ML16154A825

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Insp Repts 50-269/95-16,50-270/95-16 & 50-287/95-16 on 950710-14.No Violations Noted.Major Areas Inspected: Electrical Design to Review Licensee Action in Response to Edsfi Findings & Other Edsfi Issues Noted in Insp Repts
ML16154A825
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/08/1995
From: Steven Rudisail, Shymlock M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML16154A826 List:
References
50-269-95-16, 50-270-95-16, 50-287-95-16, NUDOCS 9508220219
Download: ML16154A825 (13)


See also: IR 05000269/1995016

Text

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REGUo

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

o

101 MARIETTA STREET, N.W., SUITE 2900

ATLANTA, GEORGIA 30323-0199

0A

Report Nos.:

50-269/95-16, 50-270/95-16 and 50-287/95-16

Licensee: Duke Power Company

422 South Church Street

Charlotte, NC

28242

Docket Nos.:

50-269, 50-270, and 50-287

License Nos.:

DPR-38, DPR-47,

and DPR-55

Facility Name:

Oconee Nuclear Station Units 1, 2 and 3

Inspection Conducted:

July 10 - 14, 1995

Inspector:

/o

-73

c '

S.'Rudisail

Date Signed

Accompanying Personnel:

Virgil Beaston, NRR

Approved by:

M. B. Shymlock, Chief

Date Signed

Plant Systems Section

Engineering Branch

Division of Reactor Safety

SUMMARY

Scope:

This routine, announced inspection was conducted in the areas of electrical

design to review the licensee action in response to Electrical Distribution

System Functional Inspection (EDSFI) findings and other EDSFI issues

identified in NRC Inspection Report 50-269, 270, 287/93-02. These items were

being resolved as part of the licensee's Power Upgrade Project (PUP).

Other

items completed as part of the PUP effort were also reviewed.

Results:

In the areas inspected, violations or deviations were not identified.

The inspectors reviewed various PUP items completed in response to EDSFI

findings. These EDSFI findings were identified as Inspector Follow-up Item

(IFI) 93-02-03.

OThe inspectors reviewed calculations, calculations revisions, procedures and

design basis documentation which had been completed to address the EDSFI

findings.

Enclosure

9508220219 950811

PDR ADOCK 05000269

G

PDR

2

Overall, the calculations were of good quality with no problems identified

during the calculation reviews. The licensee corrective actions for these

items were technically sound and thorough.

In some cases, actions completed by the licensee substantiated the licensee

previous conclusion that systems as designed were adequate. However, in some

cases actions completed by the licensee in response to the EDSFI findings

resulted in additional analysis and corrective actions to be completed by the

licensee.

The inspectors reopened IFI 93-02-04 to document continuing staff evaluation

of six EDSFI inspection items. This item was reopened as IFI 95-16-01.

REPORT DETAILS

1.

Persons Contacted

Licensee Employees

  • L. Azzarello, Mechanical Systems Engineering

M. Bailey, Regulatory Compliance

  • E. Burchfield, Regulatory Compliance Manager
  • D. Coyle, Mechanical Systems Engineering

J. Davis, Engineering

T. Grant, Electrical Systems Engineering

  • T. Ledford, Electrical Systems Engineering
  • C. Little, Electrical Systems Engineering
  • J. Peele, Plant Manager
  • L. Underwood, Electrical Systems Engineering
  • L Wilkie, Safety Review Manager

Other licensee employee contacted during this inspection included

craftsmen, engineers, technicians, and administrative personnel.

NRC Employees:

  • P. Harmon, Senior Resident Inspector

L. Keller, Resident Inspector

  • Attended exit interview

Acronyms and abbreviations used throughout this report are identified in

the last paragraph.

2.

Background

During January 25 through March 5, 1993, the NRC conducted the

Electrical System Distribution Functional Inspection (EDSFI).

The

purpose of this inspection was to assess the capability of the Oconee

Electrical Distribution System to perform it functions during normal

operations and accident conditions. The conclusion of the EDSFI team

was that the electrical distribution system would perform its intended

function pending further analysis and testing by the licensee. During

the EDSFI inspection a violation and several deviations were identified.

