ML20198T162

Partially Withheld Insp Rept 50-285/86-10 on 860401-30 (Ref 10CFR73.21).Violation Noted:Inadequate Physical Barrier for Protected Area.Major Areas Inspected: Operational Safety Verification & Followup on LERs

ML20198T162
Person / Time
Site:	Fort Calhoun
Issue date:	06/03/1986
From:	Harrell P, Hunter D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20198T129	List: ML20198T126 ML20198T162
References
50-285-86-10, NUDOCS 8606110351
Download: ML20198T162 (8)

See also: IR 05000285/1986010

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APPEf1 DIX B

U.S. f:UCLEAR REGULATORY C0fMISSION

REGI0ft IV

flRC Inspection Report: 50-285/86-10 License: DPR-40

Docket: 50-285

Licensee: Omaha Public Power District

1623 Harney Street

Omaha, Nebraska , 68102

Facility Name: Fort Calhoun Station

Inspection At: Fort Calhoun Station, Blair, Nebraska

Inspection Conducted: April 1-30, 1986

Inspector: .

4 #4

( T. W. harrell7 Senior /esident Reactor D(te'

1. F Inspector

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Approved: ,

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D. R. Hunter, Chief, Project Section B, Mte '

Reactor Projects Branch

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Inspection Surmiary

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Inspection Conducted April 1-30, 1986 (Report 50-285/86-10)

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Areas Inspected: Routine, unannounced inspection including operational safety

verification, maintenance, surveillance, plant tours, safety-related system

walkdowns, followup on licensee event reports, and followup on a

l request from the NRC regional office regarding shipment of uranium hexafluoride

j cylinders.

Results: Within the seven areas inspected, one violation (an inadequate

physical barrier for ' he protected area, Appendix A) was identified.

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DETAILS

1. Persons Contacted

• W. Gates, Plant Manager

C. Brunnert, Operations Quality Assurance Supervisor

M. Core, Maintenance Supervisor

D. Dale, Quality Control Inspector

J. Fisicaro, Nuclear Regulatory and Industry Affairs Supervisor

J. Foley, I&C and Electrical Field Maintenance Supervisor

M. Kallman, Security Supervisor

L. Kusek, Operations Supervisor

T. McIvor, Technical Supervisor

R. Mueller, Plant Engineer

C. Norris, Radiological Services Supervisor

G. Roach, Chemical and Radiation Protection Supervisor

J. Tesarek, Reactor Engineer

S. Willrett, Administration Services and Security Supervisor

• Denotes attendance at the monthly exit interview.

The inspector also contacted other plant personnel, including operators,

technicians, and administrative personnel.

2. Followup on Previously Ideatified Items

(Closed) Open Item 8602-03: Replacement of a railroad tie support for

a uranium hexafluoride (UF6) cylinder.

The licensee completed shipment of the UF6 cylinders from the

site on April 15, 1986. Replacement of the railroad tie was no

longer required.

(Closed) Open Item 8602-09: Removal of dead vegetation in the UF6

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storage area.

The licensee completed shipment of the UF6 cylinders from the

site on April 15, 1986. Removal of the dead vegetation was no

longer required.

3. Licensee Event Report (LER) Followup

Through direct observation, discussions with licensee personnel, and

review of records, the following event reports were reviewed to determine

that reportability requirements were fulfilled, immadiate corrective

action was accomplished, and correct:ve action to prevent recurrence has

been accomplished in accordance with Technical Specifications.

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The LERs listed below were closed:

85-10 Relay failure during a surveillance test

85-11 Loss of offsite power during a refueling outage

85-12 Failure to properly post a fire watch

LER 85-10 reported a problem with an 86-type lockout relay that failed to

properly function during a monthly surveillance test. The relay is part

of the containment spray logic and was being tested during a refueling

shutdown. The licensee determined that the reason for the relay failure

to operate properly was due to a contact being out of adjustment. The

contact was adjusted, the relay reinstalled, and the test performed. No

additional problems were noted. The licensee checked other 86-type

lockout relays but noted no other problems.

