ML20204J804

Insp Rept 50-302/88-26 on 880813-0916.Violations Noted. Major Areas Inspected:Plant Operations,Security,Radiological Controls,Lers & Nonconforming Operations Repts,Facility Mods & Licensee Action on Previous Insp Items

ML20204J804
Person / Time
Site:	Crystal River
Issue date:	10/04/1988
From:	Crlenjak R, Holmesray P, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20204J755	List: ML20204J752 ML20204J774 ML20204J804
References
50-302-88-26, NUDOCS 8810250257
Download: ML20204J804 (13)

See also: IR 05000302/1988026

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NUCLEAR REGULATORY COMMISSION

o REGION 11

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101 MARIETTA ST., N.W.

ATLANTA. GEORGIA 30323

Report No: 50-302/88-26

Licensee: orida Power Corporation

3201 34th Street, South

St. Petersburg, FL 33733

Occket No: 50-302 License No.: DPR-72

Factitty Name: Crystal River 3

Inspection Conducted: August 13 - September 16, 1988

Inspectors: W. $ 4 Jet /0 /[88

Date Signed

P.Aolmes-Ray,SengrRe.identInspector

knvdas u, to M rs

J. Tedro , esidet{ Inspector Da~te' Signed

Approved by:_

R.

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TeAjak, Secj#6fi' Chief V

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/ gate:Gigned

D' ision of Reaftor Projects

SUMMARY

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

the areas of plant operations, security, radiological controls,

Licensee Event Reports and Nonconforming Operations Reports, facility

modifications, 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.

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Rasults: Ona violation and one * unresolved item were identified: Failure to

report a condition prohibited by the technical specifications,

paragraph 3.b(1); Inspection of quality items stored in staging

areas, paragraph 3.b(3).

• Unresolved items are a matter about which more information is required to  ;

determine whether they are acceptable or may involve violttio9s or deviations. ,

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ADOCK 05000302

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1. ' 4 UNITED STATES

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NUCLEAR REGULATORY COMMISSION

REGION 11

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• ,[ 101 MARIETTA ST N.W.

ATLANTA GEORGIA 30323

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Report No: 50-302/88-26

Licensee: Florida Power Corporation

3201 34th Street, South

St. Petersburg, FL 33733

Docket No: 50-302 License No.: OPR-72

Facility Name: Crystal River 3

Inspection Conducted: August 13 - September 16, 1988

Inspectprs: W. 5 /m /0[V[88_

D. fiolmes~-Ray, SengY Resident inspector Dafe $1gnecf-

% &<b

J. Tedro , eside

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nspector

'o M r?

Da'te' Signed

Approved by:

R.

m e ,

rte /Jak, Sec Chief V

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/ffate/ Signed

O' ision of Rea tor Projects

SUMMARY

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

the areas of plant operations, security, radiological controls,

Licensee Event Reports and Nonconforming Operations Reports, facility

modifications, 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. l

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Results: One violation and one * unresolved item were identified: Failure to j

ieport a condition prohibited by the technical specifications,

paragraph 3 b(1); Inspection of quality items stored in staging

areas, paragraph 3.b(3).

• Unresolved items are a matter about which more information is required to

determina whether they are acceptable or may involve violations or deviations.

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REPORT DETAILS

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3. Persons Contacted

Licensee Employees

J. Alberdi, Manager, Nuclear Plant Technical Support

• F. Bailey, Superintendent, Nuclear Projects

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• P. Bassa, Nuclear Security Specialist

• G. Becker, Manager, Site Nuclear Engineering Services

• R. Blume, Nuclear-Team Instructor

• J. Brandely, Manager, Nuclear Integrated Planning

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• J. Bufe'-Carr, Nuclear Regulatory Specialist

. *M. Collins, Superintendent, Nuclear Safety and Reliability

"J. Cooper, Superintendent,-Technical Support

B. Hickle, Manager, Nuclear Plant Operations

• M. Jones, Nuclear Modifications Specialist

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H. Liles, Nuclear Operations Technical Advisor  ;