Additionally, findings identified during the EDSFI were collectively

identified as IFI 93-02-03. Licensee actions.to address these findings

and NRC review of these actions are discussed within this report and in

previous inspection reports 50-269, 270, 287/94-26 and 50-269, 270,

287/95-10.

3.

Review of Inspector Follow-up Items (IP 92903, TI 2515/111)

The inspector reviewed the items identified at Oconee as Findings.

IFI 93-02-03, EDSFI Findings consisted of six findings with several

issues identified in each finding. This finding was closed in NRC

inspection report 50-269, 270, 287/94-26 to document the findings which

II

2

were closed in that report. IFI 94-26-02 was opened to identify the

EDSFI finding items which remain opened.

3.1

The inspectors reviewed PUP item 4.b which addressed EDSFI finding 2.g.

Finding 2.g of the Oconee EDSFI report recommended that the licensee

"Identify the full scope [of electrical components supplied by the

Keowee station batteries] and complete individual voltage component

calculations for Keowee".

Section 3.2.4.4 of the EDSFI report stated that the inspectors reviewed

calculation KC-0076, Rev. 2, Keowee 125 VDC Auxiliary Power System

Battery Voltage and Duty Cycle Calculation, and noted that there was no

discussion in the calculation which addressed the voltage limitations of

electrical equipment being supplied by the batteries. The adequacy of

voltage being supplied to some of the Keowee electrical components

(i.e.; the Keowee generators' field windings and field flashing

breakers) was to be addressed in other calculations being developed at

the time of the EDSFI inspection. The EDSFI inspectors stated in

section 3.2.4.4 that "The comprehensiveness of the scope of the

supplemental calculations to examine voltage adequacy at the component

level should be considered."

The inspectors reviewed calculation/analysis KC-Unit 1-2-0093, Keowee

125 Volt DC Voltage Adequacy Calculation, dated May 18, 1995. The

purpose of this calculation was to determine that under the worst case

load profile for the 125 volt dc Keowee power system, all devices

required to operated during an emergency start would have adequate

voltage. The worst case configuration analyzed by the licensee was a

Keowee Unit 2 black start (first minute load profile) with the unit 2

electrical equipment being supplied by the unit 1 battery through a

cross connect. The unit 1 battery was assumed to have 59 cells

available and to be supplying both its equipment and the unit 2

distribution center through the cross connect. This analysis was

performed to bound the case where one of the Keowee batteries is out of

service. It was assumed that the voltage drop to unit 2 loads was

limiting due to longer cable runs associated with unit 2 equipment.

This calculation identified that the voltage supplied to the Keowee Unit

2 governor actuator cabinet would only be marginally acceptable during

the worst case load profile analyzed and with the unit 1 battery near

the end of its life (80% capacity). In particular, the 99SN solenoid

was identified as the most limiting electrical component. The minimum

volt.age calculated for the 99SN solenoid was 77.8 volts dc. The minimum

test voltage shown to be acceptable for the solenoid to operated was 76

volts dc. While the minimum calculated voltage available to operate the

solenoid was above the minimum tested value, the licensee recognized

that a system improvement could be made to increase the voltage margin.

An additional calculation performed by the licensee showed that by

replacing the 400 feet of cable running from bus 2DA to 2LC1 with a more

direct cable of approximately 25 feet, the minimum calculated voltage

3

available to the solenoid would increase from 77.8 volts dc to 84.1

volts dc. The licensee is tracking this recommendation with PIP 0-095

0590, and plans to implement it at a future date.

The inspectors found the licensee's analysis acceptable which concluded

all devices powered by the Keowee 125 volt dc system and required to

operate during an emergency start would have adequate voltage. The

inspectors had no further concerns as a result of reviewing this

calculation. This item is closed.

3.2

The inspectors reviewed PUP item 4.e which addressed EDSFI item 2.b.

Finding 2.b of the Oconee EDSFI report stated "The team noted that there

was no analysis nor test to verify that the -rapid transfer (transfer of

power to MFBs) timing was correct."

