ML20234E250

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Insp Rept 50-382/87-15 on 870817-21.No Violations or Deviations Noted.One Unresolved Item Identified.Major Areas Inspected:Liquid & Gaseous Radwaste Programs
ML20234E250
Person / Time
Site: Waterford Entergy icon.png
Issue date: 09/15/1987
From: Chaney H, Murray B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20234E236 List:
References
50-382-87-15, NUDOCS 8709220323
Download: ML20234E250 (10)


See also: IR 05000382/1987015

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APPENDIX

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report:

50-382/87-15

License:

NPF-38

Docket:

50-382

Licensee: Louisiana Power & Light Company (LP&L)

317 Baronne Street

New Orleans, Louisiana

70160

Facility Name:

Waterford Steam Electric Station, Unit 3 (Wat-3)

s

Inspection At:

Taft, St. Charles Parish, Louisiana (Wat-3 Site)

Inspection Conducted: August 17-21, 1987

Inspector:

///N

H. E. Chaney, Radiatiorf Specialist

Dtite /

OFacilitiesRadiologicalProtectionSection

Approved:

M

/ k

B."Murray, Chief ~, Faci

ies Radiological

Dpe /

Protection Section

Inspection Summary

Inspection Conducted August 17-21, 1987 (Report 50-382/87-15)

Areas Inspected:

Routine, unannounced inspection of the liquid and gaseous

radioactive waste programs.

Results: Within the areas inspected, no violations or deviations were

identified. One unresolved item (control of radioactive contamination, see

paragraph 3) was identified.

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8709220323 870918

PDR

ADOCK 05000382

0

PDR

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DETAILS

1.

Persons Contacted

LP&L

  • R.P.Barkhurst,VicePresident, Nuclear (SiteDirector)
  • S. Alleman, Assistant Plant Manager
  • N. S. Carns, Plant Manager
  • W. T. LaBonte, Radiation Protection Superintendent
  • P. N. Backes, Nuclear Quality Assurance Manager
  • T. F. Gerrets, Acting Nuclear Services Manager
  • A. S. Lockhart, Nuclear Operations Support and Assessment Manager
  • J. M. O'Hern, Technical Support Training Superintendent
  • H. C. Lesan, Engineering Technician, Nuclear
  • J. A. Ridgel, Assistant Radiation Protection Superintendent
  • G. E. Wuller, Operational Licenting Supervisor
  • D. A. Rothrock, Operational Licensing Engineer

P. Kelley, Health Physics (HP) Technician Supervisor

D. Hoel, HP Supervisor

R. Kenning, Engineering Technician, Nuclear

B. Goldman, ALARA Supervisor / Coordinator

P. V. Prasankumar, Technical Support Superintendent

T. O. Gray, Operations Quality Assurance (QA) Supervisor

J. E. Howard, Technical Specification Surveillance Coordinator

T. Payne, Instrument and Controls (I&C) Superintendent

R. J. Matherne, I&C Supervisor

C. L. Boudreaux, Maintenance Training Supervisor

H. C. Waldrop, Nuclear Auxiliary Operator

J. Comeaux, Nuclear Plant Operator

R. P. Lee, QA Auditor

K. P. Boudreaux, Health Physics Technician

R. M. Lunn, I&C Technician

W. H. Currey, I&C Technician

R. Allen, Senior Engineer, Chemistry

R. Seidl, I&C Design Supervising Engineer

Others

  • T. R. Staker, Resident Inspector, NRC
  • M. E. Skow, inspector, NRC

S. T. Clark, HP Consultant, NUMANC0

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G. V. Policastro, HP Consultant, IRM

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  • Denotes those attending the exit interview held on August 21, 1987.

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2.

Open Items Identified During This Inspection

An open item is a matter that requires further review and evaluation by

the NRC inspector. Open items are used to document, track, and ensure

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adequate followup on matter of concern to the NRC inspector. The

folicwing open items were identified:

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Open Item

Title

See Paragraph

382/8715-01

Radiation Monitoring System

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382/8715-02

Radiation Monitoring System Training

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382/8'il5-03'

Liquid and Gaseous Effluent Release

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Record Storage

382/8715-04

Radiation Protection Personnel Fire

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Drill Support

382/8715-05

Waste Gas Holdup System Explosive

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Gas Monitoring System

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3.

Unresolved Item

An unresolved item is a matter about which more information is required to

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ascertain whether it is an acceptable item, a deviation, or a violation.

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The following unresolved item was identified:

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Unresolved

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Item No.

Title

See Paragraph

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382/8715-06

Radioactive Contamination Control

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and Procedural Compliance

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Program Areas Inspected

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The following program areas were inspected.

