ML17352A321

From kanterella
Jump to navigation Jump to search
Insp Repts 50-250/93-25 & 50-251/93-25 on 931025-29.No Violations Noted.Major Areas Inspected:Implementation of Licensee MOV Program to Meet Commitments in Response to GL 89-10
ML17352A321
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 11/18/1993
From: Casto C, Hunt M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17352A320 List:
References
50-250-93-25, 50-251-93-25, GL-89-10, NUDOCS 9312140069
Download: ML17352A321 (24)


See also: IR 05000250/1993025

Text

~R AEcg

~o

Cy

e

0

~O

++*<<+

UNITED STATES

NUCLEAR REGULATORY COMMISSlON

REGION II

101 MARIETTASTREET, N.W., SUITE 2900

ATLANTA,GEORGIA 303234199

Report Nos.:

50-250/93-25

and 50-251/93-25

Licensee:

Florida Power and Light

9250 West Flagler Street

Miami, FL 33102

Docket Nos.:

50-250

and 50-251

License Nos.:

DPR-31

and

DPR-41

Facil ity Name:

Turkey Point 3 and

4

Inspection

Conducted:

October 25-29,

1993

Lead Inspecto

~ M.

. Hunt

Ii gS'y

Da e S'gned

Accompanying Personnel:

H. Miller

Other Personnel:

H. Holbrook, Consultant,

EGSG Idaho-INEL

Approved by:

asto,

hief

Test Programs

Section

Engineering

Branch

Division of Reactor Safety

Il

I FD

Date Signed

Scope:

SUMMARY

This special,

announced

inspection

was performed at the Turkey Point nuclear

plant to examine the implementation of the licensee's

motor operated

valve

(HOV) program to meet commitments in response

to Generic Letter (GL) 89-10,

"Safety-Related

Motor-Operated

Valve Testing

and Surveillance."

The

inspectors utilized the guidance

provided in Temporary Instruction

(TI) 2515/109 (Part 2), "Inspection Requirements for Generic Letter 89-10,

Safety-Related

Motor-Operated

Valve Testing

and Surveillance."

As delineated

in Part

2 of TI 2515/109, this inspection

was the initial review of the

Licensee's

HOV program implementation in response

to

GL 89-10.

The inspectors

reviewed the engineering

data for six HOVs including selected

portions of design calculations, test packages,

and diagnostic signature

traces.

The inspectors

also reviewed follow-up issues

from the previous

NRC

inspection of the

MOV program (TI 2515/109,

Part

1) conducted

in March 1992,

and documented

in NRC Inspection

Report Nos. 50-250/92-08

and 50-251/92-08.

9312140069

931118

PDR

ADOCK 05000250

8

PDR

Results:

The inspectors identified the following items during the inspection.

Concerns

2.

3.

The procedures for the performance of MOV static testing

need to be

enhanced

to define clearly the acceptance

criteria and record the as-

found data.

These procedures

need to consider the

10 CFR50,

Appendix

B

criteria in the verification process

for the data collected

and

equipment/programs

used for the test.

There

was

a lack of documentation

to support the operation of MOV brake

assemblies

at less

than

90 percent rated voltages.

No margins

were

included in the stem friction coefficient calculation for stem

lubrication degradation.

The licensee

intends to conduct testing to

evaluate

the appropriate

amount of margin"required.

No margins were set aside for load sensitive

behavior (rate of loading)

in the licensee's

calculations.

The licensee

was evaluating this margin

for dynamically-tested

HOVs.

In cases

where dynamic testing

showed original thrust calculations

were

not conservative,

the licensee

changed

the method of extrapolating the

required thrust by directly measuring thrust at control switch trip.

Although no operability concerns

were noted,

no guidelines

were provided

to account for torque switch repeatibility and other uncertainities

in

the calculations.

~Stren the

1.

Aggressive

approach to

MOV differential pressure testing.

