ML20151D952

Insp Rept 50-302/88-16 on 880512-0608.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls,Lers,Security & Nonconforming Operations Repts

ML20151D952
Person / Time
Site:	Crystal River
Issue date:	07/07/1988
From:	Crlenjak R, Stetka T, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151D928	List: ML20151D925 ML20151D938 ML20151D952
References
50-302-88-16, NUDOCS 8807250301
Download: ML20151D952 (15)

See also: IR 05000302/1988016

Text

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• p6Ofoug' UNITED STATES

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8 i b [' ,, 101 MARIETTA STREET.N.W.

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Report No.: 50-302/88-16--

, Licensee: Florida Power Corporation

, 3201 34th Street, Scuth

St. Peter sburg, FL 33733

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Q, ' Docket No.: 50-302 License No.: OPR-72

Facility Name: Crystal River 3

h ' Inspection Conducted: May 12 - June 8,'1988

Insnectors: olvf/> )ny '7 /'? /f f

T. Stetki, Sen R ident inspector Date Signed

t/T1. w9 L

-J. Tedrow, Resident I s ector

7/7 / rd

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Date ' Signed

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Approved' by: -

RMrlenjak, Section CHieT-

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Dath Signed

Division of Reactor Safety

SUMMARY

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Scope: This : routine inspection was conducted by two resident inspectors in

the areas of plant . operations, radiological controls, security,

Licensee Event Reports and_ Nonconforming Operations Reports, facility

modifications, TMI Task Action Plan Review, Offsite Review Committee

Activities, and licensee action on previous inspection. items.

Numerous facility tours were conducted and facility operations

observed. Some of these tours and observations were conducted on

backshifts.

'NRC Region II personnel met with the licensee on May 25, 1988, to

discuss the licensee's efforts in improving the surveillance program

(paragraph 2.b.(8)(e)).

Results: Three violations were identified: Failure to perform a channel

calibration o f. the containment hydrogen analyzers, paragraph

2.b.(8)(a); Failure to - adhere to the requirements of procedure

CH-101, paragraph 2.b.(8)(b); Failure to provide adequate corrective

action to prevent exceeding the maximum release rate for a liquid

release, paragraph 3.b.(1).

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Management attention to surveillance was evident.

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8807250301 880708

PDR ADOCK 05000302

Q PDC

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. REPORT DETAILS

1. Persons Contacted

Licensee Employees

• W. Bandhauer, Assistant Nuclear-Plant Operations Manager

• G. Becker, Manager, Site Nuclear Engineering Services

• J. Brandely, Manager, Nuclear Integrated. Planning

• P. Breedlove, Nuclear. Records Management Supervisor

• J. Colby, Manager, Nuclear Mechanical / Structural Engineering Services-

• M. Collins, Nuclear. Safety and Reliability Superintendent

E. Ford,' Nuclear Operations Technical Advisor

J. Gibson, Nuclear Technical Specification Coordinator

• D. Green, Nuclear Licensing Specialist

F. Gross, Engineering Aide

-*B. Hickle, Manager, Nuclear Plant Operations

J. Holton,' Senior Nuclear Results Engineer

• G. Longhouser, Nuclear Security Superintendent

• W. Marshall, Nuclear Operations Superintendent

• P. McKee, Director, Nuclear Plant Operations

• S. Robinson, Nuclear Chemistry and Radiation Protection Superintendent

S. Roe, Nuclear Project Engineer

• V. Roppel, Manager, Nuclear Operations Maintenance and Outages

• W..Rossield, Manager, Nuclear Compliance

L. Sexton, Senior Nuclear Mechanical Engineer

• E. Welch, Manager, Nuclear Electrical / Instrumentation and Control

Engineering Services

• R. Widell, Director, Nuclear Operations Site Support

"M. Williams, Nuclear Regulatory Specialist

Other licensee. employees contacted -included office, operations,

-engineering, maintenance, chemistry / radiation and corporate personnel.

• Attended exit interview

Acronyms and initialisms used throughout this report are listed in the

last paragraph.

2. Review of.P! ant Operations (71707)

The plant continued in power operations (Mode 1) for the duration of this

Linspection,

a. Shift Logs and Facility Records (71707)

The inspector reviewed records and discussed various entries with

operations personnel to verify compliance with the Technical

Specifications (TS) and the licensee's administrative procedures.