• S. Mansfield, Nuclear Team Instructor

P. McKee, Director, Nuclear Plant Operations

• L. Moffatt, Nuclear Safety Supervisor (

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R. Murgatroyd, Superintendent, Nuclear Maintenance  ;

• T. Neaman, Nuclear Security Specialist f'

i "J. Roberts, Manager, Nuclear Chemistry

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5. Robinson, Superintendent, Nuclear Chemistry and Radiation "

l Protection

j V. Roppel, Manager, Nuclear Operations Mairtenance and CJtages

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• W. Rossfeld, Manager, Nuclear Compliance

L. Sexton, Senior Nuclear Mechanical Engineer

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• L. Snow, Occuments Clerk I

R. Watts, Manager, Nuclear Operations Purchasing and Contracting

• R. Widell, Director, Nuclear Operations Site Support

• M. Williams, Nuclear Regul't:*, Specialist i

Other licensee employees contacted included office, operations,

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engineering, maintenance, chemistry / radiation and corporate personnel, j

Pinkerton Corporation  !

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• F. Harman, Project Manager

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"Attended exit interview

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Acronyms and initialisms used throughout this report are listed in the  ;

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2. Review of Plent Operations (71707)

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

inspection period.

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.

The following records were reviewed:

Shift Supervisor's Log; Rea(tor Operator's iog; 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 deviations 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 observat'ons were conducted

during backshif ts. 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.

suring these tours, the following observations were made:

(1) Morttoring 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 Spent Fuel (SF) system to verify that the lineup

was in accordance with license requirements for system

operability and that the system drawing and procedure correctly

reflect "as-built" plant coaditions.

No violations or deviations were identified.

(3) Shif t Staffing (71707) - The inspector verified that operating

shift staffing was in accordance with TS requirements and that

control room operations were being conducted in an orderly and

professional manner. In addition, the inspector observed shif t

turnovers on various occasions to verify the continuity of plant

status, operational problems, and other pertinent 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 observa-

tions 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

ciothing;

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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 monitoring 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

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controls were adequate.

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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

program.

During a tour of the Auxiliary Building (AB) the inspector -

noted a lot of trash and debris in a contamirated area in the

"Green Room". This area is used to compact solid radioactive

waste. A significant amount of air flow through this room was

also noted, however no spread of contamination appeared to be

occurring. During meetings with licensee management personnel,

the potential spread of contamination from this situation was

discussed.

No violations or deviations were identified.

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

activities, the in< : ctor included a review of the licensee's

physical security program, lhe composition of the security

organization was checked to insure that the minimum number of

guards were available and that security activitiqs were

conducted with proper supervision. The performance of various

shif ts 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

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 lichting, prot < ;ed and vital

area barrier integrity, and the :ecuri., or va . ' ' tion interface

with operations and maintenance.  ;

No violations or deviations were identified. ,

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(7) Fire Protection (71707) - Fire protection activities, staffing

and equipment were observed to verify that fire brigade staffing

was appropriate and that fire alaemt, 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; cualified

personnel were conducting the tests; tests were at.eqLate to l

verify equipment operability; calibrated equipment was utilized;

and TS requirements were followed.

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The following tests were observed and/or data reviewed:

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SP-130, Engineered Safeguards Monthly Functional

Tests;

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SP-300, Operating Daily Surveillance Log;

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SP-317, RC System Water Inventory Balance;

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SP-323, Evacuation and Fire Alarm Demonstration;

and,

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SP-340B, "B" Train ECCS Pump and Valve Quarterly

Operability Test.

No violations or deviations were identified.

(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 folicwed;

quality control personnel were available for inspection

activities tr. required; and TS requirements were being followed.