Prioritization was given to high DP/low margin

MOVs.

2.

3.

4.

5.

Performance of multiple differential pressure

testing to aid in

justifying extrapolation methodology.

The use of upstream

and downstream

pressure

transducers

to capture time

dependent

pressure

variation during

MOV dynamic testing.

The measurement

of MOV thrust

and torque during static

and dynamic

testing to allow quantification of stem friction coefficients

and aid in

the evaluation of the load sensitive behavior

phenomena.

Engineering

and maintenance

personnel

responsible for the

MOV program

are technically knowledgeable

and current in the area of ongoing

industry issues.

REPORT DETAILS

Persons

Contacted

  • C. Bible, Supervisor,

Site Engineering

  • R. Bleaker, Electrical Supervisor,

Nuclear Engineering

  • J. Cook, Site

MOV Coordinator,

Plant St.'ucie

  • R. Gianfrancesco,

Supervisor,

Maintenance

Support Services

  • 0. Hanek,

Engineer,

Licensing

  • J. Hoffman, Mechanical

Supervisor,

Nuclear Engineering

  • H. Johnson,

Supervisor,

Operations

  • J. Knorr, Analyst, Licensing
  • R. Kundalkar,

Manager, Site Engineering

  • S. Lankford, Site

HOV Coordinator,

Plant Turkey Point

  • J. Hanso,

Principal

Engineer,

Site Engineering

  • D. Osborn,

Nuclear Assurance

  • L. Pearce,

Plant General

Manager

  • H. Pearce,

Supervisor,

Electrical

  • T. Plunkett, Site Vice President
  • D. Powell, Manager,

Technical

Support

  • J. Price,

Corporate Specialist

Other licensee

employees

contacted

during this inspection

included

engineers,

technicians,

and administrative personnel.

Other Personnel

  • J. Colvin, Mechanical

Engineer,

ABB Impell

NRC Resident

Ins ectors

  • T. Johnson,

SRI

  • B. Desai,

RI

  • Denotes personnel

that attended

the exit meeting.

Acr onyms

and initialisms used throughout this report are listed in the

l.ast paragraph.

GENERIC LETTER (GL) 89-10

"SAFETY-RELATED MOTOR-OPERATED VALVE [HOV]

TESTING AND SURVEILLANCE"

(2515/109)

On June

28,

1989, the

NRC issued

GL 89-10, which requested

licensees

and construction permit holders to establish

a program to ensure that

switch settings for safety-related

HOVs were selected,

set,

and

maintained properly.

Subsequently,

five supplements

to the

GL have

been

issued

and

one issued for comment.

NRC inspections of licensee

actions

implementing commitments to

GL 89-10

and its supplements

had

been

conducted

based

on guidance

provided in Temporary Instruction

(TI)

2515/109,

"Inspection Requirements for Generic Letter 89-10,

Safety-Related

Motor-Operated

Valve Testing

and Surveillance."

TI 2515/109 is divided into Part 1,

"Program Review," and Part 2,

" "

"Verification of Program Implementation."

The TI 2515/109 Part

1 program review was conducted

March 16-20,

1992

and documented

in NRC Inspection

Report 50-250/92-08

and 50-251/92-08.

The principal focus of this inspection

was to select

and review in depth

sev'eral

HOVs from the

111 safety-related

NOVs within the

GL 89-10

program at Turkey Point Units 3 and 4.

Valves were selected

from an

MOV

data information matrix and

NOV Testing Status

Report provided at the

request of the inspectors.

The

HOV selection

was

made to examine

various systems,

valve sizes,

and differential pressure

conditions, to

the extent practicable.

For the

HOVs selected,

the inspectors

reviewed the licensee's

GL 89-10

Motor Operated

Valve Plant Program,

piping. and instrumentation

drawings,

the design-basis

calculation results of the expected differential

pressure,

the sizing and switch setting calculations,

the diagnostic

test data

package,

and the

HOVATS software generated

diagnostic traces.