Section 2.5, "Bus Transfer," of the EDSFI report stated "The team noted

there was no design limits nor verification of the residual voltage on

the bus, and the phase angles between the outgoing and incoming voltages

prior to the transfer."

The inspectors reviewed calculation/analysis OSC-5749, "6.9 and 4.16 kV

Auxiliary System Transfer Analysis," dated May 24, 1995. The purpose of

this calculation was to verify that excessive voltages would not be

applied to motors during the fast and slow bus transfers of the Oconee

auxiliary systems. This analysis was performed by the licensee using

CYME computer analysis software. The results of this computer analysis

were evaluated by the licensee using the 1.33 p.u. volts/hertz criteria

contained in ANSI Standard C50.41-1992.

This analysis identified two instances in which the 1.33 p.u.

volts/hertz criteria would not be meet. The first instance was a fast

transfer of the 4.16 kV bus during a unit shutdown. To correct this

finding, the licensee's staff has proposed that the fast bus transfer be

blocked during unit shutdowns when the plant's auxiliaries are being fed

from the unit auxiliary transformer. The second instance was a slow

transfer of the 6.9 kV bus during normal unit operations. In this case,

the licensee's staff has proposed that the minimum bus deadtime be

extended, or the slow transfer scheme be modified to included relays

which would monitor the residual bus voltage and supervise the slow

transfer. The implementation of these recommendations was being tracked

by PIP 0-095-0585.

The inspectors found the licensee's analysis acceptable, and did not

identify any additional concerns. Because the volts/hertz values for

the two instances identified by the licensee where a bus transfer could

exceed the ANSI C50.41-1992 recommended value of 1.33 p.u. volts/hertz

only exceeded that recommended value by a small amount (approximately

5-10%) and because these two transfers were not expected to occur

repeatedly prior to the licensee taking corrective actions, the

inspectors agreed with the licensee's conclusion that these findings did

not pose a significant safety concern. This item is closed.

4

3.3

The inspectors reviewed PUP item 4.g which addressed EDSFI item 2.c.

Finding 2.c of the Oconee EDSFI report stated "The licensee did not have

a transient voltage study for the 4 kV safety load groups when they are

supplied from the Lee gas turbine or from Central substation."

Section 2.6.1 of the EDSFI report states "during starting of a unit LOCA

loads, or starting of two unit shutdown loads, the transient voltage dip

could exceed 20% [when supplied from CT-5].

The licensee agreed to

prepare a transient voltage study on the 4 kV safety load groups when

they are supplied from Lee gas turbine or from Central substation."

The inspectors reviewed calculation/analysis OSC-3290, "Voltage Study

for Oconee Auxiliary Power Systems When Fed From Lee Combustion Turbine

Via CT5 Transformer," dated May 30, 1995. The purpose of this

calculation was to validate the licensee's CYME computer modeling of the

Lee combustion turbines supplying auxiliary power to Oconee and to

simulate Oconee LOCA/LOOP and LOOP loading when supplied from Lee

combustion turbines.

The licensee performed a series of four tests designed to evaluate the

CYME modeling of the Lee combustion turbines and the electrical circuit

that connects Lee combustion turbines to Oconee nuclear units. These

tests were: (1) start of supercharger fan SC [associated with Lee

combustion turbine 5C] from Lee combustion turbine 6C; .(2) start of

supercharger fan SC from the grid; (3) start of an ASW pump at Oconee

from Lee combustion turbine 6C; and (4) trip supercharger fan 6C when

supplied from Lee combustion turbine 6C while isolated from the grid.

The CYME simulation results showed good agreement with the field data

collected during the four tests listed above.