Maintenance was observed and work packages were reviewed

for the following maintenance activities:

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Inspection of the Nuclear Services and Decay Heat Seawater

(RW) system for foreign material;

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Testing of Emergency Feedwater Initiation and Control

(EFIC) relays in accordance with procedure PM-167, EFIC

Time Delay Relay Testing;

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Troubleshooting and calibration of Reactor Coolant System

Pressure Transmitter RC-3A-PI3; and

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Testing and cleaning of the circuit breaker for the "C"

Makeup and Purification Pump (MVP-lC) in accordance with

procedure PM-101, 4.16 KV and 6.9 KV Switchgear.

No violations or deviations were identified.

(10) 9adioactive Waste , Controls (71707) - Selected liquid releases

were observed to verify that approved procedures were utilized,

that appropriate release approvals were obtained, and that

required surveys were taken.

No violations or deviations were identified.

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

hangers and seismic restraints (snubbers) on safety-related

systems were observed to assure fluid levels were adequate

and no leakage was evide:1t, restraint settings were appropriate,

and 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 that were reported immediately were ,

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

LERs 88-12 and 88-15 were reviewed in accordance with the current NRC

Enforcement Policy.

(1) (Closed) LER 88-12: This LER reported the inadequate electrical

isolation between reactor coolant syLtem hot leg temperature

instruments. This LER was previously dircussed in NRC

Inspection Report 50-302/88-16. The licensee's review of other

modifications that interface with the remote shutdown panel has

been completed and no similar problems were identified. The

licensee concluded that the design error which caused this

situation was an isolated case.

(2) (Cpen) LER 38-15: This LER reported that components tssociated

with the main feedwater startup block valves were not

environmentally qualified. This matter is discussed in more

detail in NRC Inspection Report 50-302/88-27. The licensee is

developing a schedule to replace all nonqualified components

associated with these valves and will submit this information in

a supplement to the LER by January 31, 1989. This LER will

remain open pending issuance of the supplement and completion of

the licensee's 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 baen

accmlished or are being pursued for completion, generic items are

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

reported as required by TS.

All NCORs were reviewed in accordance with the current NRC

Enforcement Policy.

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(1) NCOR 88-90 reported that surveillance procedure SP-430,  ;

Containment' Air Locks Seal Leakage Test, was . inadequate to

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implement the requirements of TS 4.6.1.3. This TS requires that

the containment air lock shall be demonstrated operable after

each opening by pressurizing the door seals and verifying that

seal leakage is within limits. The TS further requires that

this test pressure be stabilized for at least 15 minutes prior

to verifying the leakage rate. The licensee discovered that l

from April 21, 1988 to May 28, 1988, an air lock was opened on

approximately 15 different occasions and the leakage test was

j performed without the required 15 minute stabilization. time.

10 CFR 50.73 (a)(2)(1)(B) requires that a LER be submitted ,

within 30 days of the event for any operation or condition  :

prohibited by the TS. Although this matter was identified by '

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the licensee on July 12, 1988, this matter was not repor*ed to

the NRC within 30. days as required by 10 CFR 50.73 ar.d is

considered to be a violation.

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Violation (302/88-26-01): Failure to report a condition -

prohibited by the TS as required by 10 CFR 50.73.

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(2) NCOR 88-93 reported that the impeller nut for the "B" Nuclear

Services Closed Cycle Cooling Pump (SWp-18) was found loose

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during recent pump maintenance. Although this condition did not

cause the pump's impeller to become loose and thereby render the

pump inoperable, the potential existed to do so. The licensee

has noticed this same condition on the impeller nuts for pump

SWP-1A and also the "A" Decay Heat Closed Cycle Cooling Pump i

(DCP-1A). The licensee has replaced these impeller nuts with

new nuts and has applied a thread securing compound to secure  ;

i the nut in place. The licensee plans to inspect other similar

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safety related pumps, and make appropriate repairs if necessary, .

I and is reviewing this matter to determine if 10 CFR Part 21 is

applicable.