LER 85-11 discussed an event that occurred during performance of

maintenance activities on the electrical distribution system. While in a

refueling shutdown, the plant was in an altered electrical lineup when an

individual performing maintenance on the transformer supplying onsite

electrical loads from offsite inadvertently tripped the incorrect relay

causing a loss of offsite power. The loss of offsite power caused the

loss of power to all 480-volt AC buses,125 volt DC bus 2, and 125 volt AC

instrument buses B and D. The buses were reenergized within approximately

30 minutes. Even though the electrical distribution system was degraded,

no safety significant problems were encountered. The licensee has

reviewed this problem with operating personnel to ensure personnel do not

place the plant's electrical distribution system in a position where loss

of one power source will degrade the system. The licensee also stressed

to operating personnel, the need for controlling maintenance activities to

ensure maintenance is not performed on redundant equipment at the same

time. The licensee stressed to maintenance personnel the importance of

ensuring the component being worked on is the correct one.

LER 85-12 reported the failure to properly post a fire watch when the

Halon system for the switchgear room was secured. The failure to properly

establish a continuous fire watch was determined by the license. to be due

to personnel not clearly understanding the fire watch requireme rts.

Instead of posting a full-time fire watch as required by the Technical

Specifications, the fire watch was posted only during welding activities.

The licensee has revised the procedures that establish the requirements

for posting and maintaining fire watches. It appears that the revised

procedures will establish the necessary requirements to ensure fire watch

activities will be properly controlled in the future.

No violations or deviations were identified.

4. Followup on a Regional Request

Based upon a request from Region IV, the NRC inspector reviewed the

licensee's activities associated with shipment of the uranium hexafluoride

(UF6) cylinders offsite. The licensee shipped 52 cylinders to a

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Department of Energy facility in Paducah, Kentucky, via semitrucks.

Shipment of the cylinders commenced on April 4 and was completed on

April 15, 1986.

The NRC inspector observed licensee activities associated with the

preparation and loading of the cylinders. This review was performed to

verify that activities were conducted in accordance with approved

procedures and Materials License SMC-1420. The items reviewed / observed by

the NRC inspector are listed below:

. Lifting equipment had been satisfactorily tested prior to use

. Appropriate individuals were present during lifting and shipping

operations

. Job briefings were performed prior to commencing activities

. Each individual involved in the lifting and shipping activities were

trained in appropriate actions in the event of a cylinder rupture or

other anomaly

. Radiation surveys were performed prior to departure of cylinders from

the site

. Cylinders were inspected and determined to be structurally

. satisfactory before shipment

. Repair to cylinders was performed for the cylinders requiring repair

. Plant review committee. approved procedures were used and followed

. Documentation for offsite shipment was completed

Based on the reviews performed and observations by the NRC inspector, it

appears that the licensee completed shipment of the UF6 cylinders in

accordance with procedures and other requirements.

No violations or deviations were identified.

5. Performance of a Regulatory Effectiveness Review

A team of inspectors from the NRC's Nuclear Material Safety and Safeguards

(NMSS) Office performed a review of the security program at the plant

site. The review was performed from April 28 to May 2 and included a

detailed evaluation of the licensee's security program. The senior

resident inspector participated as a member of the review team. The

results of the review will be discussed in detail in a report to be issued

by NMSS.

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6. Operational Safety Verification

The NRC inspector conducted the reviews and observations described below

to verify that facility operations were performed in conformance with the

requirements established under 10 CFR, administrative procedures, and the

Technical Specifications.

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The NRC inspector made several control room

observations to verify:

. Proper shift staffing

. Operator adherence to approved procedures and Technical

Specifications

. Operability of reactor protective system and engineered safeguards

equipment.

. Logs, records, .ecorder traces, annunciators, panel indications, and

switch positions complied with the appropriate requirements.

. Proper return to sers'ce of components.

. Maintenance orders had been initiated for equipment in need of

maintenance.

. Appropriate conduct of control room and other licensed operators.

No violations or deviations were noted.

7. Plant Tours

The NRC inspector conducted plant tours at various times to assess plant

and equipment conditions. The following items were observed during the

tours:

. General plant conditions.

. Equipment conditions, including fluid leaks and excessive vibration.