The following HOVs were selected

for review:

MOV-8788

MOV-3-1405

HOV-3-1420

High Pressure

Safety Injection

Pump

Discharge Disconnect

Valve

Auxiliary Feedwater

Pump Steam

Supply Valve

Steam Generator

Feedpump

Discharge

Isolation Valve

HOV-4-843A

HOY-4-869

Boron Injection To Reactor Coolant

System Cold Leg Valve

Reactor Coolant System Hot Leg

Safety Injection Stop Valve

MOV-4-1420

Steam Generator

Feedpump

Discharge

Isolation Valve

I

Based

on the review of the

HOVs sampled,

the inspectors

determined that

the licensee

was implementing

an effective

NOV program.

In response

to

GL 89-10, the review of the

MOV documentation verified that the design-

basis capabilities

were being met.

The inspectors

concluded that the

licensee's

implementation of its HOV program addressed

the

GL 89-10

recommendations

and the licensee's

commitments to the generic letter.

.r

The inspectors

reviewed the licensee's

design-basis'to

determine

and

verify its adequacy for the six sampled

HOVs examined during this

inspection.

In addition, the recommended

action "a" of GL 89-10 that

requested

the maximum differential pressure

and flow expected for both

normal

and abnormal

(accident)

conditions

was examined to verify that

maximum parameters

were used.

These follow-up reviews were conducted to

determine if changes

were implemented after the first NRC

MOY GL 89-10

Part

1 inspection

conducted

March 1992.

During that inspection,

the

licensee's

design-basis

documentation

and the electrical calculations

for degraded

voltage were reviewed.

However, the licensee

had not

completed the design-basis

HOV calculations for all ill HOVs.

The

licensee

had completed calculations for 30

MOVs with 81 calculations

remaining that were not complete.

During that inspection,

the

inspectors

concluded that the design-basis

was adequately

addressed

the

recommendations

in GL 89-10.

Since that Part

1 inspection,

the licensee

had received additional information that required further evaluation of

the design-basis

documentation.

During this inspection the inspectors

reviewed the licensee's

design-

basis calculations

and documents to verify that the remaining

81

HOV

calculations

were completed.

Since the Part

1 inspection,

many

calculations

and documents

were revised.

All of the revised

documents

and calculations

were reviewed to determine

and verify that design-basis

differential pressure

and flow conditions,

design temperature,

and other

design parameters

for the

HOV selected for review met the

recommendations

of GL 89-10.

The degraded grid calculations

were

reviewed to ensure that the lowest motor terminal voltage

commensurate

with design-basis

conditions

was factored into the

HOV electrical

calculations.

The closure control for all six valves

was by torque

switch in the closing position

and by limit switch in the opening

position.

Design-basis

documentation

was reviewed for the selected

HOVs

that were configured

as

shown in Appendix A.

The following design-basis

documentation,

calculations,

drawings,

and

procedures

were reviewed:

System Description

No. 021,

Emergency

Core Cooling Systems

(MOV-878B, MOV-4-843A, and MOV-4-869)

1

System Description

No. 112,

Condensate

And Feedwater

System

(HOV-3/4-1420)

System Description

No.

117, Auxiliary Feedwater

System

(HOV-3-1405)

Design Basis

Document,

Volume 1,

DBD No. 5610-062-DB-002,

Revision 3. Auxiliary Feedwater

System

Design Basis

Document,

Volume 2,

DBD No. 5610-062-DB-002,

Revision 3, Safety Injection System

PTN-BFJH-90-076,

Revision

4 dated July 20,

1993,

"NRC Generic Letter 89-10

MOV Design Basis Differential Pressure

Determination"