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The following records were reviewed:

Shift Supervisor's' Log; Reactor Operator's Log; Equipment

Out-0f-Service Log; Shift Relief Checklist; Auxiliary . Building

Operator's Log; Active Clearance Log; Daily Operating Surveillance

Log; Work Request Log; Short Term Instructions (STI); and Selected

Chemistry / Radiation Protection Logs.

In addition to these record reviews, the inspector independently

verified clearance order tagouts.

No violations or deviation; were identified.

b. Facility Tours and Observations (71707)

Throughout the inspection period, facility tours were conducted to

observe operations and maintenance activities in progress. Some

operations ' and. maintenance activity observations were conducted

during backshifts. Also, .during this inspection period, licensee.

meetings were attended by - the inspector to observe planning and

management activities.

The facility tours and observations encompassed the following areas:

security perimeter fence; control room; emergency diesel generator

room; auxiliary building; intermediate building; battery rooms; and

electrical switchgear rooms.

During these tours, the following observations were made:

(1) Monitoring Instrumentation - The .following instrumentation

and/or indications 'were observed to verify that indicated

parameters were in accordance with the TS for the current

operational mode:

Equipment operating status; area atmospheric and liquid

radiation monitors; electrical system lineup; reactor

operating parameters; and auxiliary equipment operating

parameters.

No violations or deviations were identified.

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(2) Safety Systems Walkdown (71710) - The inspector conducted a

walkdown of the emergency feedwater system (EF) to verify that

the lineup was in accordance with license requirements for

system operability and that the system drawing and procedure

correctly reflected "as-built" plant conditions.

No violations or deviations were identified.

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-(3) Shift Staffing (71707) - The inspector verified that operating

shif t staffing was in accordance owith TS requirements and that

control room operations were being conducted in an orderly and

professional manner. In addition, the inspector observed shift

turnovers' on varinus occasions to verify the continuity of plant

status, operati."=1 problems, and other' portinent plant

information during these turnovers.

No violations or deviations were identified.

(4) Plant Housekeeping Conditions (71707) - Storage of material and

components and cleanliness conditions of various areas

throughout the facility were observed to determine whether

safety and/or fire hazards existed.

No violations or deviations were identified.

(5) Radiological Protection Program (71709) - Radiation protection

control' activities were observed to verify that these activities

were'in conformance with the facility policies and procedures,

and in compliance .with regulatory requirements. These

observations included:

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Selected licensee conducted surveys;

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Entry to and exit from contaminated areas including

step-off pad conditions and disposal of contaminated

clothing;

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Area, postings and controls;

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Work activity within radiation, high radiation, and

contaminated areas;

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Radiation Control Area (RCA) exiting practices; and

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Proper wearing of personnel mon;toring equipment,

protective clothing, and respiratory equipment.

Area postings were independently verified for accuracy by the

inspector. The inspector also reviewed selected Radiation Work

Permits (RWPs) to verify that the RWP was current and that the

controls were adequate.

The implementation of the licensee's As Low As Reasonably

Achievable (ALARA) program was reviewed to determine personnel

involvement in the objectives and goals of the orogram.

No violations or deviations were identified.

(6) Security Control (71881) - In the course of the monthly

activities, the inspector included a review of the licensee's

physical se:urity program. The composition of the security

organizatior, was checked to insure that the miaimum number of

guards were available and that security activities were

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conducted with proper supervision. The performance of ~ various

shifts of the security force was observed in the conduct of

daily activities to include: protected and vital area access

controls;~ searching of personnel, packages, and vehicles; badge

' issuance and retrieval; escorting of visitors;- patrols; and

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compensatory posts. In addition, the inspector observed the

operational status of Closed Circuit Television (CCTV) monitors,

-the Intrusion Detection system in the central and secondary-

alarm stations, protected area lighting, protected and vital

area barrier integrity, and the security organization interface

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with cperations and maintenance.

No violations or deviations were identified.

(7) Fire Protection (71707) - Fire protection activities, staf fing,

and equipment were observed to verify that fire brigade staffing

- was appropriate and that fire alarms, extinguishing equipment,

actuating controls,- fire fighting equipment, emergency

equipment, and fire barriers were operable.