The results of calculation/analysis OSC-3290 showed that while bus

voltage could momentarily drop below 50% for a worst case loading

scenario voltage would recover quickly, and all motor loads would start

without actuation of protective relaying. The analysis conducted by the

licensee identified three recommendations that would improve system

performance during periods when Oconee auxiliaries were being fed from

Lee. These recommended improvements are listed below and were being

tracked by PIP 0-095-0616 for further consideration by the licensee:

(1) When LOCA and LOCA/LOOP loads are automatically loaded onto a Lee

unit, the speed droops 2 to 3 percent. Before 4.16 kV manual

loads are loaded onto Lee following a LOOP or LOCA/LOOP, the

Oconee operator should make sure that the frequency of the Lee

unit is restored to normal;

(2) Field tests performed to verify the CYME program indicates that

the reactive droop compensator on the voltage regulator is set

between 5 and 6 percent. A setting of 0% or close to 0% would

improve the Lee unit voltage response when the Oconee auxiliary

loads are connected to Lee; and

5

(3) The calculation results indicate that all motors would start and

that motor protective devices would not trip, however, 4 kV motor

protection settings should be reviewed and set closer to the motor

thermal damage curves (where possible) so that more of the motor

thermal capacity can be used during motor starts. Motors

specifically mentioned in the calculation were LPSW and LPI pump

motors.

The inspectors found the licensee's analysis adequate, and they agreed

with the licensee's conclusion that Lee combustion turbines could supply

adequate power to meet postulated Oconee LOOP or LOCA/LOOP accident

scenarios. The inspectors did not identify any further concerns while

reviewing this calculation. The adequacy of power supplied to Oconee

from Central substation was addressed in Inspection Report 95-10.

This

item is closed.

3.4

The inspectors reviewed the licensee actions completed in response to

EDSFI finding 6.a.

Finding 6.a of the EDSFI report stated "The team identified several

components involved in the operation of the Keowee units during an

emergency start which were not being tested."

Section 3.4.2.4 of the EDSFI report identified that testing procedures

associated with ACBs 1, 2, 3, and 4 were noted to have weaknesses.

Procedure MP/O/A/2001/2:

Inspection and Maintenance of Keowee ACBs and

Associated Disconnects and Bus did not provide sufficient detail for

testing the check valves on the air accumulator in each breaker.

The licensee had revised maintenance procedure MP/O/A/2001/2:

Inspection and Maintenance of Keowee ACBs and Associated Disconnects and

Bus to include specific instructions for checking the operation of these

check valves. The inspector reviewed the revised procedure and found

the instructions adequate for resolution of the EDSFI concern. This

item was closed.

3.5

The inspectors reviewed PUP item 18 which addressed EDSFI item 6.b.

Finding 6.b of the Oconee EDSFI report stated "Testing was not being

performed on safety related mechanical components (i.e.; coolers and

pumps)."

Section 3.4.2.4 of the EDSFI report stated "It was noted that

performance monitoring testing was not routinely performed on the safety

related mechanical components (coolers and pumps) at Keowee . . . During

the inspection, the team identified several valves which were required

to change position for Keowee to provide emergency power, which were not

included on the Keowee active valve list (KC-0085)." Valves 1 and 2 OG

7 (the Keowee governor oil tank float valves) were specifically

mentioned in

the report.

6

The function of valves l and 2 OG-7 is to close on low oil level in the

governor oil tank and prohibit air entrainment into the Keowee governor.

Should air displace oil in a governor, control of that unit's wicket

gates could be adversely affected. In a worst case scenario, the wicket

gates of the affected Keowee unit could be driven closed at such a rapid

rate that an excessive pressure surge would be created in the penstock,

potentially damaging the penstock which is common to both Keowee units.

At the time of the inspection, testing of these two valves was required

to be performed annually as a part of the governor actuator inspection

and maintenance procedures (MP/l/A/2200/003 and MP/2/A/2200/003).

Acceptable operation of valves 1 and 2 OG-7 had been verified on

February 20, 1995, and February 15, 1995, respectively. The inspectors

had no further concerns regarding the testing of these two valves.

The licensee had initiated PIP 0-094-1162 to track EDSFI item 6.b which

had a tentative completion date of November 1, 1995. Corrective actions

stated in the PIP required the inclusion of appropriate Keowee equipment

into the licensee's inservice testing program, development of inspection

and test procedures, and performance of any necessary modifications and

initial testing. Since the licensee has not completed its corrective

actions to finding 6.b, this item will remain open until the licensee

completes these actions, and they have been reviewed. This item is

open.

3.7

Item 3.b identified that a controlled document for the setpoints at

Keowee (except for electrical relay settings) was not available. This

item was addressed by the licensee as PUP item 1h.