1) Attachment

12, HOV-3/4-843A/B

2) Attachment

20, HOV-3/4-869

3) Attachment

22,

HOV-878-A/B

4) Attachment

25, MOV-3/4-1403,

1404,

1405,

5) Attachment 27, HOV-3/4-1420,

1421

PTN-BFJM-92-039,

Revision

0 dated

November 24,

1992,

Determination

Of Revised

Design Basis Differential Pressure

And Thrust Requirements

For HOV-3/4-1420.And HOV-3/4-1421

PTN-BFJH-90-077,

Revision

5 dated July 22,

1993,

NRC Generic Letter 89-10

HOV Thrust Calculation

PTN-BFJE-92-022,

Revision

0 dated

March 9,

1992,

PSB-1

Voltage Analysis For Electrical Auxiliary Systems

PTN-BFJE-90-006,

Revision

6 dated August 2,

1993,

Motor

Operated

Valve Voltage Drop Calculations

- Generic Letter 89-10

PTN-BFJE-91-015,

Revision

3 dated August 2,

1993,

Motor

Operated

Valve Voltage Drop Calculations

Based

On

EDG 3A And

3B Test Results

PTN-BFJH-93-019,

Revision

0 dated

June

28,

1993,

Evaluation of HOV Output Torque Capability Considering

The

Effects Of Derated Motor Starting Torque

PTN-BFJH-93-003,

Revision

2 dated July 14,

1993,

Calculation

To Determine

The Starting Torque,

Current And

Voltage Of AC Valve Actuator Motors At Elevated

Temperatures

PTN-BFJE-92-032,

Revision

0 dated July 13,

1992,

125

VDC

Valve Actuator Motor Voltage Drop Calculation -

GL 89-10

EC-136,

Revision

4 dated August 22,

1991, Existing Stationary

Battery Cell Sizing And Voltage Drop Calculation (Verified 105

VDC

was minimum DC voltage)

EBASCO Services

Incorporated

FL0-53-20.5009,

Revision

0 dated

January

31,

1992, Unit 4 Emergency Diesel

Generator Units Dynamic

Load Study (Verified degraded grid was worst case

minimum voltage

for Unit 4)

Electrical

Elementary

Drawings

1) 5610-E-25,

Sheet

35B

2

5613-E-26,

Sheets

12G,

and 36A

3) 5614-E-10,

Sheet

1

4) 5614-E-25,

Sheets

27K and 28P"

5) 5614-E-26,

Sheet

36A

Mechanical

Process

Diagrams

1) 5613-H-3074,

Sheet

1

2) 5613-M-3075,

Sheet

1

3) 5614-H-3062,

Sheets

1 and

2

4) 5614-H-3074,

Sheet

1

JPN-PTN-SEHP-93-021,

Revision

0 dated

June

28,

1993,

Reduced Starting Torque Capability For Limitorque

Supplied Motors Located

In High Temperatures

Environments

(This document is classified

as

a

Substantial

Safety Hazards

Evaluation)

  • Denotes revision since Part

1 inspection in March 1992.

The licensee

was awaiting completion of the

NRC staff's reconsideration

of the need for

PWR licensees

to address

valve mispositioning

as part of

their

GL 89-10 program.

Besides

reviewing the

HOV documentation,

the inspectors

conducted plant

walkdown inspections to examine the

HOVs for stem lubrication and

'nstalled

strain gages.

The motor control centers

(MCCs) were inspected

to verify the installed electrical configuration agreed with design

drawings.

No concerns

were identified.

The inspectors identified no concerns with the performance of the

design-basis

review for the selected

HOVs and concluded that the

licensee

has adequately

addressed

the design-basis

review for the HOVs.

2.2

MOV Sizin

and Switch Settin

The inspectors specifically reviewed

PTM-BFJN-90-077,

"NRC Generic Letter 89-10

MOV Thrust Calculation,"

PTM-BFJN-90-077,

"NRC Generic Letter 89-10

HOV Actuator Evaluation,"

and the documentation for

determination of thrust

and torque requirements

for the six selected

valves.