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IFI (302/88-26-02): Follow licensee's activities to inspect i

safety related pumps for loose impeller nuts and determination l

of 10 CFR Part 21 reportability. }

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$ (3) NCOR 88-100 reported that periodic in'pections of some quality i

storage items were not being performea as required by Regulatory

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Guide 1.38. The licensee identified that ome items being i

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stored in "staging" areas were not inspected. The licensee uses (

these staging areas to assemble parts and equipment necessary l

. for the performance of plant work and modifications. The

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! licensee has taken interim action to remove the items from the

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staging areas and is inspecting these items prior to returning

i them to the appropriate storage area. The licensee is also

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evaluating new methods for performing these inspections in the

future. This item is considered unresolved pending NRC review l

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of the inspection results for. items stored in the scaging areas

and development of new methods for performing the inspections.

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Unresolved Item (302/88-26-03): Review. inspection results of

qmlity items stored in staging areas and development 'of new

methods for performing periodic inspections.

(4) NCORs88-101, 88-104, and 88-105 reported that battery charger

output shunt devices .were not being calibrated. The voltage

across these shunts was used in previous surveillance tests to

4 measure charger output current as required by the TS.  ;

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Subsequent calibration of' these devices by the licensee

determined that they were out of tolerance in the conservative

direction and the battery chargers were capable of supplying the

i required current. The applicable surveillance procedure has

been revised to require the use of a portable battery load test

device which has an installed calibrated shunt to measure

charger output curreat, and this procedure has been performed

i satisfactory on both battery banks. New shunts are presently

, being ordered and will be installed in the battery chargers.

The licensee also plans to include the battery charger shunts in

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the PM-200 calibration program. This matter is considered to be

a licensee identified violation in which appropriate corrective ,

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action was taken to prevent recurrence. The licensee's

corrective action will be followed by an IFI.

IFI (302/88-26-04): Review the licensee's activities to install

, new shunt devices in the battery chargers and include these -

devices in the PM-200 calibration program.

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(5) NCOR 88-108 reported that modification reviews failed to provide l

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adequate guidance for High Energy Line Break (HELB)  ;

considerations. One main steam line was walked down to assess *

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the HELB qualification of equipment installed subsequent to  ;

, original construction. The licensee's analysis stated in  !

conclusion that the potential targets affected by breaks in the

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one main steam line are not configured such that the operability

. of any system to mitigate a steam line break is affected.

! The licensee has a plan for completion of analy is of the other l

i HELR areas. The resident inspectors will follow the licensee's i

progress. ,

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

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

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changes were ovaluated and approved in accordance with 10 CFR 50.59, that j

] the changes were performed in accordance with technically adequate and  ;

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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 following modification approval records (MARS) were reviewed and/or

associated testing observed:

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MAR 88-01-21-0) , Install Backflow Preventer in Auxiliary Building

Demineralized Water Line; and

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MAR 87-07-23-01, Replacement of Toxic Gas Monitors.

5. Licensee Action on Previously Identified Inspection Findings (92702 &

92701)

a. (Closed) IFI 302/88-14-05: Review the revision and revalidation of

procedure PM-123, Periodic Electrical Checks of Emergency Diesel

Generators.

The licensee has revised procedure PM-123 (revision 8 dated July 19,

1083) to correct the identified problems. A field validation was

again performed to ensure the procedure could be performed as

written.

b. (Closed) Unresolved ! tem 302/88-06-01: Review the licensee's

detailed evaluation of the effect of uncilibrated instrumentation.

The licensee has completed their detailed evaluation of

instrumentation which was overdue for calibration. The licensee did

not identify any unresolved safety concerns and the function of

safety systems was not adversely affected.

c. (Closed) IFI 302/83 14-H: Review the licensee's revision to

procedure SP-340A, "A" Train ECCS Pump and Valve Quarterly

Oogrability Test.