No violations or deviations were identified.

(8) Surveillance (61726) - Surveillance tests were observed to

verify that approved procedures were being used; qualified

personnel were conducting the tests; tests were adequate to

verify equipment operability;. calibrated equipment was utilized;

and TS requirements _were followed.

The following tests were observed-and/or data reviewed:

"o-1608, Functional and Operability Che P cf the

Containment Hydregen Monitoring WS-10-CE;

- SP-317, RC System Water Inventory Balance;

- SP-375A, Chilled Water Pump (IA) Quarterly Operability

Demonstration;

- SP-430, Containment Air Locks Seal Leakage Test;

- SP-711, Core Flood Tank "B" Monthly Surveillance Program;

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- PT-319, Discharge Valve Positioning Verification.

(a) Procedure SP-1608 was reviewed to determine the licensee's

compliance with the TS. This procedure was written to

implement TS 4.6.4.1,

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which requires the licensee to

perform a channel calibration on the containment hydrogen

analyzers at least once every 92 days. The inspector

noticed that this procedure did not include a check of the

analyzers' local alarms or the r earm annunciated on the

main control board ~in the control room. The TS definition

of a channel calibration encompasses the entire channel

including alarm functions. From a review o maintenance

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history for this instrumentation, the inspector determined '

that a check- of these alarms had not been performed since

the analyzers were installed in August 1983.

Through discussions with licensee engineering and operating

personnel, and a review..of the licensee's emergency

procedures, the._ inspector determined that the containment

hydrogen indication would be monitored following an-

accident and that the loss of alarm function. for this

monitor would not prevent the safety function of the

system. However, f ailure to include a check of the alarm

functions during the required channel calibration is

contrary to the requirements of TS 4.6.4.1 and is

considered to be a violation.

Violation (302/88-16-01): Failure to perform a channel

calibration on the containment hydrogen analyzers.

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(b) Procedure SP-711 was written by the' licensee to implement

the requirements of TS 4.5.1.b to verify the boron

concentration in the core flood tanks. Thi: procedure

specifies that the boron analysis be perform d in

accordance with chemistry procedure CH-101, Determination

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of Boron, Mannitol Complex Titration Method. During the

performance of this analysis on June 1, 1988, the inspector

noticed that the chemistry technician deviated from the

instructions provided in procedure CH-101. The technician

analyzed a sample volume of 10 milliliters (ml) while

procedure step 9.2.1 and Table 1 required a sample volume

of 25 ml. When questioned about this apparent

nonconformance, the technician stated that he had received

verbal _ instructions from his supervisor to perform the

analysis using 10 ml of sample and using a different

titration apparatus than specified by procedure CH-101.

The inspector met with the chemistry supervisor, who

confirmed the verbal instructions provided to the

technician.

Althou the sampling method used by the technician did not

appe. adversely affect the sample results, the use of

verbal instructions' vice written procedures to implement

the requirements of TS 4.5.1.b is contrary to the

requirements of Regulatory Guide (RG) 1.33, November 1972,

Section J, and is considered to be a violation of TS 6.8.1.a.

Violation (302/88-16-02): Failure to adhere to the

requirements of procedure CH-101.

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(c)L During the performance of procedure SP-375A, the inspector

was informed by the technician performing the procedure

that the point "C" identi fied L by the machine sketch

provided in the procedure did not indicate a pump bearing,

but rather the location of. a packing gland. The licer.see

was etilizing this location for measuring the pump bearing

vibration and temperature specified by the ASME Boiler and

Pressure Vessel ~ Code,Section XI.

This information was discussed with licensee engineering

persennel who provided the inspector with the pump'r

technical manual. This type of pump- does not contain a

pump bearing, but utilizes 'cwo bearings on the pump's

driver (motor) for support. Although, this procedure is

performed by the licensee for information purposes only, in

accordance with NRC relief request V-370 to the licensee's

proposed inservice testing program, the inspector

considered it prudent to record the vibration and

temperature measurements on the motor bearing closest to

the pump as required by ASME Section XI, Article IWP-1200.