The licensee's

gate valve thrust equation typically used

a valve factor

of 0.30 for flex wedge gate valves

when tested

at static conditions.

A

valve factor of 0.50 for wedge gate valves

was

used for dynamic (flow)

testing.

Similar choices

using 0.20 static

and 0.40 dynamic were

selected for double disk gate valves.

A valve factor of 1. 10 was used

for all globe valves.

The licensee

had revised their valve factor

assumptions

for the

18 inch Malworth flex wedge gate valves to

approximately 0.76.

The value of 0.76 was

based

on in-situ dynamic test

results.

The licensee

assumed

a stem friction coefficient of 0.20 for those

HOVs

that were located inside containment,

or that experienced

high operating

temperatures.

A stem friction coefficient of 0.15 was used for the

balance of HOVs in the program.

The licensee

had not included

a

specific margin in its

HOV calculations for stem lubrication degradation

that might increase

the stem friction coefficient over the lubrication

int'erval.

The licensee

intends to conduct

some as-found testing to

determine

an appropriate

margin to account for degradation of the

lubricant.

Minimum thrust requirements

were adjusted to account for

diagnostic

equipment

inaccuracy

and torque switch repeatability.

The licensee

had not set aside

a margin for load sensitive

behavior

(also

known as "rate of loading" ).

The licensee

was assessing

load

sensitive

behavior for specific dynamically-tested

MOVs, but had not

identified margins necessary

for MOVs that will only be tested

statically.

The licensee

intends to review their test data to justify

appropriate

margins for these valves.

The inspectors

noted that the licensee

had addressed

Limitorque's

Potential

10 CFR 21 condition, "Reliance

3 Phase

L. C. Actuator Motors

(Starting Torque at Elevated Temperatures),"

dated

Hay 13,

1993, which

dealt with the effect of elevated

temperature

on the output of AC

motors.

In response

to the issue,

calculation

PTN-BFJM-93-019,

"Evaluation of HOV Output Torque Capability Considering the Effects of

Derated Motor Starting Torque," dated

June

28,

1993,

was developed to

assess

the impact of derating

AC motor output torque.

The licensee

concluded that all affected

HOVs were capable of functioning under

design basis conditions.

However,

HOV-3-6386 and MOV-4-6386 were

evaluated

as having

a small margin

and were identified by the licensee

as

a candidate for future modification to improve actuator torque

capability.

The inspectors

agreed with this conclusion.

Calculation

PTN-BCJH-93-005,

"MOV GL 89-10 Diagnostic Test Data

Evaluation," dated

September

7,

1993, contained

the static test results,

and dynamic test packages

for the selected

valves:

VALVE

HOV-4-843A

HOV-4-869

HOV-878B

HOV-3-1405

MOV-3-1420

HOV-4-1420

CLOSE MAX.

D/P

1715

sid

1715

sid

1715 psid

1118

sid

312

sid

312 psid

CLOSE TEST

D/P

1489

sid

1474

sid

425 psid

290

sid

330

sid

298

sid

HAX D/P

87%

86%

25%

26%

106%

96%

The inspectors

reviewed the licensee's

dynamic test data that used the

industry standard

equation,

the valves'rifice diameters,

and the

dynamic test conditions.

Gate valve factors for the closing direction

ranged

from 0.16 (double disk) to 0.71 (flex wedge)

(see Appendix A).

The licensee's

test method identified load sensitive

behavior

as high as

24 percent.

The licensee's

valve factor assumption for gate valves

was

not always bounding.

However, the licensee

had increased their valve

factor assumption for their 18" Walworth flex wedge gate valves to 0.76.

Stem friction coefficients for the sample valves

(determined at flow

isolation) were

as high as 0. 14.

To determine

the operability of an

HOV, the licensee

used linear

extrapolation for the thrust necessary

to overcome differential pressure

to design basis conditions.

The licensee

was conducting multi-point

dynamic tests to develop

a justification for their extrapolation

methods.