Unless otherwise noted, the

inspection was completed and revealed no violations, deviations,

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unresolved items, or open items. Notations after a specific inspection

item are used to identify the following:

I = item not inspected or only

partially inspected; V = violation; D = deviation; U = unresolved item;

and 0 = open item.

Procedure

Program Area and Inspection Requirements

83722

Organization and Management Controls (Radwaste)

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02.01 - Organization

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02.02 - Staffing

02.04 - Identification and Correction of Weaknesses

02.05 - Audits and Appraisals - 0 (see paragraph 7)

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83522

Organization and Management Controls (Radwaste)

02.01 - Organization, Responsibilities, and Authorities

02.02 - Staffing

02.03 - Identification and Correction of Weaknesses

02.04 - Audits and Appraisals

02.05 - Communication to Employees

02.06 - Documentation and Implementation

83723

TrainingandQualifications(Radwaste)

02.01 - Adequacy of Training - 0 (see paragraph 6)

02.02 - Employee Knowledge - 1

02.03 - Transportatiori/Radwaste Training - 1

02.04 - Qualification Requirements

02.05 - New Employees

02.06 - INP0 Accreditation

02.07 - Audits and. Appraisals

02.08 - Training Not Covered by INP0 - I

83523

TrainingandQualifications(Radwaste)

02.01 - Training and Qualifications Program

02.02 - Education and Experience

02,03 - Adequacy and Quality of Training

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84723

Liquid Radioactive Wastes

02.01 - Audits and Appraisals

02.02 - Program Changes

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02.03 - Effluents

02.04 - Instrumentation

02.05 - Reactor Coolant and Secondary Water

84523

Liquid Radioactive Waste

02.01 - Construction and Installation of Liquid Waste System

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02.02 - Liquid Leakage, Overflow, and Spillage

02.03 - Sampling

02.04

Preoperational Test Program - I

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02.05

Completion of Preoperational Test Program - I

02.06 - Installation,(Calibration, and Testing of Process

Monitors - 0 see paragraph 5)

02.07 - Procedures

84724

_Gpseous Radioactive Wastes

02.01 - Audits and Appraisals

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02.02 - Program Changes

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02.03 - Effluents

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02.04 - Instrumentation

~02.05 - Air Cleaning Systems - I

02.06 - Programs, Plans, and Procedures

84524

Gaseous Radioactive Waste

'02.01 - Construction and Installation of Gaseous Waste

System - I

02.02 - Sampling

02.03 - Preoperational Test Program - I-

02.04 - Completion of Preoperational Test Program - I.

02.05 - Installation, Calibration, and Testing of Process

Monitors - 0 (see paragraph 5)

02.06 - Procedures

90713

Review of Periodic and Special Reports

02.01 - Report Content

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02.02 - Verify Test Results

02.03 - Ascertain Adequacy of Corrective Actions - 0 (see

paragraph 9)

02.04 - Determine Classification of Report Contents

02.05 - Document Review and Closeout - U (see paragraph 10)

83726

Control of Radioactive Materials and Contamination, Surveys,

and Monitoring

02.01 - Audits and Appraisals

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02.02 - Changes

02.03 - Surveys and Monitoring - 0 (see paragraph 8)

02.04 - Radioactive Materials ard Contamination Controls

5.

Process and Effluent Monitoring System

The licensee's radiation monitoring system (RMS) for radioactive

liquid /gasevus process, effluent, accident monitors has experienced a

large amount of downtime.

The RMS is a General Atomics (GA) computer

based system comprised of both GA and Nuclear Measurement

Corporation (NMC) instruments.

These monitors involve both Technical

Specification (TS) required monitors and non-TS monitors.

The NRC

inspector determined that the licensee had a backlog of maintenance and

calibrations actions for several non-TS monitors due to priority being

given to the maintenance and calibration of TS monitors.

The NRC inspector observed maintenance operations on selected RMS

moniters, interviewed personnel, and inspected training programs and

qualification records.

The licensee's RMS problems appear to be due to a

combination of system design, component operation, and component

environmental qualification.

These aforementioned factors have required

continuous maintenance work on the RMS T,o maintain its operability.

The

NRC inspector determined that the licensee had apparently complied with

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all TS required action items concerning the monitors addressed in the TS

when.they were determined to be out-of-service.

The NRC inspector.noted during reviews of the licensee's Plan of the Day

meeting reports that approximately six to as many as eighi, TS required

effluent and reactor accident monitors were declared out-of-service on

August-18-21, 1987, due to maintenance problems.

On August 21, 1987,

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neither the liquid or the gaseous effluent monitors were' operational due

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to component problems.

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The NRC inspector determined that the licensee's I&C group which is

responsible for maintaining the RMS had undergone a reduction-in-force.