The licensee

developed setpoint document changes which added all Keowee

instrumentation that have adjustable setpoints to the Oconee Alarm and

Setpoint Document. The inspector reviewed these setpoint document

changes and compared the setpoint values and process descriptions to

Keowee drawings, DBDs, annunciator response procedures, and equipment

settings in the field. With only a few exceptions the information was

correct and consistent between the various sources. For the

discrepancies identified, the licensee appropriately dispositioned the

items through their Problem Identification Process (PIP).

This item was

closed.

Item 3.c identified that bulletins, information notices and generic

letters had not been reviewed for applicability to Keowee. The licensee

subsequently performed a comprehensive search of their Licensing

Correspondence files and their Integrated Commitment Index in order to

identify the population of items that might be applicable to Keowee. The

licensee identified a total of 502 items for review. These items were

distributed to Engineering mechanical, electrical, and civil groups for

review of applicability to Keowee. If the item was found to be

applicable, then a review of Oconee's response was performed. If the

Oconee response included Keowee or if the actions taken covered Keowee,

then no further corrective action was taken.

Items that were found to

be applicable to Keowee, and no action for Keowee had been taken, were

then reviewed for appropriate corrective action. The inspector found

the approach taken by the licensee to identify all potential items

7

applicable to Keowee to be acceptable. The inspector performed a spot

check of several bulletins and generic letters and determined that they

were dispositioned correctly in regard to Keowee. This item was closed.

4.

Review of Power Upgrade Project Items not Identified as EDSFI Findings

(IP 92903)

4.1

The inspectors reviewed PUP item 66 which related to a preliminary

initial scope document that identified the need for a modification of

the Keowee voltage regulators.

The Keowee generators are designed to operate as the onsite emergency

power sources for the Oconee Nuclear Power Plants. As such, they must

be able to act as isolated power sources and maintain adequate output

voltage during a postulated accident scenario. Maintaining adequate

output voltage is the function of the Keowee voltage regulators. During

an emergency start of the Keowee units, the voltage regulators are

placed in automatic control.

Between the dates of September 9, 1992, and May 8, 1993, the Keowee

Units 1 & 2 voltage regulators failed a total of six times to transfer

to automatic control following normal automatic starts as documented by

PIPs 92-0455, 92-0490, 92-0647, 92-0718, 93-0340, and 93-0385. The

cause for these failures was not know at the time, but it was thought to

be due to an unreliable voltage adjuster (70V) cam switch. As a result

of these repeated failures, on May 8, 1993, a condition of operability

was placed on the Keowee units. This condition required operators to

verify that the S8 contacts on both the base adjuster (70B) and the

voltage adjuster (70V) of a Keowee voltage regulator closed following a

unit shutdown. Since the root cause of the voltage regulators to

transfer to automatic upon startup was believed to be due to misposition

of the voltage adjuster following a unit shutdown, this condition of

operability was implemented to ensure the Keowee units would by ready

for any subsequent emergency starts. To remove this condition of

operability and to improve the reliability of the Keowee units, the

licensee started development of modification package NSM ON-52965 to

upgrade the Keowee voltage regulators.

Subsequent to the implementation of the condition of operability on the

Keowee units, the failure of the voltage regulator to transfer to

automatic did not reoccur until April 20, 1995. At this time the

failure persisted. With the ability to repeat the failure to assist in

troubleshooting, the licensee was able to identify the root cause of the

problem. The problem was identified as a bad module in the voltage

regulator's synchronizer which caused the voltage adjuster (70V) to be

driven out of its preset position before the regulator could transfer to

automatic. A document review by the licensee showed that the on

December 23, 1992, the synchronizer from Unit 1 was replaced with the

one from unit 2. This finding was consistent with the fact that the

failures on unit 2 occurred prior to that date, and the failures on unit

1 occurred after that date.