Until the licensee

completes their justification, the

inspectors

consider the licensee's

extrapolation to be in the first

stage of a two stage

approach,

where the valves are setup using the best

available data,

as discussed

in GL 89-10.

The licensee

would be

expected

to justify its method of extrapolation

by the schedule

commitment date for the completion of their

GL 89-10 program.

During review of the dynamic test packages,

the inspectors

noted that

the test acceptance criteria only determined if the assumptions

made in

the original calculation were conservative.

No extrapolations

(where

necessary)

or margin assessments

were made prior to returning the valve

to service.

However, the licensee

had completed

a detailed review of

all dynamic test data conducted

before the inspection

and no operability

concerns

were identified.

In JPN-PTN-SEHP-032,

"Engineering Evaluation

for

NRC Generic Letter 89-10

HOV Static

and Dynamic Test Results,"

Rev.

0, dated October

15,

1993, the licensee identified that

a more

comprehensive

review was required before returning the

HOV to service.

This document

contained specific recommendations

for the revision of

dynamic test acceptance

criteria.

The licensee

indicated that computer

software

was being developed to allow the test evaluations to be

performed in a timely manner.

The licensee's

engineering

evaluations typically compared the

extrapolated

required thrust to the minimum control switch trip (CST)

thrust specified in the original calculation.

These evaluations

provided assurance

that sufficient margin existed to account for

uncertainties

(e.g.,

torque switch repeatability).

However, in those

cases

where the original thrust calculation

was not conservative,

the

licensee

used

a different approach,

in that the extrapolated

required

thrust was compared directly to the thrust measured

at CST.

In these

cases,

the licensee did not have guidelines specifying the amount of

margin that was required to account for torque switch repeatability

and

other uncertainties.

No operability concerns

were identified with the

use of this approach for the sample

MOVs.

However, the licensee is

developing this guidance for future operability judgements.

During review of the static test

package for HOY-4-843A, the inspectors

noted that the technician

signed off procedure

steps.

The technicians

answered

"yes" to questions

on

a check list that the available thrust

was within the specified

window when the measured

available thrust

was

less than the minimum required available thrust, corrected for

uncertainties.

The condition was not identified at the

end of the

static test,

but was later identified by the

HOV coordinator after the

dynamic test

was completed.

The valve performance

was acceptable

during

the dynamic test.

The licensee

performed

an additional static test

where the torque switch was set higher to allow for additional

margin

and to bring the measured

available thrust in conformance with the

requirements

of the thrust calculations.

The licensee

stated that the

test procedures will be enhanced

to improve the acceptance

criteria,

and

their independent verification process.

The inspectors

noted deviations in the HOV-4-843A engineering

evaluation's

"corrected target" values

as

compared to the values

used in

the dynamic test package.

Licensee

personnel

stated that

a

communication error between

maintenance

and engineering

was the cause of

the deviation.

Engineering incorrectly assumed that the strain gage

had

been calibrated with the

HOVATS torque thrust cell (which would allow

use of a smaller uncertainty),

when the strain

gage

had not been

calibrated.

This error led to the development of thrust limits that did

not adequately

account for diagnostic

equipment uncertainty.

After

review of the remaining

sample

HOVs, it was found that this was

an

isolated occurrence.

The licensee

stated

they will conduct

a review to

ensure that similar errors

have not occurred,

and will develop ways to

prevent

a recurrence

of the event.

2.4

During review of test

packages for HOV-3-1420, the measured

torque at

CST exceeded

the maximum allowed

CST torque

by 39 ft-lb.

The licensee

dispositioned

the condition on the basis that the torque limit was not

a

structural limit.

However, the torque limit was

based

on the actuator's

output capability under degraded

voltage conditions.

This means that

the actuator would be unable to generate sufficient output torque to

open the torque switch during

a degraded

voltage condition and could

cause

the actuator to stall.