Licensee representatives agreed with the inspector's

comments and stated that they would make appropriate

changes to procedure SP-375A and the redurdant B train

SP-375B test procedure.

IFI (302/88-16-03): Review the revision to SP-375A/B to

take bearing vibration and temperature measurements on the

motor bearing closest to the pump.

(d) During the performance of_ procedure PT-319, the inspector

noticad wide variations in the flow ratt for the temporary

flow monitoring instrument on the nucleac services seawater

(RW) system. Also, the indicated flow cpoeared to be much

lower (approximately 1000 gpm) than measured flows during

previous tests. Troubleshooting of- this indication by the

licensee revealed that the flow element nad been damaged

during insertion into the system and silt had accumulated

in the element.

Further inspection by the licensee revealed that the RW

system piping was also slightly damaged during the process

of inserting the flow element. The inspector observed

liceresee personnel perform an ultrasonic test of this

piping to determine the extent of damage. Although the

results of this test showed no sig11ficant deformation of

the piping, the protective lining used on tFis piping to

prevent corrosion could have been damaged. Tie licensee

plans to perform periodic ultrasonic testing of the piping

to determine if corrosion is occurring more rapidly than

expected. The licensee also plans to develop a procedure

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to address the installation and precautions necessary for

use of this type of flow element,

IFI (3'02/88-16-04): Review the1 licensee's activities to

develop a procedure for use of flow measuring devices in

the RW system and periodic ultrasonic-testing of RW system

piping.

(e) NRC Region II personnel met with the FPC staff to discuss

the. status of surveillance program improvements in light of

the pervious SALP 3 rating. The licensee described its

overall surveillance improvement program, which included:

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instituting a new computerized Surveillance Tracking

- System to address deficiencies in the area of

surveillance scheduling,

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adopting a ',' system engineer" concept which identifies

a single point of contact for each system in an effort

to. develop expertise in engineers who write

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procedures, and

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rewriting surveillance procedures, as necessary, and

implementing a verification and validation program to

confirm the adequacy of surveillance procedures.

From discussions with the licensee, management attention to

surviellance was evident.

(9) Maintenance Activities (62703) -

The inspector observed

maintenance activities to verify that correct equipment

clearances were in effect; work requests and fire prevention

work permits, as required, were issued and being followed;

quality control personnel were available for inspection

activities as required; and TS requirements were being followed.

Maintenance was observed and work packages were reviewed for the

following maintenance activities:

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Replacement of the power supply for the "D" channel of the

reactor protection system in accordance with procedures

MP-531, Troubleshooting Plant Equipment, SP-110, Reactor

Protective System Functional Testing, SP-312, Heat Balance

Calculations, and SP-113, Power Range Nuclear

Instrumentation Calibration;

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Calibration of the waste gas release flow transmitter

(WD-19-FT) in accordance with procedure SP-168, Radiation

Monitoring Flow Rate Instrumentation Calibration;

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Ultrasonic testing for nuclear services arid decay heat

seawater piping degradation; and

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Troubleshooting of containment hydrogen analyzer (WS-10-CE)

"Standby" indication in accordance with procedure MP-531.

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. No violations or deviations were identified. i

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,(10) Radioactiv'e' Waste Controls (71707) - Selected liquid and gaseous

releases were observed to verify that approved procedures were I

utilized, that ' appropriate release approvals were obtained, and '

that required surveys were taken.

No violations or deviations were identified. l

(11) Pipe Hangers and Seismic Restraints (71707) - Several pipe

hangers and. seismic restraints (snubbers) on safety-related

systems were observed to insure that fluid levels were adequate

and no leakage was evident, that restraint settings were

appropriate, and that anchoring points were not binding.

No violations or deviations were identified.

3. Review of Licensee Event Reports (92700) and Nonconforming Operations

Reports (71707)

a. Licensee Event Reports (LERs) were reviewed for potential generic-

. impact, to detect trends, and to determine whether corrective actions

appeared appropriate. Events which were reported immediately were

reviewed as they occurred to determine if the TS were satisfied.

LERs 87-22, 87-28, 88-03, 88-04, 88-11, and 88-12 were reviewed in

accordance with the current NRC Enforcement policy. LERs 87-22,

87-28, 88-03 and 88-04 are closed.