This reduction of I&C technicians appeared to contribute to the

maintenance backlog problem.

At the exit interview on August 21, 1987,

the licensee committed to the NRC inspector to provide at least three

additional RMS qualified I&C technicians for RMS associated work.

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'he licensee had determined, prior to this inspection, that they could

obtain better reliability in the RMS by replacing the five, high

maintenance, NMC monitors (gaseoas, liquid, and boron waste management

systems, steam generator blowdown system, ana the chemical and volume

control system) with similar GA components.

Replacement of the NMC

components will be completed during the second cycle refueling outage.

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The NRC inspector discussed the need to review equipment performance

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trends and correlate the data with I&C technician observed and perceived

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field problems with the RMS.

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This~is considered an open item pending licensee completion of I&C

staffing and review of RMS equipment performance trends (382/8715-01).

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6,

Training

The NRC inspector inspected the licenree's training programs for Nuclear

Auxiliary Operators, I&C technicians, and radiation protection pcrsonnel

regarding radioactive effluent controls, effluent sampling, RMS operation,

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maintenance, cali.bration, effluent discharge procedures, and plant system

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training.

Even though the licensee's training program for radiation personnel

address RMS operations, the NRC inspector determined that Lesson

Plans H040-022-00 and H040-021-00, dated September 1986, contained

incorrect system descriptions and an incorrect lesson plan title.

The NRC

inspector also determined that the performance based qualification

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sign-off logs (No. 3 and 4) for senior radiation protection personnel did

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not adequately address the performance aspects necessary for assignment of

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duties involvina effluent sampling, counting room operations, or RMS

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operation.

This is considered an open item pending licensee completion of

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personnel training and revision of lesson plans and qualification sign-off

logs (382/8715-02).

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7.

-Record Storage

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The NRC inspector reviewed licensee audits of the radioactive effluent

controls and determined that, among other findings, audit SA-87-013.1,

dated June 1987, identified deficiencies in the licensee's plant wide

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protection provided official records (Quality Notice QA-87-084).

During the review of radioactive effluent discharge records, the NRC

inspector noted that the licensee maintained effluent discharge records

required by TS 6.10.3 in a. temporary storage area in the health physics

office area pending transfer to the permanent plant storage area.

These

records were not being provided adequate fire protection during-interim

storage in the health physic's office.

The records were comprised of 1986

liquid and gaseous effluent discharge documents.

The NRC inspector

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determined that the licensee had develcped a procedure-(HP-1-173, " Records

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Preparation, Collection and Storage") that would provide appropriate

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instruction.s on transmitting and storage of effluent records.

In a

July 22, 1987, memorandum to the QA Department, the Radiation Protection

Superintendent stated that the aforementioned procedure would be

implemented when the 1-hour, fire rated, lockable file cabinets were

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received.

As of this inspection, the file cabinets had not been received

onsite.

The licensee committed to the NRC inspector during the exit

interview on August 21, 1987, that alternate protective storage for the

effluent discharge documents would be provided pending arrival of the fire

rated file cabinett.

This is considered an open item pending licensee

completion of actions to provide proper record storage for health physics

records and other appropriate plant records.

(382/8715-03)

8.

F_ ire Drill

The NRC inspector observed a fire drill involving the Radwaste Compaction

Building.

The NRC inspector discussed the following observations with

licensee representatives following the drill and at the exit meeting on

August 21.

Scenario:

A hydraulic fluid fed fire is burning within the sheet metal radwaste

compacting building.

Several plastic bags of compacted trash were

supposedly burning.

The building, located outside of the power block,

normally houses only low level radioactivity waste.

From the prompter's

description of the fire inside the building, the NRC inspector determined

that the building's thin sheet metal wall or roof would have been

breached.

Observations:

a.

The responding radiation protection technicians relied on the rescits

of a week old radiation survey of the building in lieu of providing

fire fighters with portable radiation monitoring instruments other

than pocket dosimeters.

External radiation surveys of the building

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would have been appropriate due to the. compactor's location near a

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thin sheet metal wall and relative small-size of the building.

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b.~

Responders did not anticipate the need to isolate fire fighting water

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runoff from the storm drain system or the need to sample runoff for

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radioactivity.

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c.

Radiation protection personnel failed to assess down wind airborne

radioactivity levels or the need to temporarily evacuate personnel

from those areas until surveys had been completed.

d.

The fire brigade's hand-held 2-cell flash lights appeared to be

inappropriate for use in a small building containing burning plastics

which generate' dark sooty smoke.

High intensity lighting would seem

to be more appropriate.

e.

The NRC inspector noted that radiation protection personnel kept

returning to other work areas to obtain equipment and supplies.

The

NRL inspector discussed the need for prestaged kits to support fire

fighting operations outside of the power block.