The licensee

reevaluated

the

maximum

allowed torque limit using

an application factor of 1.0 that resulted in

a corrected

maximum allowed

CST torque of 1004.4 ft-lb, which was 64.4

ft-lb greater

than the measured

torque.

The licensee

also noted that

their standard

methodology

used

a more conservative pullout efficiency

for the closing direction.

The licensee

conducted

a review and

determined that no other conce} ns were dispositioned

using this basis.

The inspectors

performed

a detailed review of diagnostic traces

using

the

HOVATS 3000 software for the sample

MOVs.

The licensee

used the

highest force including hard seat contact

as the force used in their

extrapolation for design-basis.

No concerns

were noted in this area.

HOV Motor Brakes

In Maintenance

Update 92-2, Limitorgue Corporation

informed the nuclear

industry that there

was

a concern with motor brakes.

Limitorque stated

it had discovered

through operating experience

and testing that motor

brakes

do not minimize the thrust load caused

by inertia when closing

HOVs.

Limitorque also stated it did not qualify motor brakes

through

its nuclear qualification program.

Limitorque warned that voltage

variations

(low voltage)

may render the brakes inoperative.

In

addition, disconnection of the electrical

leads

does not render the

brake inoperative,

the friction pads

need to be removed.

The inspectors

discussed this motor brake concern with the licensee.

The licensee

informed the inspectors

they were aware of the motor brake

issue

and

had already

implemented partial corrective action.

Six HOVs

with motor brakes,

HOV-3-865A, B,

& C and HOV-4-865A,

B 5

C were locked

open to prevent valve failure due to the motor brakes.

These six

valveswere

scheduled

to have the motor brake assemblies

removed during

the next refueling outage.

The licensee

also identified twelve

additional

HOVs with motor brakes installed.

These

HOVs are listed as

follows:

HOV-3-716A

HOV-3-716B

HOV-3-730

MOV-3-872

MOV-3-880A

HOV-3-880V

HOV-4-716A

HOV-4-716B

MOV-4-730

HOV-4-873

MOV-4-880A

HOV-4-880B

The licensee

calculated

the minimum voltage at the

HOV motor brake

assembly terminals for brake equipped

HOVs in both Units.

The 90

percent voltage rating of 460 volts for the brake assemblies

is 414

volts.

The inspectors verified that the calculated

voltages for Unit 4

MOV motor brakes

assemblies

were above the 90 percent voltage rating at

degraded grid voltage.'owever,

the

HOV motor brake assembly terminal

voltage for Unit 3

HOVs was below the 90 percent rating at degraded

10

grid.

(Degraded grid is the setpoint where the emergency diesel

generators

start

and pick-up load.)

The licensee

addressed

this concern

through discussions

with other licensees

that had

HOVs with motor

brakes.

However, they had not contacted

the

MOV brake vendor.

The

inspectors

informed the licensee that

MOV motor brake concern

was under

review by the

NRC staff.

The licensee

advised the inspectors that the

vendor would be contacted

and appropriate corrective action taken.

The

inspectors

requested

that the licensee

keep the

NRC informed of their

actions.

The inspector

concluded that the licensee

was addressing

the

MOV motor

brake concern in a satisfactory

manner.

'.5

Schedule

In GL 89-10, the

NRC staff requested

that licensees

complete all design-

basis

reviews,

analyses,

verifications, tests,

and inspections that were

initiated to satisfy the generic letter recommendations

by June

28,

1994, or three refueling outages after December

28,

1989, whichever is

later.

The licensee's

commitment to

GL 89-10 requires that all

HOVs within the

scope of its

GL 89-10 program

be tested with their design-basis

capability verified by June

1994.

The licensee's

schedule

indicated

that this commitment will be met.

Approximately 21

HOVs remain to be

dynamically tested during Refueling Outage

5, which is scheduled

to

begin in Hay 1994.