(1) (Closed) LER 87-22: This LER reported an Engineered Safeguards

(ES) actuation that occurred while electricians were installing

an e ctrical jumper across a pressure switch. The licensee has

revised procedure SP-178, Containment Leakage Test - Type "A",

Including Liner Plate, (revision 13 dated May 3, 1988) to

L require the use of jumper leads with insulated connections.

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l (2) (Closed) LER 87-28: This LER reported an ES system actuation

which occurred during the operation of a vital bus transfer

switch and inverter manual bypass switch. The licensee has

completed the operator training on proper switch operation, and

has provided a schematic diagram of the vital bus power supplies

in the inverter rooms.

(3) (Closed) LER 88-03: This LER reported that a surveillance

procedure was not adequate to implement the 31 day containment

in+egrity verification required by TS 4.6.1.1. The licensee has

implemented enhancements to their TS amendment review process

which will include a list of other technical specifications

requirements most likely affected by the amended specifica+1on.

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. (.4 ) (Closed) LER ' 88-04: This LER reported that the weekly channel

check of the incore detector system was not completed within the

required frequency and that the 1.nitial data collected was not

evaluated 'to determine system operability. The licensee has

removed the applicable channel check instructions from procedure

SP-433, Incore Backup Recorder Calibration, and has incorporated

these instructions'in procedure SP-438, Incore Neutron Detectors

Channel Check. This new procedure has been assigned to reactor

engineering for accomplishment.

LERs 88-11 and 88-12 will remain open for the following reasons:

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(5) (0 pen) LER 88-11: This LER reported that the inservice testing

program valve stroke tot was not performed during the first

three months of 1988 as required by TS 4.0.5. The licensee

identified this matter during a routine review of surveillance

procedures. To prevent recurrence of this event, the licensee

will revise procedure SP-443, Master Surveillance Plan, to

specify surveillance tests subject to the ASME Section XI test

frequencies. The licensee plans to implement this procedure

change by July 15, 1988. This matter is considered to be a

licensee identified violation in which appropriate corrective

action was taken to prevent recurrence.

(6)' (0 pen) LER 88-12: This LER reported the inadequate electrical

isolation betdeen reactor coolant system hot leg. temperature

instruments in the control room and remote shutdown panel. The

licensee identified this matter during an engineering design

review. Upon discovering this situation, the licensee verified

that a previously established roving fire watch was in effect

and continued this compensatory measure until electrical

separation could be provided for this instrumentation. The

licensee installed modifications MAR 82-05-03-06, FCN-23, and

MAR 82-05-03-01, FCN-36A, to provide the required electrical

isotation. This matter is considered to be a licensee

identified violation in which appropriate corrective action was

taken to prevent recurrence.

The licensee's corrective action associated with this event will

include a detailed review of other modifications that interface

with the remote shutdown panel to determine if similar problems

exist. This review will be completed by June 10, 1988. This

LER will remain open pending completion of this corrective

action,

b. The inspector reviewed Nonconforming Operations Reports (NCORs) to

verify the following: TS are complied with, corrective actions as

identified in the reports or during subsequent reviews have been

accomplished or are being pursued for completion, generic items are

identified and reported as required by 10 CFR Part 21, t.nd items are

reported as required by TS.

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All NCORs were reviewed in accordance with the current NRC

Enforcement Policy.

.e (1) NCOR 88-69 reported that on May 14, 1988, the maximum

permissible liquid release rate specified by liquid - radwaste

release permit number L 88-160 was exceeded. This release was

being performed in accordance with procedure OP-407H, Operation

of the Laundry and Shower Monitoring Tanks, which requires in

step . 3.2.S.5 that the release rate specified on the release

permit not be exceeded. The actual release rate of 36 gpm

exceeded the maximum release rate permitted of 34'gpm. Further

review of the post-release records,- however, indicated that no

radiological limits ware exceeded by this event.

The licensee attributed the cause for this event to be the use

of chart paper on the release recorder that indicated only half

of the actual flow. This event is similar to an event which

occurred in September 1987 and was the subject of a NRC

violation (Violation 302/87-30-02). The licensee's corrective

. action for this violation was documented in a response letter to

the NRC dated November 18, 1987, and included, inpart, ordering

new chart paper for the flow rate recorder to indicate the

correct release flow rate.