. Plant housekeeping and cleanliness practices including fire hazards

and control of combustible material.

. The physical security plan was being implemented in accordance with

the station security plan.

. Adherence to the requirements of radiation work permits.

. Work activities being performed in accordance with approved

procedures.

During a tour of the plant, the NRC inspector noted that a protected area

security barrier was not being maintained in accordance with requirements.

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The discussion of the details of this occurrence contains safeguards

information, as defined in 10 CFR Part 73.21; therefore, the details are

discussed in the attachment to Appendix A of this inspection report.

8. Safety-Related System Walkdowns

The NRC inspector walked down accessible portions of the following

safety-related systems to verify system operability. Operability was

determined by verification of valve and switch positions. The systems

were walked down using the drawings and procedures noted:

. Auxiliary feedwater system (Drawings M-253, Revision 50 and M-254,

Revision 55, and Procedures OI-FW-4, Revision 28 and 01-AFW-1,

Revision 1).

. Raw water system (Drawing M-100, Revision 26 and Procedure 01-RW-1,

Revision 13).

During the walkdowns, the NRC inspector noted minor discrepancies of an

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editorial nature between the drawings, procedures, and plant as-built

conditions. None of the conditions noted affected the operability or safe

operation of the system. Licensee personnel stated that the noted minor

discrepancies would be corrected.

During the previous inspection period, as a result of a system walkdown,

the NRC inspector noted discrepancies in the procedure and on the station

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one-line electrical diagram for the plant. At the end of the inspection

period, the NRC inspector was still attempting to resolve the

discrepancies with licensee personnel. The licensee has resolved the

discrepancies and has determined that the discrepancies do not affect the

operability or safe operation of the plant. The NRC inspector concurred

with tha results of the licensee's review. In an effort to upgrade system

procedures and drawings, the licensee has instituted a program to perform

wa14 downs of all plant systems. The result of the program will be

procedures and drawings that will reflect the as-built plant.

No violations or deviations were identified.

9. Monthly Maintenance Observation

The NRC inspector observed station maintenance activities of

safety-related systems and components to verify the maintenance was

conducted in accordance with approved procedures, regulatory requirements,

and the Technical Specifications. The following items were considered

during the observations:

. The limiting conditions for operation were met while systems or

components were removed from service.

. Approvals were obtained prior to initiating the work.

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. Activities were accomplished using approved maintenance orders (MO)

and were inspected, as applicable.

. Functional testing and/or calibrations were performed prior to

returning components or systems to service.

. Quality control records were maintained.

. Activities were accomplished by qualified personnel.

. Parts and materials used were properly certified.

. Radiological and fire prevention controls were implemented.

The NRC inspector observed the following maintenance activities:

. Radiation portal monitor annual calibration (CP-PM/8).

. Evacuation of UF6 cylinders (SP-UF6-3).

. Replacement of valve on UF6 cylinders (M0 861469).

. Loading of UF6 cylinders (M0 861454).

No violations or deviations were noted.

10. Monthly Surveillance Observation

The NRC inspector observed the Technical Specification required

surveillance testing on safety-related systems and components. The NRC

inspector verified the following items during the testing:

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. Testing was performed using approved procedures.

. Test instrumentation was calibrated.

. Limiting conditions for operation were met.

. Removal and restoration of the affected system and/or component were

accomplished.

. Test results conformed with Technical Specification and procedure

requirements.

. Test results were reviewed by personnel other than the individual

directing the test.

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. Deficiencies identified during the testing were properly reviewed and

resolved by appropriate management personnel.

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The NRC inspector witnessed the following surveillance test activities.

The procedures used for the test activities are noted.

. Station battery checks (ST-0C-1-F.1).

. Auxiliary feedwater pump check (ST-FW-1-F.2).

. Diesel generator monthly test (ST-ESF-6-F.2).

. Containment hydrogen monitor checks (ST-VA-6-F.2).

No violations or deviations were identified.

11. Exit Interview

The NRC inspector met with Mr. W. G. Gates (Plant Manager) at the end of

this inspection. At this meeting, the inspector summarized the scope of

the inspection and the findings.

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