2.6

Pressure

Lockin

and Thermal Bindin

0

The Office for Analysis

and Evaluation of Operational

Data

(AEOD) has

completed

a study of pressure

locking and thermal binding of gate

valves.

AEOD concluded

in its report that licensees

have not taken

sufficient action to provide assurance

that pressure

locking and thermal

binding will not prevent

a gate valve from performing its safety

function.

The

NRC regulations require that licensees

design safety-

related

systems to provide assurance

that those

systems

can perform

their safety functions.

In GL 89-10, the staff requested

licensees

to

review the design basis of their safety-related

HOVs.

The inspectors

reviewed several

licensee's

documents that addressed

pressure

locking and thermal binding.

FPL had performed

an evaluation

in response

to

INPO SOER 84-7 and identified 40 valves that were subject

to pressure

locking and thermal binding.

The inspectors

reviewed

a

draft list that contained

59 valves

as the result of the

GL 89-10 study.

The licensee

has modified 22 HOVs to preclude pressure

locking.

The

inspectors

reviewed engineering

evaluation

JPN-PTN-SEHJ-89-066,

Revision

I, Evaluation of Pressure

Locking of Motor Operated

Gate Valves,

dated

December

12,

1989,

which evaluated

the various valves for operability

concerns.

The licensee

has

an

on going evaluation

program to address

any additional valves that exhibit pressure

locking or thermal binding.

ll

Follow-u

of Concerns

Enumerated

in the Part I Re ort

The concerns identified in the Part I report were reviewed to verify

that the licensee

had taken actions to improve, modify, or correct

any

deficiencies

observed

by the inspectors.

The} e was concern that certain

MOVs that were practicable to test

may

not be in situ DP/Flow tested.

The licensee is evaluating the

possibility of grouping in lieu of dynamically testing

each valve and is

awaiting the results of the

EPRI testing program.

The inspectors

reviewed the licensee's list of valves that were not practicable to

dynamically test.

The justification for each non-testable

valve was

examined

by the inspectors

and found technically sound

and justified.

The licensee

has not completely developed all the procedures

necessary

to support the

MOV maintenance

and testing program.

The inspectors

reviewed various parts of the maintenance

and post maintenance

testing

procedures listed below:

gI 11-PTN-I, Test Control

gI ll-PTN-3, Post Maintenance

Tests

W

O-ADM-701, Control of Maintenance

and Constructions

Work

Activities

O-ADM-737, Post Maintenance Testing

Procedures

did not require as-found data collection

and trending

information assimilation.

Test procedures

did not fully consider

the

intent of the

10 CFR 50 Appendix

B criteria to verify the data

collection process.

EXIT INTERVIEW

The inspection

scope

and findings were summarized

on October

29,

1993

with those

persons

indicated in paragraph l.

The inspectors

described

the areas

inspected

and discussed

in detail the inspection results.

Proprietary information is not contained in this report.

No dissenting

comments

were received

from the licensee.

ACRONYMS AND INITIALISMS

AC

AEOD

CS

CST

CT

DBD

D/P

EPRI

FPL

ft-lb

FSAR

GL

Alternating Current

Office for Analysis

5. Evaluation of Operational

Data

Charging System

Control Switch Trip

Containment

Spray System

Design Basis

Document

Differential Pressure

Electric Power Research

Institute

Florida Power

5. Light

Foot Pounds

Final Safety Analysis Report

Generic Letter

INEL

INPO

HCC

HOV

NRC

NRR

PTN

PMR

psid

ROL

SOER

TI

V

VDC,

12

Idaho National Engineering Laboratory

Institute of Nuclear

Power Operations

Hotor Control Center

Hotor Operated

Valve

Nuclear Regulatory

Commission

Nuclear Reactor Regulation

Plant Turkey Point Nuclear

Pressurized

Mater Reactor

Pounds

Per Square

Inch Differential

Rate of Loading

Significant Operating

Experience

Report

Temporary Instruction

Volts

Volts Di}ect Current