This corrective action was insufficient to prevent recurrence of

this event. Failure to provide adequate corrective actions is

contrary to the requirements of 10 CFR Part 50, Appendix B,

Criterion XVI and is considered to be a violation.

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Violation (302/88-16-05): Failure to provide adequate

corrective actions to prevent exceeding the maximum release rate

for a liquid radwaste release.

(2) NCOR 88-77 reported that a fire service valve (FSV-14) was found

in the closed position vice the open position required by plant

procedures. The licensee discovered this . situation during the

removal of an equipment clearance (CL-88-05-106) and discovered

that this valve was inadvertently closed during the

implementation of the clearance which specified that a nearby

valve (FSV-13) be closed. The improper implementation of the

clearance rendered two of three fire service pumps out of

service for approximately one day. The TS allows up to 7 days

of operation with only one fire service pump.

As part of their corrective actions associated with this event,

the licensee is reviewing procedures to determine if the

requirement for independently verifying the implementation of

equipment clearances needs clarification. This matter is

considered to be a licensee identified violation in which

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appropriate corrective action will be taken to prevent

recurrence.

IFI (302/88-16-06): Review the licensee's activities to clarify

the requirements .to provide independent verification of

equipment clearances,

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4. Design, Design Changes and Modifications (37700) -

Installation of new or modified systems were reviewed to verify that the

changes were reviewed and approved. in accordance with 10 CFR 50.59, that

the changes were performed in accordance with technically adequate and

approved procedures, that subsequent testing and test results met

acceptance criteria or deviations were resolved in an acceptable manner,

and that appropriate drawings and facility procedures were revised as

necessary. This review included selected observations of modifications

and/or testing in progress.

The folicwing l modification approval records (MARS) were reviewed and/or

associated testing observed:

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Separation of hot leg temperature instrumentation between the remote

shutdown panel and the control room in accordance with modifications

MAR 82-05-03-06, FCN-23, and MAR 82-05-03-01, FCN-36A and functional

test in accordance with procedure TP#11A, RC-004A-TE1 and RC-0048-TE4

Isolation Module; and

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Installation and test of the containment high range radiation monitor

recorder in accordance with MAR 84-08-10-07, FCN-29A and functional

test in accordance with procedure TP#48, MAR Functional Test for RNR

Recorders and Indicator Verification / Calibration.

5. NUREG 0737 - TMI Task Action Plan Item Review (92701)

The licensee's activities associated with the TM1 Task Action Plan Item

II .E.1.1.,

2 , Auxiliary Feedwater System Evaluation, were reviewed. The

licensee has completed construction of the emergency feedwater tank and

has submitted the Probability Risk Analysis (PRA) for the emergency

feedwater system in a letter to the -NRC dated December 2,1986. The

inspector performed a walkdown of the completed tank and verified that the

licensee's system drawings and procedures reflect the "as built" plant

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configuration. The licensee's action on this item is complete and this

item is considered closed.

6. Review of Offsite Review Committee Activities (40701)

-The inspector attended a meeting and reviewed the activities of the

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. licensee's offsite review committee, the Nuclear General Review Committee

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(NGRC). This review included a determination that TS requirements were

being met uith regard to the following:

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Commi ttee' quo' rum;

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Committee composition with respect to disciplines and' expertise;

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Qualification of committee members; and

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Review activities of the committee.

No violations or deviations were identifled.

.7. - Licensee Action on - Previously Identified Inspection Findings (92702 &

92701)

a, (Closed) Violation 302/87-40-01, Failure to Perform Certifications on

Active Clearances as Required by Procedure CP-115

The licensee has revised the distribution list for notification of

open clearances, issued a memorandum dated December 9, 1987,

emphasizing clearance holder responsibilities, and reviewed this

event with operators.

b'. (Closed) Deviation 302/87-19-01, Failure to Meet a Commitment as-

Stated in the Response Letter to Violation- 302/86-31-01 Dated

January 22, 1987-

The licensee has combined its two separate tracking systems to avoid

similar incidents from occurring. In addition, the FSAR was revised

on February 1, 1988, revision 9, to include descriptions for the

normal operation of cooling water systems thct supply cooling water

for.the makeup pumps.

