this

event.

(reference Problem Report 93-112)

The non-reportable events and the event which is the main subject

of this inspection have one common factor; all involved a problem

with procedures (i.e., failure to follow procedure or inadequate

procedure). However, the inspectors determined there was not

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sufficient commonality among the events. Consequently, the latest

event was not a result of inadequate corrective action for the

previous events.

4.6

Inspection Element (f):

Determine if the operational controls

(including training) on switchyard activities are adequate.

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Controls on activities in the switchyards at the Crystal River

site were delineated in the CR-3/0thers Interface Matrix Manual

and Administrative Instruction AI-1300, Crystal River Coal Plants,

Substation, ECC, and Relay Departments Interface with Crystal

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River Unit 3.

Inspector review of these documents identified that

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these documents provided direction for control of activities in

the switchyards such as; notification of the Unit 3 SS00 for

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routine entries, and notification of the Unit 3 Senior Nuclear

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Scheduling Coordinator for preplanning of maintenance and/or

modification activities. Additional controls had been implemented

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following the loss of offsite power event at plant Vogtle,

including limiting access to a main gate, requiring flagmen for

backing of vehicles in the switchyards, and restricting the use of

hazardous materials in the switchyards.

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There were indications of less than rigorous coordination of work

activity in the switchyard. For example, when there was a half

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trip of the 230kV switchyard on March 11, personnel in the Unit 3

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control room were not aware there was testing ongoing although the

work had been coordinated through the Senior Nuclear Scheduling

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Coordinator. Also, on April 8, the electricians who performed the

battery cell replacement contacted the control room from the relay

house in the 500kV switchyard without having previously receiving

permission to enter the switchyard as discussed in AI-}300.

The CR-3/0thers Interface Matrix Manual and Administrative

Instruction AI-1300, Crystal River Coal Plants, Substation, ECC,

and Relay Departments Interface with Crystal River Unit 3,

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specifically address the performance of surveillance testing on

the Unit 1/2 batteries which supply control power to the 230kV

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switchyard breakers. The surveillance testing of the Unit 1/2

batteries was required because both normal offsite power circuits

to Unit 3 are supplied through the 230kV switchyard. The 500kV

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switchyard is only used as an offsite power source when the plant

is shut down and backfeed has been aligned.

In order to ensure

compliance with TS, tne licensee applied the TS surveillance

requirements which applied to the Unit 1/2 batteries to the 500kV

switchyard batteries when utilizing the 500kV backfeed as an

offsite power source. The CR-3/0thers Interface Matrix Manual and

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AI-1300 did not address the performance of these surveillance

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tests. They were performed by Unit 3 electricians. As described

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in NRC Inspection Report 50-302/93-06, paragraph 4.a, difficulties

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had been experier.ced maintaining the specific gravity of cu cell

of the battery within tolerance since the testing had been

initiated prior to the beginning of the outage.

It was decided to

replace the cell. The work was authorized through work request 308885.

The Unit 3 electricians were inadequately trained on

operation of the system and the work request did not include

instructions for performing the necessary switching operations to

disconnect the battery from the charger. The Unit 3 electric shop

did not routinely work on, nor were they trained on the operation

of the switchyard battery systems. The day shift electrical

supervisor who reviewed the work request prior to implementation,

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recognized that further information was necessary for performance

of the work. He interfaced with systems engineering and

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operations to develop an acceptable method to perform the work.

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This information was not incorporated into the work request, nor

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passed on to the night shift electric shop supervision. The night

shift electrical supervisor did not recognize that further

information was necessary for performance of the work and the work

was assigned to the shop crew. With the battery charger connected

to the system, Unit 3 electrical maintenance personnel opened a

switch to disconnect the battery. Within seconds of disconnecting

the battery, 500kV circuit breakers tripped, deenergizing the

safety-related buses.

Since the battery charger was not designed

to supply the load independent from a battery, the charger

produced voltage outside the specified operating range when the

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battery was disconnected. Apparently, the abnormal voltage on the

system damaged a solid state auxiliary tripping relay, causing it

to go into the tripped condition, tripping the 500kV breakers.

This deenergized the 'B' 4160V Engineered Safeguards electrical

bus in service which resulted in an automatic start of the 'B'

Emergency Diesel Generator and a three minute interruption in the

operation of the decay heat removal system.

The failure to

establish an adequate procedure for the operation of the 500kV

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switchyard DC control power system was a violation and is

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Identified as VIO 50-302/93-11-01.

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5.

Conclusions

Prior to the interruption of decay heat removal on April 8, licensee

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personnel were aware of the problems associated with isolated charger

mode of operation at other sites; however, tb i analysis of the

information available was narrowly focused, p.ecluding the

identification of the similar vulnerability which existed at Crystal

River (paragraph 4.3).

The risk of interrupting power to the shutdown cooling systems while

performing the 500kV switchyard battery cell replacement was not

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adequately evaluated by the licensee (paragraph 4.4).

Personnel assigned to replace the 500kV switchyard battery. were

inadequately trained on the operation of the system and were supplied

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inadequate procedures to do the work (paragraph 4.6).

Short term corrective actions, particularly the Operations Standing

Order to prohibit work in the switchyard powering the shutdown cooling

systems, were very good (paragraph 4.2).

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Management decisions to perform the evaluation of the human performance

aspects and to establish the Management Review Team were sufficient to

establish the basis for the identification of the significant

contributing causes of the April 8 interruption of shutdown cooling and

commonality to other switchyard problems during the maintenance outage.

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Management oversight of the technical aspects of the root cause

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analysis, although adequate, could have been improved to allow a more

thorough understanding of the event and to ensure comprehensive

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corrective actions (paragraph 4.1).

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The latest event was not a result of inadequate corrective action from

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previous events at Crystal River (paragraph 4.5).

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6.

Exit Interview

The inspection scope and findings were summarized on April 16, 1993,

with those persons indicated in paragraph 1.

The-inspectors described

the areas inspected and discussed in detail the inspection findings and

the violation listed below.

Proprietary information is not contained in

this report.

Disse eing comments were not received from the licensee.

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Item Number

Description and Reference

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50-302/93-11-01

Violation - Failure to establish an adequate

procedure for the operation of the 500kV

switchyard DC control power system (paragraph

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4.6).

7.

Acronyms and Abbreviations

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AI

- Administrative Instruction

CFR

- Code of Federal Regulations

CP

- Compliance Procedure

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CR

- Crystal River Unit 3

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DC

- Direct Current

ECC

- Energy Control Center

EN

- Event Notification

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kV

- kilovolt

NRC

- Nuclear Regulatory Commission

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SSOD - Shift Supervisor of Duty

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TS

- Technical Specification

V

- volt

VIO

- Violation

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