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Partially Withheld Insp Rept 50-285/86-07 on 860301-31 (Ref 10CFR73.21).Violation Noted:Failure to Maintain Vital Area Security Barrier in Accordance W/Regulations
	ML20195F263
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
ML20195F258	List: ML20195F256; ML20195F263;
References
	50-285-86-07, 50-285-86-7, NUDOCS 8606110263
	Download: ML20195F263 (10)
	v • d • e

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APPENDIX B

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-285/86-07 Licensa: 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: March 1-31, 1986

Inspector: _

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P.' H. HarreYl, Tenipf Resident Reactor D6ter

Inspector

Approved:

D. R. Hunter, Chief, Project Section B, Date

3/8

Reactor Projects Branch

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Inspection Sumary

Inspection Conducted March 1-31, 1986 (Report 50-285/86-07)

Areas Inspected: Routine, unannounced inspection including operational safety

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

walkdowns, followup on previously identified items, followup on licensee event

reports, and review of plant procedures program.

Results: Within the eight areas inspected, one violation (failure to maintain

a vital area security barrier in accordance with regulations, Appendix A) was

identified.

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DETAILS

1. Persons Contacted

R. Andrews, Nuclear Production Division Manager

C Brunnert, Quality Assurance Supervisor

M. Core, Maintenance Supervisor

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

W. Gates, Plant Manager

R. Johansen, Test Engineer

M. Kallman, Security Supervisor

L. Kusek, Operations Supervisor

T. McIvor, Technical Supervisor

R. Mueller, Plant Engineer

D. Hunderloh, Licensing Engineer

G. Roach, Chemical and Radiation Protection Supervisor

J. Tesarek, Reactor Engineer

D. Trausch, Operations 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.

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2. Followup on Previously Identified Items

(Closed) Unresolved Item 285/8002-01: Licensee to provide data for

containment leakrate test.

The licensee has provided the data as requested by the NRC

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inspector. No additional action is required.

l (Closed) Severity Level IV Violation 285/8415-01: Failure to inspect

critical quality equipment (CQE) material.

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The licensee has reviewed all open CQE requisitions / purchase

orders to verify that no other material, other than that

identified by the NRC inspector, had entered the plant without

the proper receipt inspection. The results of the review

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indicate that no other material was installed in the plant

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without the proper receipt inspection being performed. The

licensee has also taken actions to prevent recurrence of this

problem. The actions taken include installing a sign at the

plant entrance to warn personnel not to bring material in the

plant without the proper receipt inspection, enhancing CQE

receipt inspection requirements at general employee training

sessions, and instructing security guards not to allow material

received during off-normal hours to enter the plant. The

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licensee has made the appropriate procedure changes to include

the requirements. The NRC inspector has reviewed the actions

listed above to verify that the actions were appropriately

completed. No problems were noted.

(Closed) Severity Level IV Violation 285/8515-03: Failure to perform

routine surveillance for toxic gas monitors.

The licensee has revised Form FC-71 to include a requirement for

recording toxic monitor readings on a shift basis. The NRC

inspector reviewed Form FC-71 and verified the form was changed

and that the readings were being recorded. The NRC inspector

also reviewed other changes in the Technical Specification

amendments to verify that the licensee has properly incorporated

the requirements into appropriate procedures. No problems were

noted during the review.

(Closed) Deviation 285/8527-01: Failure to meet a commitment relative

to the cleanliness of fluid systems.

To ensure that personnel involved in establishing cleanliness

control conditions are aware of all the applicable program

requirements, the licensee issued a memorandum to quality

control, plant engineering, and maintenance personnel. This

memorandum explains what actions are required for maintaining

system cleanliness. The NRC inspector reviewed routine

operational and maintenance activities during this inspection

period to verify tne requirements for system cleanliness were

being met. No problems were noted.

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(Closed) Severity Level V Violation 285/8527-03: Failure to display

l security badge while in protected area.

The licensee has issued a memo to each badge holder to remind

them of the requirement for displaying their security badges

while inside the protected area. The licensee has also posted

signs .it the entrance to the protected area to remind

individuals of the requirement. The NRC inspector has reviewed

the wearing of security badges by personnel while in the

protected and vi?.al areas. No problems were no+,ed.

j 3. Licensee Event Report (LER) Followup

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Through direct observation, discussions with licensee personnel, and

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

that reportability requirements were fulfilled, immediate corrective

action was accomplished, and corrective action to prevent recurrence has

been accomplished in accordance with Technical Specifications.