The licensee has revised procedure SP-340f, (eevision 11 dated July

20, 1988) to reflect the correct stroke time for valve MOV-69 and has

also clarified which locations pump vibration measurements are to be

obtained. 1

d. (0 pen) IFI 302/88-18-03: Review the licensee's revisions to the TS

and applicable surveillance procedures to reflect the increased

containtrent leakage test pressure (Pa).

In the process of verifying the maximum Reactor Builoing (RB)

pressure following a Loss of Coolant Accident (LOCA), the licensee i

discovered that the maximum temperature assumed to exist in the RB '

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before the accident occurs was 110 degrees Fahrenheit (F) instead_of

the maximum 130 F RB temperature that is allowed by the TS. The '

average RB temperature is routinely as high as 124 F. Subsequent

reanalysis of the maximum RB pressure possible following a LOCA with  :

the 130 F initial RB temperature produced a slightly higher traximum .

accident pressure of 53.3 psig (0.7 psig increase). This pressure is [

still below the RB design pressure of 55 psig. The licensee plans to -

revise the TS and applicable surveillance procedures to reflect a Pa ,

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of 53.3 psig.

e. (Closed) IFI 302/87-16-02: Review the licensee's activities to

determine the cause for component contamination and review of IE

Circular 77-14.

As discussed in NRC Inspection Report 50-302/88-11, this item ,

i remained open pending the installation of a backflow preventer in the

demineralized water supply line to the AB and the establishment of

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3 administrative controls for valve 00V-128. The licensee has i

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completed modification MAR 88-01-21-01, Install Backflow Preventer.in  :

AB DW Line, and has revised procedure OP-416, Domestic Water Supply ,

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Syster.i (revision 23 dated July 15, 1988), to require that valve

00V-129 be maintained locked closed.

I f. (Closed) IFI 87-40-06: Review the licensee's investigation regarding  ;

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the size and location of control transformers for valves MUV-23 and

MUV-25.

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The licensee reviewed modification and work socumentation associated

with these valves and was unable to determine the cause for the

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oversized transformers. The licensee has determined that these

! transformers are more than sufficient for the design application and

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has revised applicable plant drawings to correctly reflect what is

installed in the field.

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6. Exit Interview (30703)  !

1 The inspector met with licensee representatives (cer.oted in paragraph 1)  !

3 at the conclusion of the inspection on September 16, 1988. During this i

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meeting, the inspector summarized the scope and findings of the inspection  !

as they a*e detailed in this report with particular emphasis on the  :

. violation, unresolved item and inspector followup items.  ;

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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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Item Number Description and Reference

50-302/88-26-01 Violation - Failure to report a condition

prohibited by the TS as required by 10 CFR 50.73.

50-302/88-26-02 IFI - Follow licensee's activities to inspect

safety related pumps for loose impeller nuts and

determination of 10 CFR Part 21 reportability.

50-302/88-26-03 UNR - Review inspection results of quali ty items

stored in staging areas and aevelopme..; of new

.?athods for performing periodic inspections.

50-302/88-26-04 IFI - Review tne licensee's activities to install

new shunt devices in the battery chargers and

include these devices in the PM-200 calibration

program.

7. Acronyms and Abbreviations

AB - Auxiliary Building

ALARA - As low As Reasonably Achievable

CCTV - Closed Circuit Television

CFR - Code of Federal Regulations

ECCS - Emergency Core Cooling System (s)

EFIC - Emergency Feedwater Initiation and Control

F - Fahrenheit

HELB - High Energy Line Breaks

IFI - Inspector Followup Item

LER - Licensee Event Report

LOCA - Loss of Coolant Accident

MAR - Modification Approval Record

NCOR - Nonconforming Operation Report t

NRC - Nuclear Regulatory Commission

RB - Reactor Building  !

RCA - Radiation Control Area

RC - Reactor Coolant

RW - Nuclear Services and Decay Heat Seawater System i

- Raciation Work Permit

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RWP

SF - Spent Fuel

SP - Surveillance Procedure

STI - Short Term Instruction

TS - Technical Specification

UNR - Unresolved Item

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