8

Since the root cause of the failures had been identified and it was not

due to an unreliable voltage adjuster, the licensee removed the

condition of operability originally placed on the Keowee units. The

initial reason for the voltage regulator modification had been to remove

this condition of operability. Since the voltage regulator problem has

been identified and corrected, implementation of NSM ON-52965 is not

considered necessary for closer of this item. The licensee still

planned however to implement the modification. Also planned as a part

of NSM ON-52965 was the replacement of Keowee components identified as

seismically suspect and implementation of recommendations made by the

licensee's Keowee lockout relay study (KC-0107). This item is closed.

4.2

The inspectors reviewed PUP item 91 which evaluated the effect of a

momentary loss of voltage on one of the 120 volt ac vital I&C busses

caused by the current limiting feature of an inverter.

The inspectors reviewed section 13.1.2, 7.5 kVA Safety-Related Inverter

Output Fault, of calculation OSC-3120, Oconee Relay Settings and Breaker

Coordination, dated June 1, 1995. If a fault occurred on a load

connected to the 120 volt ac vital I&C busses, the inverter could go

into a current limit condition before the load breaker connecting the

1fault

tripped and cleared the fault. If this were to occur, the output

voltage of the inverter would be degraded and could be low enough to

prevent operation of some of the supplied loads. Loads that would be of

concern in this situation are the Reactor Protection System (RPS) and

Inadequate Core Cooling Monitor (ICCM) instrument channels.

There are four RPS channels (2-out-of-4 logic) supplied from four

different inverters and two ICCM channels supplied from two of these

inverters which provide inputs to the Diverse Scram System (DSS)(2-out

of-2 logic) of ATWS. Two of the four inverters, therefore, supply both

one channel of RPS and one channel of ICCM. The licensee's analysis

documented that a momentary loss of voltage to one of these loads (RPS

or ICCM) would not be a problem for RPS because RPS has three other

redundant channels and would still be capable of performing its safety

function. The safety function of DSS is to provide backup for RPS in

the event of a common-mode failure of all channels of RPS. Since a

fault in a single channel of RPS is not a common-mode failure of RPS,

RPS would still be capable of performing its safety function, and

operation of the ICCM channel effected by the momentary loss of voltage

would not be required. The licenses analysis also concluded that any

postulated fault would be cleared by a load breaker prior to tripping

the inverter or the 125 volt dc panelboard supplying the inverter. The

inspectors had no concerns with the licensee's analysis. This item is

closed.

4.3

The inspectors reviewed PUP items 75 and 78. These items identified

licensee action to review Design Basis Documentation (DBD) against test

procedures and calculations to ensure that the ability to meet the

design basis was either tested or demonstrated with calculations.

9

The inspectors selected a sample of electrical DBDs to review the

methodology taken by the licensee for this review. The following DBDs

were reviewed:

(1) 120 VAC Instrumentation and Control Power

(2) 125 VDC SSF Auxiliary Power

(3) 230 kV Switchyard 125 VDC Power System

(4) 230 kV Switchyard

(5) 4 kV Essential Auxiliary Power System

(6) 4160/600/120V SSF Essential Power System

(7) Keowee Emergency Power

(8) Lee Emergency Power System

(9) Keowee 125 VDC Power System

(10) 250 VDC Auxilary Power System

The inspector reviewed the testing and calculations identified in the

DBD Testing/Calculation Matrix for each DBD. The design basis

requirements were identified with the relevant calculation and/or test

procedures to document the testing or calculation which demonstrated the

ability of the system to meet the design basis requirements.

The inspector considered the methodology for cross referencing the

testing and calculation to the design basis requirement as adequate.

The inspector did not review the test procedures for adequacy of scope

or procedural content.

4.4

The inspector reviewed PUP item 85. This item was identified as a PUP

item to resolve a problem with the Keowee 125 VDC breaker settings and

drawing discrepancies.

The licensee identified that various Keowee 125

VDC Distribution Center load breaker types were different than those

shown on one-line diagrams and vendor drawings. Additionally, breaker

coordination analysis has revealed that coordination could be

significantly improved by increasing battery breaker and tie-breaker

instantaneous settings to the HI setting.

The inspectors reviewed the licensee actions taken for this PUP item.