The LERs listed below are closed:

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LER 84-020 reported the inoperability of hydrogen analyzer VA-81A due to

improper replacement of the catalyst bed / cell. During performance of the

calibration procedure for VA-81A, it was discovered that the analyzer

would not calibrate properly. An investigation was performed and it was

determined that the analyzer catalyst bed / cell had been installed

incorrectly during modification activities. The investigation also noted

that the calibration performed after the modification was completed had

been performed incorrectly by the technician due to the technician failing

to follow the procedure. The catalyst bed / cell was immediately

reinstalled correctly and calibrated to verify operation. The licensee

appropriately disciplined the technician for failing to correctly follow

procedure. The licensee revised the analyzer calibration procedure to

provide further assurance against a recurrence of the problem. The

licensee also issued a postmaintenance operability check procedure for the

analyzers. To ensure that postmaintenance operability checks are

performed on plant equipment, the licensee has added a blank to the

maintenance order form for quality control personnel to sign to verify the

necessary operability checks have been performed. The NRC inspector

reviewed the actions taken by the licensee in this area and noted no

problems.

LERs84-023, 84-025, and 85-002 reported initiation of the ventilation

isolation actuation system (VIAS) due to leaks in various systems caused

by different problems. LER 84-023 discussed five VIAS initiations due to

leakage from the pressurizer spray valve. The initiation occurred while

shutting down the plant to repair the spray valve leakage.

LER 84-025 reported a VIAS initiation due to a leaking valve in the waste

gas vent header. LER 85-002 discussed an initiation of the VIAS due to a

l leak on a charging pump suction line. In each of the above cases, when

l the VIAS initiation occurred, all activities associated with venting

operations were suspended. A search was conducted to locate the source of

the activity and immediate action taken to stop the leak. In each of the

above occurrences, none of the releases experienced exceeded Technical

Specification or 10 CFR Part 20 limits. This was confirmed by analyses

performed by the licensee.

LER 85-001 reported a case where the VIAS was initiated due to a chemistry

technician purging the reactor coolant sample line in preparation for

drawing a sample. The chemistry technician purged the line too long,

causing a buildup of radioactive gasses released by the reactor coolant.

This buildup of gasses initiated a VIAS. There was no release exceeding

Technical Specification or 10 CFR Part 20 limits as determined by a

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licensee analysis. A review of procedures and sampling operations was

performed. No problems were identified. The importance of not greatly

exceeding minimum purge times was emphasized to the plant staff.

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LER 85-003 reported an actuation of the VIAS during the transfer of spent

resin. The VIAS initiation was caused when the ion exchanger was purged

with nitrogen gas after the resin had been transferred to the spent resin

storage tank. When the nitrogen gas purge was performed, a mixture of

nitrogen / radioactive gas carried through the drain line, causing an

actuation of the VIAS. During this transfer operation, the VIAS was

initiated twice, each time for the same reason. In each case, the

licensee performed an analysis to verify the release to the atmosphere did

not exceed Technical Specification or 10 CFR Part 20 limits. A review was

performed of the controlling procedure and the actual operation. No

problems were noted. This evolution has been performed since this

occurrence without a VIAS initiation.

LER 85-007 reported the initiation of the VIAS during a refueling

shutdown. The licensee was in the process of testing the containment

stack gas monitor to prove operability. The test was being performed in

accordance with Si approved procedure. The procedure required that

containment pressure be reduced to atmospheric before opening the purge

valves. Due to an inaccurate indication, containment pressure was

slightly greater than atmospheric when the purge valves were opened. This

caused a VIAS initiation. The licensee performed an analysis to determine

the magnitude of the release. The results indicated that no Technical

Specification or 10 CFR Part 20 limits were exceeded.

No violations or deviations were identified.

4. 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. 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, recorder traces, annunciators, panel indications, and

switch positions complied with the appropriate requirements.

. Proper return to service of components.

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Maintenance orders had been initiated for equipment in need of

maintenance.

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. Appropriate conduct of control room and other licensed operators.

No violations or deviations were noted.

5. 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 vital area

security barrier was not being maintained in accordance with regulations.

The discussion of the details of this occurrence contains safeguard

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

discussed in Appendix A of this inspection r6 port.

6. Safety-Related System Walkdowns

l The NRC inspector walked down accessible portions of the following

safety-related systems to verify system operability. Operability was

i determined by verification of valve and/or switch positions. The systems

were walked down using the drawings and procedures noted:

. Fire protection system (Drawing 11405-M-266, Revision 31 and

Procedure OI-FP-6, Revision 46).