9.

Waste Gas Holdup System Hydrogen and Oxygen Monitoring System

During a review of the licensee's submitted Semiannual Radioactive

Effluent Release Reports for the yeare 1985 and 1986, the NRC inspector

noted that the licensee had been routinely reporting that the TS 3.3.3.11

required Waste Gas Holdup System Explosive Gas Monitoring

System (WGS/EGMS) has been inoperable.

This condition has existed since

March 1985 following initial plant startup.

Based on reviews of reports and interviews with knowledgeable licensee

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personnel, the NRC inspector determined that the WGS/EGMS has suffered

from poor initial system design, poor installation, and failure of vendor

supplied replacement equipment.

The licensee is currently meeting

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TS 3.3.3.11 actions statements by sampling the Waste Gas Holdup System at

4-hour intervals and analyzing the samples onsite.

The licensee's latest

endeavor to make the WGS/EGMS operational is a complete replacement of the

rnalyzing equipment, using a different equipment vendor, and modifying

(Station Modification 818) the inplant sampling facilities so that

hydrogen and oxygen sampling safety parameters can be met.

The WGS/EGMS

modifications are scheduled to be completed during the second refueling

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outage.

This is considered an op-en item pending licensee completion of the

modifications to the WGS/EGMS.

(382/8715-05)

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10.

Followup on Licensee Event Reporting (LER)

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(Closed) LER 382/87-003:

Technician Wore Contaminated Clothing Offsite

Due to Failure to Follow Procedures - The event the LER describes occurred

on January 21-22, 1987, and was discussed in HRC Inspection

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Report' 50-382/87-08.

The licensee has completed an investigation of the

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event.

Based on a review of the licensee's final report and subsequent QA

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audits and surveillance (QS-87-007 and'SA-87-024.1, respectively), it

appears that the licensee's corrective actions have not been effective in

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correcting the problem.

This concern is considered an Unresolved Item

pending further NRC review to determine the effectiveness of the

licensee's corrective actions concerning the problems identified in

LER 87-003 and the subsequent investigation (382/8715-06),

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(Closed) LER 382/G7-011:

Eff?uent Radiation Monitor Setpoint Higher Than

Required Due to Personnel Error - The event the LER describes occurred on

March 30,.1987, and involved the Gaseous Waste Management Effluent

P.adiation Monitor (PRM-IRE-0648).

The licensee discovered that'the alarm

setpoint for this monitor was set by a factor.10 above the required

setpoint.

This condition had existed since startup of the plant and was

caused by an engineer that calculated the setpoint not taking into,

consideration certain interfacing system parameters and data conversion

factors.

The licensee has hired a consultant to review the entire

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Radiation Monitoring System data base and basis for setpoints on all

monitors.

The licensee's short and long term corrective actions appear to

be sufficient to prevent a recurrence of the problem.

(Closed) LER 382/87-15: Control Room Emergency Ventilation Actuation Due

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to Radiation Monitoring Spike - The event the LER describes occurred on

May 18, 1987, and involved the Control Room Outside Air Intake (CRCAI)

radiation monitor.

The licensee determined that this recurring problem

was caused by two types of unwanted current flow (electrical noise)

factors (multiple ground connections in detector circuits, and current

induction in detector cables due to the energizing and deenergizing of

either of two large inductive relays) which caused detector spiking.

The

licensee has installed nylon shoulders and flat washers on detector mounts

to isolate grounding electrical noise, and R-C filters for suppression of

high frequency noise generated by the relays.

The licensee's actions

aFpear to have effectively reduced the spurious actuations of this

emergency system due to the aforementioned sources.

(Closed) Special Report 382/87-002:

High Range Gas Monitor Inoperable

Greater than 7 Days - This Special Report describes the licensee's actions

when the Fuel Handling Building Emergency Exhaust High Range Gas Monitor

(PRM-IRE-3032) was declared inoperablo due to a faulty display module.

Tne monitor was out of commission for greater than 7 days due to a lack of

qualified onsite spare display modules, and a delay in obtaining a

replacement display module from the vendor.

The licensee established

compensatory measures per TS 3.3.3.1 Action Statement 27 and station

Procedure EP-2-050, "Off-Site Dose Assessment (Manual)."

11.

Exit Interview

The NRC inspector met with the NRC resident inspector and licensee

representatives denoted in paragraph 1 on August 21, 1987, and summarized

the scope and findings of the inspection as presented in this report.

The

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licensee committed to the following regarding the Radiation Monitoring

System concerns:

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a.

Increase the number of I&C technicians involved with RMS maintenance

and calibration to reduce the maintenance backlog.

b.

Assign a dedicated engineer to managed and coordinate RMS activities.

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