Minor modification OE-8047 was being implemented to revise drawings and

change breaker settings to address the identified discrepancies. The

actions were being tracked under PIP NO. 0-094-1655 and 2-093-0438. The

inspectors reviewed the scope of the corrective actions identified in

the PIPs and the minor modification. The actions were adequate to

address the concerns. This item was closed.

5.

Review of Inspector Followup Item 93-02-04:

EDSFI Items identified for

further NRC Review

IFI 93-02-04 identified various items during the EDSFI for additional

NRC review. This IFI was closed in NRC inspection report (IR)

50-269,

270, 287/94-26. This item was closed because no corrective actions were

required by the licensee. However, NRC review of these items was not

complete. The specific items below will be addressed as additional NRC

reviews are completed. Therefore, this item is reopened as IFI 95-16-01

Followup EDSFI Open Issues.

10

Item 1:

(page 25) The SSF make-up pump is rated at 29 gpm. TS 3.1.6.9

allows leakage not exceeding 30 gpm.

Item 2:

(page 12)

The MFBMP logic is designated as non-safety related.

The licensee basis for this designation is (1) during a LOOP only DBE

there is no established time period necessary for automatic power

restoration and (2) during a LOCA the EPSL would automatically restore

power to the bus.

Item 3:

(page 15) The feeder cables for the switchyard battery

chargers are non-safety related and the chargers are load shed during a

LOOP. TS requires the battery chargers be operable for the switchyard

batteries to be operable. The licensee considers the battery chargers

to be safety related. The basis for designating the feeder cables as

non-safety related is that manual action in the switchyard could be

taken to operate switchyard breakers if the switchyard batteries are

unavailable.

Item 4: (page 23)

The licensee does not analyze smart failures within

control systems when analyzing for single failure. This item was

identified in regard to the voltage regulator but captured a broader

issue applying to Oconee implementation of single failure.

(Finding

5.a is related)

Item 5:

(page 25) The definition of single failure and how it is

applied in reference to the 230 kV switchyard was questioned. The team

identified that the licensee did not consider a failure concurrent with

the initiating event in their single failure analysis in regard to the

230 kV switchyard as detailed in the FSAR. The licensee considers part

of the switchyard to be on-site even though the UFSAR analyzes part of

the off-site system. The team considered it to be off-site until

isolated by the switchyard logic and that a single failure should be

considered with the initiating LOCA/LOOP.

Item 6:

(page 22)

The team questioned the licensee's conformance to

the single failure criteria as stated in the UFSAR. Section 8.3.1.2 of

the UFSAR states " The basic design criteria of the entire emergency

power system of a nuclear unit, including the generating sources,

distribution equipment, and controls is that a single failure of any

component, passive or active, will not preclude the system from

supplying emergency power when required. The team found the licensee

had not fully analyzed the controls consistent with this requirement

specifically in regard to the governor control systems.

(Finding 4.a

and 5.a are related.)

6.

Exit Meeting

The inspection scope and results were summarized on July 14, 1995, with

those individuals indicated in paragraph 1. The inspector described the

areas inspected and discussed in detail the inspection findings. There

was no dissenting comments received from the licensee. Proprietary

information is not contained in this report.

11

Items opened/closed in this report Inspection Report IFI 95-16-01,

Followup of Open EDSFI Issues (IFI 93-02-04).

7.

Acronyms and Abbreviations

CFR

Code of Federal Regulations

ECCS

Emergency Core Cooling System

EDSFI

Electrical Distribution System Functional Inspection

FSAR

Final Safety Analysis Report

IFI

Inspector Follow-up Item

IP

Inspection Procedure

IR

Inspection Report

kA

Kiloamperes

kV

Kilovolts

KVA

Kilo- Volt- Amperes

LOCA

Loss of Coolant Accident

MCC

Motor Control Center

MVA

Mega Volt Amperes

NRC

Nuclear Regulatory Commission

NRR

Nuclear Reactor Regulation

MW

Mega-Watts

PIP

Problem Investigation Process

PUP

Power Upgrade Project

SSF

Safe Shutdown Facility

TI

Temporary Instruction

V

Volts

VAC

Volts Alternating Current

VDC

Volts Direct Current

VPC

Volts Per Cell