-c. (Closed) .FI 302/86-38-13, Review Completion of Licensee's Long-term

Protective Measures for Sulfur Dioxide Tanks

Corrective actions were . verified as complete, as stated in NRC

Inspection Report 50-302/87-28, with the following exceptions:

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installation of improved door and damper seals to reduce

inleakage into the control room; and

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installation of control logic to reposition the control complex

HVAC system dampers to the recirculation mode in the event toxic

gas is detected at the storage tanks' local monitors.

The licensee completed these modifications in accordance w1th MAR

85-03-10-01. The inspector reviewed the completed modification

package, including work requests and test procedures, and where

possible, conducted visual observations to verify the modification.

The inspector considers action on this item complete,

d. (Closed) IFI 302/88-11-05, Follow the Licensee's Troubleshooting

Activities Associated with Reactor Protection System (RPS) Channel

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The licensee has-identified the most probable cause for the spurious

trips to be. due to a faulty power supply. The power supply has

subsequently been replaced,

e. (Closed); IFI 302/88-01-04, Review the Licensee's Flow Measurement

Test to -Verify Discharge Valve Throttling Method and Pump

Ferformence.

The. inspector ob' served the performance of the flow measurement test

conducted in accordance with procedure PT-319, Discharge Valve

Positioning Verification. This test verified that the discharge-

valve throttling ' method used provided consistent results and that

pump performance did not significantly vary with tide level.

f. (Closed) IFI 302/86-38-07', Review the Licensee's Progress in

Developing ~ Maintenance Procedures to Cover Certain Electrical

Equipment.

The licensee has implemented proce'dures PM-130, Static Inverters, and

MP-152, Performance Checks of Power Supplies, to direct maintenance

activities on the vital inverters. The licensee has decided not to

develop an electrical maintenance procedure for the Emergency Diesel

Generators (EDG) since no significant maintenance has been performed

on these electrical generators in the past. Instead, the licensee

.has implemented a preventive maintenance procedure for this

equipment,. PM-123, Periodic Electrical Checks of Emergency Diesel

Generators, to - direct the periodic maintenance performed or the

EDG's.

g. (Closed) Deviation 302/87-40-03, Failure to Install a Recording

Display as Committed to Meet Regulatory Guide 1.97.

The inspector reviewed and verified the implementation of the

corrective actions stated in FPC's letter of March 16, 1988.

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The

inspector reviewed modification MAR 84-08-10-07, FCN-29A and

functional test procedure TP#4B which installed and tested the

containment high range radiation monitor recorder.

7. Exit Interview (30703)

The inspector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on June 8,1988. During this meeting,

the inspector summarized the scope and findings of the inspection as they

are detailed in this report with particular emphasis on the violations and

IFI's.

-The licensee representatives acknowledged the inspector's comments and did

not identify as proprietary any of the materials provided to or reviewed

by the inspectors during this inspection.

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During the exit meeting, licensee representatives stated that they may.

.take exception _to the violation described in paragraph 2.b,(8)(b) of.this

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-report_'~ regarding the applicability .of RG 1.33 . to certain chemistry

procedures.

8. . -Acronyms and Abbreviations

^ALARA - As Low.As Reasonably Achievable

ASME - American Society of Mechanical Engineers

CCTV ~- Closed Circuit Television

EDG - Emergency Diesel Generators

EF -

Emergency Feedwater

ES ' - Engineered Safeguards

FPC - Florida Power Corporation

-FSAR -

. Final Safety Analysis. Report

IFI -

Inspector Followup Item

.LER -

Licensee Event Report

MAR -

~ Modification Approval Record

ml -

' Milliliters

NCOR - Nonconforming Operations Report

NGRC - Nuclear. General Review Committee

NRC- -

Nucleai Regulatory Commission

PRA - Probablility Risk Analysis

RCA -

Radiation Control Area

RG -

Regulatory Guide

RPS -

Reactor Protection System '

RWP -

Radiation Work Permit

SALP -

Systenatic Assessment of Licensee Performance

STI -

Short' Term Instruction

TMI -

Three Mile Island

TS -

Technical Specification

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