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Electrical distribution, 480-volt system (Drawing 8.1-1, Revision 21,

and Procedure OI-EE-2, Revision 8).

i . Electrical distribution, 125 volt DC system (Drawing 8.1-1,

Revision 21, and Procedure OI-EE-3, Revision 17).

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. Electrical distribution, 125-volt AC system (Drawing 8.1-1,

Revision 21 and Procedure OI-EE-4, Revision 24).

During the walkdown of the fire protection system, the NRC inspector noted

minor discrepancies of an 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 walkdown of the electrical distribution system, numerous

apparent discrepancies were noted on the procedures and the electrical

distribution one-line diagram. None of the noted discrepancies affected

the operability or safe operation of the system. However, the apparent

discrepancies affect the correctness of the procedures and the drawing.

At the end of this inspection period, the discussion regarding the

apparent discrepancies had not been completed. For this reason, this

portion of the inspection will be completed during the next inspection

period.

No violations or deviations were identified.

7. Monthly Maintenance Observation

The NRC inspector reviewed 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 reviews:

. The limiting conditions for operation were met while systems or

components were removed from service.

. Approvals were obtained prior to initiating the work.

. 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 reviewed the following maintenance activities:

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. Repairing of a gasket leak on high pressure safety injection valve

HCV-383-4 (M0 854112).

. Repairing of a fire barrier penetration (M0 854210).

. Cleaning of letdown control valve LCV-101-1 (M0 854227).

. Rebuilding air regulator for steam supply to auxiliary feed pump

valve YCV-1045A (M0 857014).

. Repairing seal leaks on charging pump CH-1A (M0 861214).

. Packing leak repair on high pressure safety injection valve HCV-315

(MO 854361).

. Repairing of jockey fire pump discharge check valve (M0 861214).

. Adjusting alarm on containment stack monitor RM-051 (M0 854586).

. Repairing of high pressure safety injection isolation valve HCV-2987

(M0 860725).

No violations or deviations were noted.

8. 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:

I . 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 teet.

. Deficiencies identified during the testing were properly reviewed and

resolved by appropriate management personnel.

The NRC inspector witnessed the following surveillance test activities.

The procedures used for the test activities are noted.

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. Containment monitoring isolation valves (ISI-VA-1-F.1).

. Process monitors (ST-RM-2-F.5).

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

The NRC inspector also reviewed the results of other surveillance tests

performed during this inspection period. The review was performed to

verify the tests were completed as required by the Technical

Specifications, regulations, and procedure. No problems were noted with

the 27 completed surveillance tests reviewed.

No violations or deviations were identified.

9. Review of Plant Procedures Program

The NRC inspector performed a review of the plant procedures program to

verify overall plant procedures are in accordance with regulatory

requirements, temporary procedures and procedure changes are made in

accordance with Technical Specification requirements, and the technical

adequacy of the reviewed procedures is consistent with desired actions and

modes of operation. The review included the following items:

. Procedure changes were made to reflect Technical Specification or

license revisions.

. Changes made to procedures were in conformance with 10 CFR

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Part 50.59 requirements.

. Temporary procedures were properly approved and did not conflict with

Technical Specification requirements.

The NRC inspector reviewed the procedures listed below:

Number Title Revision

OP-1 Master Checklist for Startup or Trip 24

Recovery

0P-3 Plant Startup from Hot Standby to 22

Minimum Load

01-SI-l Safety Injection (Normal Operation) 34

OI-CH-1 Chemical and Volume Control System 12

(Normal Operation)

OI-MS-2 Operating Instructions in Steam System 14

Cold St rtup

OI-RC-4 Reactor Coolant System Normal Shutdown 42

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01-RPS-1 Rea-tor Protective System (Normal 7

Operation)

A0P-6 Emergency Fire Procedure 0

A0P-18 Loss of Raw Water 0

A0P-1 Acts of Nature 0

A0P-7 Forced Evacuation of Control Room 0

OP-10-Al Raw Water Supply Header Flow Low 8

G-17 Maintenance Orders 35

3 0-22 Containment Access & Egress 2

MP-CH-24 Letdown Strainer Cleanout 1

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MP-IC-2 Incore Instrumentation Guide Tube 1

Cleaning

MP-MS-1 Main Steam Safety Valve Inspection 11

and Repair

MP-N0ZDAM-1 Steam Generator Nozzle Dam 2

Installation Procedure

MP-SCIV-1-B Repacking of HCV-347 and HCV-348 1

No violations or deviations were identified.

10. Exit Interview

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The NRC inspector met with Mr. R. L. Andrews and other members of the OPPD

staff at the end of this inspection. At this meeting, the inspector

summarized the scope of the inspection and the findings.

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ML20195F263

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